ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 265

DOE Review Release 01/26/2010

Document Title:

Hanford Site – Occupational External Dose

Document Number: ORAUT-TKBS-0006-6

Revision: 04

Effective Date: 01/07/2010

Type of Document: TBD

Supersedes: Revision 03, ORAUT-OTIB0030 Rev 00 PC-1

Subject Expert(s): Fred Duncan and Edward D. Scalsky

Site Expert(s): John J. Fix 

Approval: Signature on File Approval Date: 01/05/2010

Fred Duncan, Document Owner

Concurrence: Signature on File Concurrence Date: 01/05/2010

Chris M. Tornes, Objective 1 Representative

Concurrence: Signature on File Concurrence Date: 01/05/2010

Scott R. Siebert, Objective 3 Representative

Concurrence: Signature on File Concurrence Date: 01/06/2010

James P. Griffin, Deputy Project Director

Approval: Signature on File Approval Date: 01/07/2010

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 2 of 265

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

10/10/2003 00 First approved issue. Initiated by Edward D. Scalsky.

01/09/2004 01 Approved Issue of Revision 01. Initiated by Edward D. Scalsky.

10/05/2006 01 PC-1 Approved page change revision to add updated required language 

on page 8 in Section 6.1. Adds Purpose Section (6.1.1) and Scope 

Section (6.1.2) to page 9. Makes reference to ORAUT-OTIB-0017 

on page 10 in Section 6.2 for guidance to be used. Adds two 

references to pages 56 and 58 in Reference Section. No changes 

occurred as a result formal internal review. Incorporates NIOSH 

formal review comments. This revision results in no change to the 

assigned dose and no PER is required. Training required: As 

determined by the Task Manager. Initiated by Edward D. Scalsky.

Signature on File 09/02/2006

Edward D. Scalsky, Document Owner

Signature on File 09/05/2006

John M. Byrne, Task 3 Manager

Signature on File 09/29/2006

Edward F. Maher, Task 5 Manager

Signature on File 10/03/2006

Kate Kimpan, Project Director

Brant A. Ulsh Signature on File for 10/05/2006

James W. Neton, Associate Director for Science

11/21/2006 02 Approved Revision 02 to incorporate SC& A comments and 

responses to claimant concerns. Constitutes a total rewrite of 

document. Incorporates internal and NIOSH formal review 

comments. This revision results in no change to the assigned dose 

and no PER is required. Training required: As determined by the 

Task Manager. Initiated by Edward D. Scalsky.

06/05/2007 03 Approved revision initiated to include Attributions and Annotations. 

No further changes occurred as a result for formal internal review. 

Incorporates formal NIOSH review comments. This revision results 

in no change to the assigned dose and no PER is required. Training 

required: As determined by the Task Manager. Initiated by Edward 

D. Scalsky

01/07/2010 04 Revision initiated to incorporate neutron and photon measurement 

data collection and analysis of Hanford once-through cooling 

production reactors, 200 Area Plutonium Facilities, 300 Area and 

Miscellaneous Research Facilities with potential neutron exposure, 

and coworker analyses previously contained in ORAUT-OTIB-0030. 

Incorporated formal internal and NIOSH review comments. 

Constitutes a total rewrite of the document. Training required: As 

determined by the Objective Manager. Initiated by Fred Duncan.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 3 of 265

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations .............................................................................................................12

6.1 Introduction ............................................................................................................................15

6.1.1 Purpose......................................................................................................................16

6.1.2 Special Exposure Cohort Petition Information for Hanford.......................................... 16

6.1.3 Scope.........................................................................................................................16

6.2 MED/AEC/DOE External Radiation Dosimetry .......................................................................17

6.2.1 History of Radiation Safety Guidance ......................................................................... 17

6.3 Hanford Operations................................................................................................................17

6.3.1 Radiation Safety Practices.......................................................................................... 19

6.3.1.1 Radiological Record Practices................................................................... 19

6.3.2 Incidents.....................................................................................................................20

6.4 Dose Reconstruction Parameters...........................................................................................22

6.4.1 Hanford Historical Administrative Practices ................................................................ 22

6.4.2 Hanford Personnel Dosimetry Technology.................................................................. 24

6.4.2.1 Beta/Photon Radiation Personnel Dosimeters........................................... 25

6.4.2.2 Neutron Radiation Personnel Dosimeters.................................................. 27

6.4.3 Calibration and Dosimeter Response Characteristics ................................................. 28

6.4.3.1 Hanford Beta/Photon Dosimeters.............................................................. 28

6.4.3.2 Hanford Beta/Photon Dosimeter Response 

Characteristics .......................................................................................... 29

6.4.3.3 Hanford Neutron Dosimeters..................................................................... 30

6.4.3.4 Hanford Neutron Dosimeter Response Characteristics ............................. 31

6.4.4 Workplace Radiation Fields ........................................................................................ 32

6.4.4.1 Beta/Photon Radiation .............................................................................. 32

6.4.4.2 Workplace Beta/Photon Dose Fraction...................................................... 32

6.4.4.3 Neutron Radiation ..................................................................................... 32

6.4.4.4 Workplace Neutron Dose Fraction............................................................. 37

6.5 Monitored Hanford Workers–Measured Dose ........................................................................38

6.5.1 Photon Dose Adjustments .......................................................................................... 39

6.5.2 Photon Organ Dose Conversion Factors .................................................................... 39

6.5.3 Neutron Dose Adjustments......................................................................................... 39

6.5.4 Neutron Weighting Factor........................................................................................... 40

6.6 Monitored Hanford Workers – Missed Dose...........................................................................40

6.6.1 Photon Missed Dose .................................................................................................. 41

6.6.2 Neutron Missed Dose ................................................................................................. 42

6.7 Unmonitored Hanford Workers...............................................................................................42

6.7.1 Coworker Assigned Photon Dose ............................................................................... 42

6.7.2 Construction Trade Workers....................................................................................... 44

6.7.3 Neutron-to-Photon Dose Ratio.................................................................................... 44

6.7.3.1 100 Area Single-Pass Cooling Reactors.................................................... 45

6.7.3.2 100 Area N Reactor................................................................................... 48

6.7.3.3 200 Area Plutonium Facilities .................................................................... 51
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6.7.3.4 300 Area Reactor, Plutonium and Miscellaneous Hanford 

Research Facilities.................................................................................... 54

6.7.3.5 NP Dose Ratio Summary .......................................................................... 56

6.8 Uncertainty.............................................................................................................................56

6.8.1 Measured Photon Dose.............................................................................................. 57

6.8.2 Measured Neutron Dose............................................................................................. 59

6.8.3 Measured Beta Dose.................................................................................................. 60

6.9 Shallow Dose.........................................................................................................................62

6.9.1 Assigned Shallow Dose.............................................................................................. 62

6.9.2 Assigned Extremity Skin Dose.................................................................................... 62

6.9.3 Assigned Pre-October 1944 Extremity and Skin Dose................................................ 63

6.10 Non-Site-Specific Factors.......................................................................................................64

6.10.1 Adjustment for Glovebox Workers .............................................................................. 64

6.10.2 Construction Trade Workers....................................................................................... 64

6.11 Attributions and Annotations ..................................................................................................64

References ........................................................................................................................................69

Glossary ............................................................................................................................................90

ATTACHMENT A, WORKPLACE NEUTRON SPECTRA MEASUREMENTS ................................. 100

A1. 100 Area Reactor Facilities ..................................................................................................100

A2. 200 and 300 Area Plutonium Facilities .................................................................................101

A3. Neutron Energy Spectra.......................................................................................................102

ATTACHMENT B, HANFORD COWORKER DOSE ASSIGNMENT................................................ 106

B1. Purpose ...............................................................................................................................106

B2. Background..........................................................................................................................106

B3. Applications And Limitations ...............................................................................................107

B4. Hanford Coworker Data Development.................................................................................. 108

B5. Hanford Coworker Annual Dose Summaries........................................................................ 109

B6. Penetrating Dose Values Based on ORAUT-OTIB-0052 Guidance for 

Selected Construction Trade Workers..................................................................................111
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ATTACHMENT C, SKIN DOSE ASSIGNMENT FOR HANFORD CASES ....................................... 114

C1. General Information .............................................................................................................114

C2. Procedure ............................................................................................................................115

ATTACHMENT D, HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED 

EVENTS AT HANFORD.....................................................................................118

D1. Radiation Protection.............................................................................................................118

D2. Historical Timeline................................................................................................................122

ATTACHMENT E, A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON 

MEASURED PHOTON DOSE AT 100 AREA N REACTOR FACILITY 

OPERATIONS AT THE HANFORD SITE........................................................... 200

E1. Executive Summary .............................................................................................................201

E2. Introduction ..........................................................................................................................202

E3. Site Profile Neutron Dose Reconstruction Recommendations.............................................. 203

E4. History..................................................................................................................................203

E4.1 Facility Design .......................................................................................................... 204

E4.2 N Reactor Operation................................................................................................. 205

E5. Radiation Protection Practices .............................................................................................206

E6. Methods ...............................................................................................................................207

E6.1 Site Expert Interviews............................................................................................... 207

E6.2 Data Capture............................................................................................................ 207

E6.3 DOE REIRS Data ..................................................................................................... 208

E6.4 U.S. Nuclear Regulatory Commission (NRC) Studies of Commercial 

Nuclear Plants .......................................................................................................... 208

E7. Results.................................................................................................................................208

E7.1 Site Expert Interviews............................................................................................... 208

E7.2 Dosimeter Recorded Photon Dose ........................................................................... 210

E7.3 N Reactor Reports, Policies and Procedures............................................................ 211

E7.4 Query of N Reactor Workers Dosimeter Measured Neutron and 

Photon Dose............................................................................................................. 213

E7.5 DOE REIRS Annual Dose Summaries...................................................................... 217

E7.6 UNC Annual Exposure Summaries........................................................................... 218

E7.7 NRC measured neutron and photon doses in commercial nuclear 

plants........................................................................................................................ 218

E8. Summary .............................................................................................................................219
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ATTACHMENT F, A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON 

MEASURED PHOTON DOSE AT 200 AREA PLUTONIUM FACILITY 

OPERATIONS AT THE HANFORD SITE........................................................... 220

F1. Executive Summary .............................................................................................................221

F2. Introduction ..........................................................................................................................222

F3. History..................................................................................................................................223

F3.1 200 Area Plutonium Facilities ................................................................................... 223

F4. Plutonium grade...................................................................................................................229

F5. Radiation Protection.............................................................................................................229

F6. Methods ...............................................................................................................................230

F6.1 Site Expert Interviews............................................................................................... 230

F6.2 Data Identification..................................................................................................... 231

F6.3 Data Capture............................................................................................................ 231

F7. Results.................................................................................................................................231

F7.1 Site Expert Interviews............................................................................................... 231

F7.2 Workplace Measurements of Neutron Radiation....................................................... 234

F7.3 Technical Reports..................................................................................................... 234

F7.4 Radiation Survey Data.............................................................................................. 237

F7.5 Analysis of NP Ratio Measurement Data.................................................................. 237

F7.6 Recommended NP Ratios ........................................................................................ 247

ATTACHMENT G, A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON

MEASURED PHOTON DOSE AT HANFORD 300 AREA AND 

MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE ........... 250

G1. Executive Summary .............................................................................................................251

G2. Introduction ..........................................................................................................................251

G3. History..................................................................................................................................255

G3.1 Hanford 300 Area Plutonium and Site Miscellaneous Facilities................................. 255

G3.1.1 Test Reactor Facilities............................................................................. 255

G3.1.2 Critical Mass Laboratory Facilities ........................................................... 256

G3.1.3 Radiological Calibration Laboratory Facilities .......................................... 257

G3.1.4 300 Area Laboratory Facilities................................................................. 257

G3.2 Facilities Operational in the 1940s............................................................................ 257

G3.3 Facilities Operational in the 1950s............................................................................ 258

G3.4 Facilities Operational in the 1960s............................................................................ 258

G4. Radiation Protection.............................................................................................................258

G5. Methods ...............................................................................................................................259

G5.1 Site Expert Interviews............................................................................................... 259

G5.2 NTA Results Database ............................................................................................. 259

G5.3 Data Identification..................................................................................................... 259
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G5.4 Data Capture............................................................................................................ 259

G6. Results.................................................................................................................................260

G6.1 Site Expert Interviews............................................................................................... 260

G6.2 NTA Processing Files ............................................................................................... 261

G6.3 Workplace Measurements of Neutron Radiation....................................................... 262

G7. Technical Reports ................................................................................................................262

G8. Radiation Survey Data .........................................................................................................263

G8.1 Analysis of Neutron to Photon Dose Ratio................................................................ 265

G9. Summary .............................................................................................................................265
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 8 of 265

LIST OF TABLES

TABLE TITLE PAGE

6-1 Hanford pre-1965 radiation protection procedures manuals ................................................... 19

6-2 Historical Hanford recorded dose practices............................................................................ 20

6-3 Hanford historical dosimetry systems..................................................................................... 25

6-4 Analysis of multielement film dosimeter dose......................................................................... 31

6-5 Hanford workplace photon spectra measurements................................................................. 33

6-6 Workplace measured nonpenetrating and penetrating collective doses ................................. 34

6-7 Beta and photon radiation energies and percentages for Hanford facilities ............................ 34

6-8 Hanford workplace neutron spectra measurements ............................................................... 36

6-9 Parallel workplace measured NTA and HMPD neutron dose ................................................. 37

6-10 AEC Study NP dose ratios ..................................................................................................... 38

6-11 Hanford facility neutron dose fractions ................................................................................... 39

6-12 Conversion from NCRP 38 neutron quality factors to ICRP 60 weighting 

factors....................................................................................................................................40

6-13 Hanford beta/photon dosimeter period of use, type, LOD, exchange 

frequency, and potential annual missed dose......................................................................... 42

6-14 Hanford neutron dosimeter period of use, type, LOD, exchange 

frequency, and potential annual missed dose......................................................................... 43

6-15 Lognormal parameters of NP ratio for Hanford reactors ......................................................... 47

6-16 Operating history of Hanford single-pass production reactors ................................................ 47

6-17 Lognormal parameters of NP ratio for Hanford N-Reactor...................................................... 51

6-18 Hanford 200 Area plutonium facility NP ratio survey records.................................................. 51

6-19 Lognormal parameters of NP ratios for Hanford 200 Area plutonium 

facilities ..................................................................................................................................54

6-20 Measured measured neutron dose rates for Hanford 200 Area plutonium 

facilities ..................................................................................................................................54

6-21 Summary of measured neutron dose rates for application to Hanford 300 

Area and Hanford facilities with some potential for neutron exposure .................................... 55

6-22 Hanford NP dose ratio summary ............................................................................................ 56

6-23 Bias and variance features for Hanford film dosimeter records .............................................. 57

6-24 Uncertainty in beta/photon Hp(10) in Hanford facilities............................................................ 58

6-25 Overall bias and uncertainty due to variation and uncertainties regarding 

energy levels and geometry in recorded dose as an estimate of deep 

dose.......................................................................................................................................59

6-26 Test irradiations–thermal neutrons ......................................................................................... 60

6-27 Test irradiations–fast neutrons ............................................................................................... 61

6-28 Relative error values for electron exposure of Hanford film dosimeters, 

1950–1964.............................................................................................................................62

6-29 Maximum assigned pre-October 1944 skin dose in Hanford reactor fuel 

fabrication ..............................................................................................................................64

A-1 Laboratory-measured dose fractions from PuF4 ................................................................... 104

A-2 200 Area measured dose fractions....................................................................................... 105

A-3 300 Area measured dose fractions....................................................................................... 105

A-4 400 Area measured dose fractions....................................................................................... 105

B-1 Missed external doses based on the main body of this TBD and ORAUTOTIB-0017 ........................................................................................................................... 109

B-2 Annual Hanford external coworker doses modified to account for missed 

dose..................................................................................................................................... 111

B-3 Annual Hanford external penetrating coworker doses modified in 

accordance with ORAUT-OTIB-0052 ................................................................................... 112
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C-1 Examples of skin dose assignments for Hanford badge readings in 1980 ............................ 117

C-2 Examples of skin dose assignments for Hanford badge readings in 1970 ............................ 117

D-1 Chronology of radiation standards: occupational external whole body 

dose equivalent limits........................................................................................................... 121

D-2 Abbreviated timeline of significant Hanford radiation exposure associated 

events .................................................................................................................................. 123

E-1 Sample of Hanford N-Reactor data collection....................................................................... 212

E-2 List of N Reactor worker measured neutron and photon dose, ≥30 mrem, 

respectively.......................................................................................................................... 216

E-3 Lognormal statistical parameters to measured TLD neutron dose........................................ 216

E-4 Unique REX-ID worker annual dose records with positive neutron dose .............................. 217

E-5 Unique REX-ID worker measured and assigned annual neutron doses for 

1964–86............................................................................................................................... 217

E-6 Hanford reactor category REIRS/REMS reporting................................................................ 218

E-7 UNC annual report identified dose components ................................................................... 218

E-8 Neutron dose distribution for UNC annual reports ................................................................ 218

F-1 NP ratio determined from 1971 workplace study of neutron dose 

measurements ..................................................................................................................... 235

F-2 Summary of 1981 Hanford workplace neutron dose measurements .................................... 236

F-3 Summary of 1982 Hanford workplace neutron dose measurements .................................... 236

F-4 200 Area workplace measurement comparisons with HMPD ............................................... 237

F-5 SRDB references containing neutron and photon dose survey 

measurements ..................................................................................................................... 238

F-6 Hanford 200 Area plutonium facility NP ratio survey records................................................ 239

F-7 1972 AEC NP ratios used to reconstruct maximum worker dose.......................................... 241

F-8 Statistical parameters for lognormal distribution for the respective 

selections of NP ratio measurement data............................................................................. 243

F-9 Illustration of assigned dose to long-term PFP worker.......................................................... 248

G-1 AEC 1972 Committee N:P ratio recommendations............................................................... 253

G-2 300 Area and Hanford NTA processing results .................................................................... 262

G-3 N:P Ratio determined from 1971 Workplace Study of Neutron Dose 

Measurements ..................................................................................................................... 263

G-4 Summary of 1981 Hanford workplace neutron dose measurements .................................... 264

G-5 Summary of 1982 Hanford workplace neutron dose measurements .................................... 264
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LIST OF FIGURES

FIGURE TITLE PAGE

6-1 Box plot of historical measured Hanford worker whole-body annual doses showing 

median, whiskers at 25th and 75th percentiles, respectively, and bullets at 95 

percentile compared to official and Hanford administrative dose limits................................... 18

6-2 Trend in the number of Hanford monitored workers, the number of workers with 

recorded photon or neutron doses >0, and the total collective dose, 1944–1989 ................... 21

6-3 Annual dose components for a single Hanford worker, 1948–1976........................................ 23

6-4 Measured Hanford dosimeter photon response characteristics .............................................. 29

6-5 Annual Hanford external coworker 95th percentile penetrating doses 

modified to account for missed dose in comparison with 95th-percentile 

measured dose ......................................................................................................................43

6-6 Annual Hanford 95th-percentile penetrating CTW assigned doses in 

comparison with 95th-percentile coworker assigned and measured doses ............................ 44

6-7 Single-pass reactor paired neutron and photon survey measurements .................................. 46

6-8 Probability distribution of the NP ratio .................................................................................... 46

6-9 Trend of 100-N worker recorded shallow, neutron, and extremity annual dose to 

recorded deep dose for 4,777 records with deep annual dose >0 .......................................... 49

6-10 Hanford 200 Area plutonium facility NP ratio measurements.................................................. 52

6-11 Probability distribution of the 200 Area plutonium facility NP ratio for instruments and 

dosimeters .............................................................................................................................53

6-12 Comparison of Hanford film and TLD nonpenetrating dose results......................................... 63

A-1 Neutron spectra for Hanford 400 Area FFTF........................................................................ 101

A-2 Degradation in neutron energy spectra for bare, 2.54 cm and 5.08 cm of 

acrylic plastic shielding with neutron energy groups overlay................................................. 103

A-3 Neutron energy spectra recorded at Hanford PFP 234-5Z ................................................... 103

A-4 Neutron spectra for Hanford 308 and 324 facilities............................................................... 104

D-1 HEW Special Work Permit Form .......................................................................................... 120

E-1 Hanford N-Reactor plutonium production ............................................................................. 206

E-2 Comparison of parallel field testing of thermoluminescent, film, and pencil 

dosimeters ........................................................................................................................... 211

E-3 Trend of recorded shallow, neutron, and extremity annual dose to 

recorded deep dose for 4,777 records with deep annual dose >0 ........................................ 214

E-4 Graph of N-Reactor worker annual measured photon and neutron, and 

the calculated NP ratio ......................................................................................................... 215

E-5 Trend of recorded photon versus neutron dose for all >0 recorded neutron 

doses ................................................................................................................................... 215

F-1 Timeline of Hanford plutonium plant facilities and operational changes................................ 224

F-2 Hanford plutonium production .............................................................................................. 230

F-3 Variation in measured neutron and photon dose rates with distance, and 

the associated calculated NP ratio ....................................................................................... 238

F-4 1,419 measured NP ratios in Hanford 234-5Z plutonium facility ........................................... 240

F-5 Scatter plot of 1,346 measured neutron and photon doses .................................................. 242

F-6 Lognormal probability plot of 1,419 measured NP values..................................................... 242

F-7 Radiation control report instrument measured monthly neutron dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-8 Radiation control report instrument measured monthly photon dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-9 NP ratios calculated from the data contained in Figures F-5 and F-6 ................................... 245
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F-10 Correlation of TLD measured neutron and photon doses ..................................................... 246

F-11 Lognormal probability plot for TLD measured neutron-photon ratios .................................... 246

F-12 Fluorination 7C/9B and 7A/9A hoods instrument and worker TLD NP ratio 

measurements ..................................................................................................................... 247
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ACRONYMS AND ABBREVIATIONS

AP anterior-posterior (X-ray)

AEC U.S. Atomic Energy Commission

CEDR Comprehensive Epidemiologic Data Resource

cm centimeter

CP Cutie Pie (measurements)

CTW Construction Trade Worker

d day

DCF dose-rate conversion factors

DOE U.S. Department of Energy

DOELAP DOE Laboratory Accreditation Program

DUN Douglas United Nuclear, Inc.

EEOICPA Energy Employees Occupational Illness Compensation Program Act

EURATOM European Atomic Energy Community

eV electron-volt

FFTF Fast Flux Test Facility

FR Federal Register

ft foot

gal gallon

GE General Electric Corporation

GM geometric mean

GSD geometric standard deviation

H&S Health and Safety

HAPO Hanford Atomic Products Operations

HEW Hanford Engineer Works

HMPD Hanford Multipurpose TLD

Hp(d) Personal Dose Equivalent at depth d in tissue

HQ Headquarters

hr hour

IARC International Agency for Research on Cancer

ICRP International Committee for Radiological Protection

in. inch

IREP Interactive RadioEpidemiological Program

keV kiloelectron-volt

LOD Limit of Detection

m meter

MED Manhattan Engineer District

MeV megaelectron-volt

MDL minimum detection level

Mg milligram

Min minute

mm millimeter
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mR milliroentgen

mrem millirem

mSv millisievert

MW megawatt

MWD megawatt-day

NCRP National Council on Radiation Protection and Measurements

NIOSH National Institute for Occupational Safety and Health

NIST National Institute of Standards and Technology 

NOCTS NIOSH-OCAS Claims Tracking System

NP neutron-to-photon

NRC U.S. Nuclear Regulatory Commission

NTA Eastman-Kodak Nuclear Track, Type A emulsion

OCAS Office of Compensation Analysis and Support

ORAU Oak Ridge Associated Universities

ORNL Oak Ridge National Laboratory

OW (Hanford) designation of open window (i.e., no filter) nonpenetrating dose

PFP Plutonium Finishing Plant

PFPP Plutonium Fuels Pilot Plant 

PIC pocket ionization chamber (i.e., “pencil” dosimeter)

PNNL Pacific Northwest National Laboratory

POC probability of causation

PRTR Plutonium Recycle Test Reactor Facility

PUREX Plutonium-Uranium Extraction Plant

R Roentgen

RBE Relative Biological Effectiveness

RCT Radiation Control Technologist

RECUPLEX Recovery of Uranium and Plutonium by Extraction

REDOX Reduction Oxidation Plant

REIRS Radiation Exposure Information Record System

rem radiation equivalent man

RG Rubber Glove

RL DOE Richland Operations Office

RM Remote Mechanical

RMA Remote Mechanical A (line) series of gloveboxes

RMC remotely operated series of gloveboxes

S (Hanford) designation of penetrating dose behind 1 mm thick silver filter

SEC Special Exposure Cohort

SRS Savannah River Site

TBD technical basis document

TED track-etch dosimetry 

TEPC Tissue Equivalent Proportional Counter

TIB technical information bulletin

TLD thermoluminescent dosimeter

UNI United Nuclear Industries

U.S.C. United States Code
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W watt

WB whole-body

yr year

§ section or sections
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6.1 INTRODUCTION

Technical basis documents (TBDs) and site profile documents are not official determinations made by 

the National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historic background information and guidance to assist in the preparation of 

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents can be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds on 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

The statute also includes a definition of a DOE facility that excludes “buildings, structures, premises, 

grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 U.S.C. 

7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. While this 

definition excludes Naval Nuclear Propulsion Facilities from being covered under the Act, the section 

of EEOICPA that deals with the compensation decision for covered employees with cancer [i.e., 42 

U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally-derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external occupational radiation exposures are considered valid for inclusion in a dose reconstruction. 

No efforts are made to determine the eligibility of any fraction of total measured exposure for inclusion 

in dose reconstruction. NIOSH, however, does not consider the following exposures to be 

occupationally derived (NIOSH 2007a):

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation, 42 C.F.R. Pt. 82) define “performance of duty” for 

DOE employees with a covered cancer or restrict the “duty” to nuclear weapons work (NIOSH 2007a).

• Background radiation, including radiation from naturally occurring radon present in 

conventional structures

 1 The U.S. Department of Labor (DOL) is ultimately responsible under the EEOICPA for determining the POC.
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• Radiation from X-rays received in the diagnosis of injuries or illnesses or for therapeutic 

reasons

6.1.1 Purpose

Hanford was established in 1942 as a major government-owned nuclear weapons production site 

fabricating reactor fuel, eventually operating nine nuclear material production reactors and building 

five major chemical separation plants, and producing plutonium for nuclear weapons. Later 

operations included nonmilitary applications of nuclear energy. The purpose of this TBD is to 

describe the external dosimetry systems and practices at Hanford. This document discusses 

historical and current practices in relation to the evaluation of external radiation exposure of monitored 

and unmonitored workers.

6.1.2 Special Exposure Cohort Petition Information for Hanford

Special Exposure Cohort (SEC) petitions for Hanford are: 

Class Added to the SEC

• Employees of DOE, its predecessor agencies, or DOE contractors or subcontractors who were 

monitored or should have been monitored for internal radiological exposures while working at 

the Hanford Engineer Works in the 300 Area fuel fabrication and research facilities from 

October 1, 1943 through August 31, 1946; the 200 Area plutonium separation facilities from 

November 1, 1944 through August 31, 1946; or the 100 B, D, and F reactor areas from 

September 1, 1944 through August 31, 1946; for a number of workdays aggregating at least 

250 workdays or in combination with workdays within the parameters established for one or 

more other classes of employees in the SEC (72 FR 55214). 

• Employees of DOE, its predecessor agencies, and DOE contractors or subcontractors who 

worked from September 1, 1946 through December 31, 1961 in the 300 area, or January 1, 

1949 through December 31, 1968 in the 200 areas (East and West) at the Hanford Nuclear 

Reservation in Richland, Washington, for a number of workdays aggregating at least 250 

workdays occurring either solely under this employment or in combination with workdays 

within the parameters established for one or more other classes of employees in the SEC (73 

FR 37459).

Class Recommended by NIOSH for addition to the SEC

• All workers of DOE, its predecessor agencies, and their contractors and subcontractors who 

worked at the Hanford Site in Richland, Washington, from October 1, 1943 to June 30, 1972, 

for a number of workdays aggregating at least 250 workdays, occurring either solely under this 

employment or in combination with workdays within the parameters established for one or 

more other classes of employees included in the SEC (NIOSH 2009). 

Dose reconstruction guidance in this document for periods prior to July 1, 1972 is presented to 

provide a technical basis for partial dose reconstructions for non presumptive cancers not covered 

within the SEC class through June 30, 1972. 

6.1.3 Scope

An objective of this document is to provide a technical basis to evaluate external radiation exposure to 

workers that can reasonably be associated with Hanford operations under EEOICPA legislation. 

Consistent with NIOSH guidelines, this document identifies options to adjust historical recorded 

occupational external dose to account for current scientific methods and protection factors. The 

methods and concepts of measuring occupational external doses to workers have evolved since the 
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beginning of Hanford operations. In particular, this document presents the methods to prepare worker 

dose information for input to the NIOSH Interactive RadioEpidemiological Program (IREP).

Attributions and annotations, indicated by bracketed callouts and used to identify the source, 

justification, or clarification of the associated information, are presented in Section 6.11. Attachments 

A to G are provided for special topics with substantial supporting data such as determination of 

coworker dose, shallow dose assignment and neutron dose bounding analyses.

6.2 MED/AEC/DOE EXTERNAL RADIATION DOSIMETRY 

External radiation dosimetry refers to the measurement of radiation external to (i.e., outside) the body 

such as occurs with medical X-rays, cosmic rays, or radiation from natural occurring radioactivity in 

the earth. Primary types of radiation typically significant to exposure to workers are beta, photon (i.e., 

X-ray and gamma) and neutron radiation, respectively, each with characteristic properties of origin 

and interaction with matter. Facilities containing X-ray equipment, particle accelerators, nuclear 

reactors, natural or manmade radionuclides, etc., have potential for external radiation exposure of 

workers. External Radiation Dosimetry can be contrasted with Internal Radiation Dosimetry, which is 

concerned with quantification of radiation exposure from radionuclides internal (i.e., inside) to the 

body.

6.2.1 History of Radiation Safety Guidance

During the early 1950s, the NCRP introduced the concept of permissible dose to replace the tolerance 

dose concept. The NCRP recommended that the maximum permissible dose to the gonads and 

blood-forming organs be 0.3 rem (3 mSv) per week in 1954 which corresponds to an annual WB dose 

limit of 15 rem (150 mSv). In the later 1950s, the potential significance of cumulative radiation 

exposure to genetic and cancer risks became a concern leading to implementation of the WB dose 

limit of 5 × (N-18) rem, where N is measured in years. In the later 1980s, changes in the WB dose 

limit were associated with an NCRP recommendation to limit WB dose to a maximum of 10 rem 

averaged over 5 years (i.e., average of 2 rem/yr). The historical trend in WB, dose limits, and in 

comparison with the median and 95th percentile Hanford recorded WB annual doses is presented in 

Figure 6-1. Hanford administratively controlled the photon dose to 3 R per year beginning in 1954 

extending to about 1972. The recommended annual dose limits by applicable scientific and regulatory 

agencies are shown in Figure 6-1. Appendix D provides a more detailed history of Hanford radiation 

dose control limits.

6.3 HANFORD OPERATIONS 

Hanford operations involved several processes of the nuclear weapons development cycle (DOE 

1996, 1997, Marceau et al. 2002) and played a significant role in the U.S. nuclear weapons program. 

In the 1940s these processes included construction and operation of new industrial scale facilities for 

nuclear fuel fabrication; nuclear reactor operations; radiochemical separations; refining, finishing and 

storing plutonium; and handling the associated radioactive waste. Peak production of plutonium was 

achieved during the latter 1950s to the mid-1960s. Hanford personnel were involved in research and 

development of reactor systems, nuclear fuel, nuclear weapons and peaceful applications of nuclear 

technology such as nuclear power plants and radioisotopes for medical diagnosis and therapy. 

Hanford operations conducted extensive studies of facility design and processes to evaluate potential 

hazards to personnel as noted in the historical events timeline in Attachment D. As described in 

Wilson (1987) Central Site-wide and respective 100, 200 and 300 Operational Area safety committees 

were established and a series of Special Hazard Bulletins were issued by these committees to alert 

staff to potential hazards and required procedures.
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Figure 6-1. Box plot of historical measured Hanford worker whole-body annual doses 

showing median, whiskers at 25th and 75th percentiles, respectively, and bullets at 95th 

percentile compared to official and Hanford administrative dose limits. 

Records of radiation doses to individual workers from personnel dosimeters worn by the worker and 

coworkers are available for Hanford operations beginning in 1944 (Buschbom and Gilbert 1993) and 

reviews of the Hanford personnel dose data for 10- and 15-year periods from Hanford startup in 

Parker (1954) and Keene (1960), respectively. Doses from these dosimeters were recorded at the 

time of measurement and routinely reviewed by Hanford operations and radiation safety staff for 

compliance with radiation control limits. Hanford used an administrative annual external gamma 

whole body dose limit of 3R per year from about 1950 to about 1972, as shown in Figure 6-1, because 

of known uncertainties in the measured neutron dose and anticipated future changes in radiation dose 

limits. The NIOSH External Dosimetry Implementation Guide (NIOSH 2007b) has identified these 

records to represent the highest quality records for retrospective dose assessments. The information 

in this section pertains to analyzing these records and has been updated to address parameters 

regarding skin, testicular, or breast radiation dose that could result from acute beta (electron) radiation 

exposure under short-term accidental or incident nonroutine workplace exposure profiles. 

Nonpenetrating radiation during routine operations is also addressed in this section [1].

Radiation dosimetry practices were initially based on experience gained during several decades of 

radium and X-ray medical diagnostic and therapy applications. These methods were generally well 

advanced at the start of the Manhattan Engineer District (MED) program to develop nuclear weapons 

beginning in about 1940. The primary new challenges encountered by MED, and later AEC, 

operations to measure worker dose to external radiation involved [2] (1) comparatively large quantities 

of high-level radioactivity, (2) mixed radiation fields involving beta, photon (gamma and X-ray), and (3) 

neutron radiation with low, intermediate, and high energies.
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6.3.1 Radiation Safety Practices

Information regarding routine Hanford radiation safety practices historically is presented in a technical 

report prepared by Wilson (1987), and for the earliest years in a report by Parker (1946). Table 6-1 

lists several of the Radiation Protection Procedures manuals issued prior to splitting the Hanford Site 

operation among several contractors, each typically with its own guidance manuals, in 1965. The last 

document in Table 6-1 provides a comparatively detailed summary of Hanford radiation protection 

limits and practices for almost all years. Attachment D contains a much more detailed summary of 

Hanford radiation protection WB, skin, and extremity dose limits historically and, in Table D-2, a 

historical timeline of numerous radiation associated reports and events that tend to illustrate the 

magnitude of Hanford Radiation Safety practices.

Table 6-1. Hanford pre-1965a radiation protection procedures manuals.

Document no. Description SRDB ID

HEW-7-703, 

Parts I and II

Hanford Engineer Works Operating Standards Manual-100, 200, and 

300 Areas that outline operational limits and criteria. 

DuPont 1943–

1946

HW-7-4282 Medical Department, Health Instrument Section, Manual of Standard 

Procedures–Personnel Meters issued May 1, 1946, pertaining to 

administration of the Hanford pencil meter and beta/photon film 

dosimeter programs. 

HEW 1946

HW-46104 Manual of Standard Procedures for 100, 200 and 300 Area Survey Work, 

dated December 1, 1949. This is a comparatively large manual 

containing radiation exposure limits, contamination limits, Special Work 

Permits, protective clothing, Special Hazards Bulletins, descriptions of 

the monitoring equipment and general monitoring information regarding 

radiation types, selections of instruments, etc.

GE 1949

Manual of 

Standard 

Procedures

Health Instrument Operational Division, Manual of Standard Procedures, 

Personnel Meters, issued August 18, 1950. This manual describes 

procedures used with the radiation instruments and dosimeters.

GE 1950

HW-25457 Radiological Sciences Department Manual of Radiation Protection 

Standards, issued December 15, 1954. 

GE 1954

HW-45674 Hanford Irradiation Processing Department issued Radiation Control 

Standards and Procedures manual dated December 14, 1956. 

GE 1956

HW-25457, Rev 

2

Manual of Radiation Protection Standards, Hanford Atomic Products 

Operation, General Electric Company, issued March 1, 1960. 

GE 1960

Procedures

Manual

Hanford External Dosimetry Operations, Operating Procedures, issued 

March 25, 1963. 

GE 1963

HW-78500 N-Reactor Radiation Protection and Procedures, issued January 1, 

1964. This document describes Hanford Operations and N Reactor 

division operational radiation controls. 

Vanderbeek 

1964

File: 1967-10 DOE-RL Health and Safety Division prepared historical summary of 

Hanford Radiation Protection Standards and Practices.

Hicks and 

Yesberger 1967

a. Beginning in 1965, routine Hanford operations were divided among several contractor organizations each typically with 

a company-specific procedures manual as described in the last entry in this table.

6.3.1.1 Radiological Record Practices

Hanford workers entering operating areas were monitored for exposure to ionizing radiation using 

assigned pocket ionization chambers (PICs) (January 1944) and personnel dosimeters (March 1944), 

and records maintained of the measured doses (Wilson 1987). Hanford practice to assign the whole 

body (WB), skin, and extremity doses maintained in the radiological records from the dosimeter 

measured unshielded [i.e., open window (OW)] and shielded (i.e., noted by S for 1 mm thick silver 

shield in the Hanford two-element film dosimeter) is summarized in Table 6-2. Trends in the number 

of monitored workers and the collective dose for these workers are shown in Figure 6-2. This figure 

illustrates the number of monitored workers and the number with positive recorded WB dose from 
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photon and neutron radiation, respectively. The trend in measured WB (i.e., photon, neutron, and 

tritium) dose in this figure does not reveal abrupt changes that might be indicative of significant 

changes in personnel dosimetry practices or the assignment of dosimeters (Buschbom and Gilbert 

1993). However, Figure 6-2 does illustrate an abrupt change in the number of workers with a 

recorded neutron dose greater than zero. The situation concerning technical limitations to measure 

neutron radiation dose is discussed later in this TBD. Basically, workers entering a radiological 

controlled 100, 200, or 300 Area were monitored, the results recorded and the majority of workers had 

some positive measured dose. Wilson (1987) provides a description of the historical Hanford 

radiation safety organization, practices, and technology.

Table 6-2. Historical Hanford recorded dose practices [71].

Year Dosimeter measured quantities Compliance dose quantities

Two-element beta/photon film dosimetera

1944–47 OW = open window, mrep Skin = OW + S

S = “shielded filter” dosimeter response, mR WB = S

1948–50 Beta = open window, mrep Skin = beta + WB

Gamma = “shielded filter” dosimeter 

response, mR

WB = gamma 

Two-element beta/photon film dosimeter + NTA neutron dosimeter

1950–57 Beta = open window, mrep Skin = beta + WB

Gamma = “shielded filter” dosimeter 

response, mR

WB = gamma + neutron 

Multielement beta/photon dosimeter + NTA neutron dosimeter

1957–58 Beta Skin = beta + gamma + 65% X-ray + neutron

Gamma

X-ray WB = gamma + 0.35% X-ray + neutron

Neutron

1959–71 Beta (-B-) Derma (skin) = beta + WB + 65% X-ray

Gamma (-G-)

X-ray (-X-) WB (penetrating) = gamma + neutron + 35% Xray)

Fast neutron (F-N)

Slow neutron (S-N)

Thermoluminescent dosimeter

1972–94 Nonpenetrating (NPEN) Skin = NPEN + WB

Penetrating (PEN)

Slow neutron (SN) WB = PEN + SN + FN

Fast neutron (FN)

1995–2003 Shallow (Sh) Skin = Sh + Dp + Nt

Deep (Dp) WB = Dp + Nt

Neutron (Nt)

From 1948-56, when dosimeter quantities for each period were noted as beta or gamma, the cumulative dosimeter dose 

quantities continued to be labeled as OW and S.

6.3.2 Incidents

External radiation dose from worker involvement in incidents is included in the dose of record for 

Hanford workers. There have been significant incidents during the history of Hanford. A few primary 

incidents are described below:

P-11: The purpose of the 120 Building so called P-11 facility was to test critical safe geometries to 

assist with design of the fuel reprocessing systems and systems at the 234-5 Plutonium Finishing 

Plant. The P-11 processes were purposely operated near the edge of criticality to determine 
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1.E+01

1.E+02

1.E+03

1.E+04

1.E+05

1940 1945 1950 1955 1960 1965 1970 1975 1980 1985 1990

Year

No. of Monitored Workers

No. of workers, Recorded Annual Dose > 0

No. of workers, Recorded Neutron Dose > 0

Figure 6-2. Trend in the number of Hanford monitored workers, the 

number of workers with recorded photon or neutron doses >0, and the total 

collective dose, 1944–1989 [3].

operational bounds. These bounds were exceeded resulting in a fire during 1950 in the atmospheric 

exhaust filter systems (Leonard 1952).

RECUPLEX: A criticality accident occurred on April 7, 1962, in a plutonium waste chemical recovery 

facility called RECUPLEX associated with the 234-5 building. Twenty-four workers were involved, 

including two patrolmen stationed at the entry gatehouse. Photon doses to workers were measured 

with personnel dosimeters. Neutron doses were determined from WB counts and blood activation 

measurements along with measurements of 32P in hair and radioactivity in objects that were on the 

workers as well as threshold detectors and recording instruments in the building. The highest 

exposed worker received 23-30 rad from fast neutrons and 63 R to the central part of the body. This 

person also received about 42-54 rad from the fast neutron radiation to his eyes (Gamertsfelder et al. 

1962).

PRTR: A fuel element and pressure tube failure occurred while testing, one of the purposes for the 

PRTR, a defective nuclear fuel element on January 29, 1965 resulting in extensive contamination of 

the 309 Building which housed this test reactor (McConnon 1968). The reactor was restarted in 1968 

after a significant effort to decontaminate the facility and to redesign some of its capabilities. 

241Am Explosion: In 1976, a chemical explosion occurred at Hanford resulting in a nuclear chemical 

operator being extensively contaminated and receiving an intake of 241Am by skin absorption and 

inhalation (see Section 5 of the Hanford Site Profile, ORAUT 2007a). 

N Reactor: On December 16, 1977, an irradiated fuel discharge occurred exposing four workmen on 

an elevator resulting in personnel radiation exposures in excess of radiation safety limits. The 

incident was identified as a Class B occurrence (according to DOE radiation protection guidance. An 

investigation committee was formed to oversee the process of determination of cause for the accident 

and the process of dose reconstruction (UNI 1978). 

The foregoing are major incidents but the term “incidents” had a much broader meaning historically at 

Hanford as illustrated in Radiological Sciences Department Annual Report, 1954 (Mickelson and Staff 

1955) which contains the following summary statistics. Apparently any unusual event or deviation 
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from procedure could result in an investigation per the various incidents described in Attachment D, 

Table D-2.

Year

Reported radiation incidents 

Informal Class I Class II Total

1944 5 0 3 8

1945 88 35 6 129

1946 85 39 4 128

1947 99 27 2 128

1948 126 38 2 166

1949 121 36 0 157

1950 124 20 5 149

1951 77 25 13 115

1952 130 71 12 213

1953 239 69 26 334

1954 287 76 20 383

6.4 DOSE RECONSTRUCTION PARAMETERS

Examinations of the beta, photon (X-ray, gamma ray), and neutron radiation type, energy, and 

geometry of exposure in the workplace and the characteristics of the Hanford dosimeter response are 

crucial to the assessment of error of the original recorded dose in relation to the shallow Hp(0.07) and 

deep Hp(10) dose equivalent. The bias and uncertainty for current Hanford dosimetry systems are 

well documented (Rathbone 2002), which is required by the DOE Laboratory Accreditation Program 

(DOELAP) implemented in 1985 (DOE 1986). The performance of historical dosimetry systems can 

often be evaluated using current DOELAP and previous (Unruh et al. 1967) testing protocols. 

Dosimeter response characteristics for radiation types and energies in the workplace are crucial to the 

overall analysis of error in recorded dose [4].

Overall, accuracy and precision of the original recorded individual worker doses and their 

comparability to be considered in using NIOSH (2007b) guidelines depend on (Fix et al. 1997a):

• Administrative practices adopted by facilities to calculate and record personnel dose based 

on technical, administrative, and statutory compliance considerations.

• Dosimetry technology, which includes the physical capabilities of the dosimetry system, such 

as the response to different types and energies of radiation, in particular in mixed radiation 

fields.

• Calibration and Dosimeter Response Characteristics of the monitoring systems and 

similarity of the methods of calibration to sources of exposure in the workplace.

• Workplace radiation fields that might include mixed types of radiation, variations in exposure 

geometries, and environmental conditions.

An evaluation of the original recorded doses based on these parameters is expected to provide the 

best estimate of Hp(10) and, as necessary, Hp(0.07) for individual workers with the least relative 

overall uncertainty.

6.4.1 Hanford Historical Administrative Practices

Historically, Hanford had an extensive radiation safety monitoring program to measure exposure in 

the workplace using portable radiation instruments (Howell et al. 1989), contamination surveys, zone 

controls, and personnel dosimeters (Parker 1954; Wilson 1987). This was done directly or under the 
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guidance of a specially trained group of radiation specialists (i.e., radiation protection technologists). 

The results from the personnel dosimeters were used to measure and record dose from external 

radiation exposure to Hanford workers throughout the history of Hanford operations (Wilson 1987). 

These dosimeters, as noted in the Health Instrument section of routine reports (Miller 1946; Parker 

1948a; also see Table D-2), include one or more of the following:

• Personnel WB beta/photon dosimeters 

• PIC dosimeters 

• Personnel extremity dosimeters

• Personnel WB neutron dosimeters

Figure 6-3 is an illustration of the dose of record for a single long-term Hanford worker using these 

dosimeters. Hanford began operations in 1944 using in-house dosimeter and processing technical 

support. Hanford based its beta/photon film dosimetry methods on the dosimeter design developed at 

the Metallurgical Laboratory by Pardue, Goldstein, and Wollan (1944). This design was implemented 

at several of the MED sites. Hanford implemented its individual worker neutron dosimetry methods 

beginning in 1944 using PICs with a 10B-enriched lining and portable instruments. In 1950, the 

Eastman-Kodak Nuclear Track, Type A (NTA) emulsion dosimeter capability was implemented [5].

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

5500

6000

6500

7000

7500

8000

1945 1950 1955 1960 1965 1970 1975 1980

Year

Dose, mrem

 NonPenetrating Dose

Penetrating Dose

 Neutron Dose

Extremity Dose

X-ray Dose

Two-Element Film Multi-Element Film TLD

Figure 6-3. Annual dose components for a single Hanford worker, 1948–1976 [7].

Parameters concerning Hanford administrative practices significant to dose reconstruction include [6]:

• Policies to assign dosimeters to workers (Parker 1955).

• Policies to exchange dosimeters.

• Policies to record the measured dose and not using a notional dose (i.e., some identified value 

for lower dosed workers often based on a small fraction of the regulatory limit). 

• Policies to estimate dose for missing or damaged dosimeters.
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• Policies to replace destroyed or missing records.

• Policies to evaluate and record dose for incidents.

• Policies to obtain and record occupational dose to workers for other employer exposure.

Hanford policies appear to have been in place for all of these parameters (Parker 1948a; see 

Table D-2). Routine Hanford practices appear to have required assigning dosimeters to all workers 

who entered a controlled radiation area (Hart 1967). Dosimeters were exchanged on a routine 

schedule. All dosimeters were processed and the measured results were recorded and used to 

estimate dose. There appears to be no use of recorded notional doses, although there are issues of 

“missed” recorded dose for low-dosed dosimeters (see section on “missed dose”) as well as recorded 

doses for individual dosimeters at levels less than the statistical Lower Limit of Detection (LOD).

Administrative practices are generally described in Wilson (1987) and contained in the procedures 

documents listed in Table 6-1. Important Hanford practices include preparation of Special Work 

Permits (SWPs) (See Table D-2), which were prepared by the tens of thousands in the early years of 

Hanford operations, to address worker protective measures in the conduct of the task considering 

radiation types, energies, geometry, contamination, etc., and the use of Special Hazards Bulletins 

prepared for several general topics such as contaminated instruments, handling injured workers in 

contaminated areas, radiation zone ingress and egress, etc., used in Site-wide employee training. 

This was an activity administered through area and central safety committees. A description of the 

content of the historical recorded dose values for each year by Fix, Carbaugh, and MacLellan (2001) 

and detailed information for each worker is in the NIOSH claim documentation. The claim 

documentation provides specific information to be evaluated regarding the recorded dose of record. 

There does not appear to be any significant administrative practice that would jeopardize the integrity 

of the recorded dose of record. Gilbert (1990) found agreement between the original paper records 

and computerized dose records. In addition, thousands of Hanford processed dosimeter films were 

examined in the 1960s at the University of Pittsburgh as part of the AEC Worker Health and Mortality 

Study (Mancuso, Sanders, and Brodsky 1966). The evaluation by University of Pittsburgh 

researchers was that the Hanford recorded dose showed that “good quality control was exercised 

over the film badge calibration and processing procedures at Hanford over the years (i.e., 1944-61).”

6.4.2 Hanford Personnel Dosimetry Technology

Early Hanford external dosimetry methods were essentially the same as practices adopted at the 

MED Metallurgical Laboratory (of the University of Chicago) and Clinton Engineering Works (now Oak 

Ridge National Laboratory [ORNL]) laboratories. Parker (1945) described results of intercomparisons 

of dosimeter processing and exposure calculations between these three laboratories prior to declaring 

the Hanford system capable of routine dosimeter processing. Comparisons of dose interpretation 

among these MED/AEC sites and other sites were done through the years (Wilson 1960a; Wilson et 

al. 1990). These sites followed a similar evolution in dosimetry technology using PICs in addition to a 

two-element film dosimeter in the 1940s and early 1950s, multielement film dosimeters in the later 

1950s, followed by multielement thermoluminescent dosimeters (TLDs) in the 1960s and 1970s. The 

adequacy of the dosimetry methods to measure radiation dose accurately is determined from the 

radiation type, energy, exposure geometry, etc., as described in later sections. The dosimeter 

exchange frequency was gradually lengthened, generally corresponding to the period of the 

regulatory dose controls (GE 1954). Major operational events at Hanford associated with radiation 

have been described in several historical documents (Wilson 1987; Wilson et al. 1990; Fix et al. 1997; 

see Attachment D.) A brief summary of the dosimetry systems and period of use is presented in 

Table 6-3.
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Table 6-3. Hanford historical dosimetry systems. (See Attachment D, Table D-2 for more detail.)

Date Description Exchange

Beta/photon radiation personnel dosimeters

1/1/1944 PICs assigned to measure dose for each worker prior to film dosimeter availability. 

Thereafter, PICs used in addition to film dosimeters.(HEW 1946; Wilson 1987).

Dailya

10/1944 Two-element (i.e., OW and 1-mm silver filter) film dosimeter issued to personnel (HEW 

1946). 

Weekly

1/1948 Two-element film dosimeter exchange changed. Biweekly

1/1950 Extremity film dosimeter implemented.

4/1957 Multielement film dosimeter implemented. Biweekly

5/1957 Multielement film dosimeter exchange period changed. Monthly

1962 Multielement film dosimeter with nuclear accident capabilities implemented. Monthly

1963 Implemented dosimeter exchange for nonradiological workers. Quarterly

1/1971 Basic (one-chip) TLD implemented. Annualb

Neutron radiation personnel dosimeters

1940s Enriched B-10 lined pocket ionization chambers assigned. Dailya

1950 NTA film was issued to personnel to measure neutron dose. Weekly

7/1957 Neutron dosimeter (NTA + beta/photon film) implemented Weekly

7/1958 Exchange period changed. Biweekly

Beta/photon/neutron personnel dosimetersc

1/1972 Five-chip Hanford Multipurpose TLD (HMPD) implemented. Monthly

7/1978 Four-chip HMPD implemented. Monthly

1/1984 Five-chip HMPD reinstated. Monthly

1/1/1995 Commercial Harshaw TLD system implemented. Routine dosimeter exchange is 

quarterly and monthly [8].

Monthly

a. Exchange as often as necessary but not to typically exceed 1 day.

b. Basic TLD exchange for nonradiological workers varied but many were exchanged annually.

c. Exchange period varied depending on exposure potential but monthly was routine for radiological workers. 

6.4.2.1 Beta/Photon Radiation Personnel Dosimeters

The following paragraphs describe the Hanford beta/photon dosimeters and period of routine use to 

provide the recorded dose of record.

Pocket Ionization Chamber, 1944. During January 1944, before the Hanford film dosimetry system

was operational, PICs were used for a few months to provide the dose of record (Wilson 1987). PICs 

were issued to employees in duplicate (i.e., two to each worker) and exposures were recorded daily. 

PICs consist of an electrically charged chamber that indicates radiation exposure as the charge 

decreases. The decrease in charge occurs from radiation exposure (i.e., ionization) but can also 

occur from any cause that reduces charge such as humidity, physical impact, etc. Therefore, PICs 

typically overestimate the exposure from routine handling and environmental effects (Watson 1957). 

Because of “false-positive” dose from routine handling and environmental effects, the lower of the two 

readings for each day was used to calculate the dose for comparison with the daily dose limits at that 

time. Following use as the earliest dosimeters, PICs have been used throughout the history of 

Hanford operations to provide administrative control of worker dose until the dosimeter being worn 

was processed and the dose calculated. It has been routine practice since at least the early 1950s to 

compare the doses measured with PICs and dosimeters and, for significant differences, to document 

the reason(s) for the discrepancy [9].

Two-Element Film Dosimeter, October 1944 to March 1957. Hanford implemented a two-element 

beta/photon dosimeter in 1944 based on the design developed by Pardue, Goldstein, and Wollan 

(1944) at the Metallurgical Laboratories. This basic dosimeter design was used at the Clinton 

Laboratory (now ORNL) and later by many other MED/AEC/DOE laboratories. The Hanford design 

consisted of an open window and a 1-mm silver shield. Records of dosimeter film processing identify 

the regions of the dosimeter film as “OW” for open window and “S” for shielded. A calibration factor 
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for each batch of film was used to convert measured optical density to dose. The optical density and 

the interpreted dose are included in the original Hanford dosimetry forms. In 1952, the practice was 

begun to include 20% of the OW dose to the S dose to calculate the penetrating dose in plutonium 

facilities (Fix, Wilson, and Baumgartner 1997b). However, this practice has not been verified with the 

actual dosimeter processing results and recorded doses. 

Another feature of the Hanford beta/photon film dosimeter was the use of DuPont 502-type film with a 

sensitive (lower radiation dose response) and an insensitive (typically accident-level dose response) 

film packet. Normally, only the sensitive film was useful for personnel dose assessment. However, 

Hanford individual worker personnel dose forms included space to record the insensitive film 

response. Prior to 1957, the processing data were recorded manually. Worker personnel dose forms 

were updated each year to enable staff to record dosimeter results directly for each dosimeter 

exchange period and each operating area. These forms were organized to enable manual entry of 

dosimeter results and to record the total annual and cumulative dose for each worker [10].

In 1958 (approximately), annual dose data were transferred to the newly implemented Hanford 

radiological computer database. During entry of the older records, a dose recorded prior to 1958 as a 

multiple of 5 mrem (0, 5, 10, 15, etc.) was rounded up to the first multiple of 10 mrem (15 mrem 

became 20, etc.). This provided consistency with the new (computer-based) practice of recording 

dose only to the first multiple of 10 mrem (10, 20, 30, etc.). This practice is still in use [11].

Multielement Film Dosimeters, April 1957 through December 1971. Hanford used multielement 

film dosimeters to measure beta, X-ray, and gamma radiation dose components in one of two designs 

during the periods of 1958 through 1961 and 1962 to 1971, respectively. These “beta/photon” film 

dosimeters consisted of four shielded regions of film and provided a substantially improved capability 

to measure the shallow, Hp(0.07), and deep, Hp(10), dose equivalent. Processing results (i.e., optical 

density) were recorded for the film response behind each filter and an algorithm was used to calculate 

the dose components. Thirty-five percent of the X-ray dose was assigned to the WB dose of record 

based on depth dose measurements in water at Hanford for 16-keV k-fluorescent X-ray (Wilson et al. 

1990). Water closely simulates the radiation response of tissue. The WB dose also included the 

assigned neutron dose, as described in this chapter, and beginning in March 1964, the assigned 

tritium dose based on methods described in Chapter 5 along with other nuclide intake into the body. 

The tritium dose was recorded separately after 1987. The skin dose of record was calculated as the 

sum of the WB (i.e., penetrating, 35% of X-ray, neutron, and tritium) and nonpenetrating doses.

Thermoluminescent Dosimeter, January 1972 through December 1994. Hanford has used TLDs 

in a few configurations. A “Basic” TLD (Kathren 1970) with limited capability for beta and photon (Xand gamma ray) radiation was used from January 1, 1971, through about 1988. This dosimeter, 

which had one chip, was assigned to personnel with little or no potential to receive dose (Wilson 

1987). Hanford Multipurpose TLDs (HMPDs) were used from January 1, 1972, through December 31, 

1994, to measure beta, photon, and neutron radiation. HMPDs originally had a five-chip design, 

which was changed to a four-chip design in July 1977 (Glenn 1977) to enable use of a commercial 

reader system and then returned to a five-chip design in January 1983 (Fleischman 1982) until the 

system was replaced on January 1, 1995, with a commercial system. The same filtration was used in 

the HMPD through all the years of use. These dosimeters were assigned to personnel likely to work 

in radiation fields. The HMPD was first accredited for performance testing in 1989 by the DOELAP in 

beta, photon and neutron radiation categories. The system has been reaccredited during later 

(typically 2-year) accreditation cycles [12].

Commercial TLD System, January 1995–Present. Hanford implemented a commercial Harshaw 

TLD system on January 1, 1995. This system includes a four-chip beta/photon dosimeter and a 

separate neutron dosimeter. Technical characteristics are described in the Hanford External 

Dosimetry Technical Basis Manual (Rathbone 2002).
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6.4.2.2 Neutron Radiation Personnel Dosimeters 

Hanford has used three general types of neutron dosimeters, which differ substantially in their 

response to neutron radiation (Brackenbush et al. 1980).

• Pocket Ionization Chamber. Prior to 1950, Hanford relied on PICs with enriched 10B liners to 

detect slow neutron exposure (Wilson 1987).

• Neutron Track Emulsion. Hanford used NTA film to measure neutron radiation from 

January 1, 1950, through December 31, 1971. The film was inserted into the two-element 

beta/photon dosimeter along with the beta/gamma film until 1958 when a plastic multielement 

neutron dosimeter with thermal neutron capabilities was implemented.

• Thermoluminescent Dosimeter. The HMPD for beta, photon, and neutron radiation was 

implemented on January 1, 1972. The HMPD was implemented as a 5-chip design with an 

automated reader system (Kocher et al. 1971). Hanford implemented a commercial Harshaw 

TLD system on January 1, 1995.

The following paragraphs describe the Hanford personnel neutron dosimeters and their periods of use 

(Fix, Wilson, and Baumgartner 1997b).

Pocket Ionization Chamber, Prior to 1950. Enriched 10B liners were used in PICs to detect slow 

neutron exposure (Wilson 1987). This method is generally acceptable to detect the presence of slow 

neutrons but not for dose measurement. There is no recorded neutron dose for any Hanford worker 

prior to 1950 (Buschbom and Gilbert 1993).

NTA Film, January 1950 to December 1971. Hanford NTA film, which was introduced on January 1, 

1950, was processed independently from the beta/photon film even though the NTA film was typically 

exchanged along with the beta/photon film. Prior to 1957, NTA film was housed in the two-element 

beta/photon dosimeter holder along with the beta/photon film. The first Hanford neutron dosimeter 

was implemented in 1958. This dosimeter had an NTA film to measure fast neutron radiation in 

addition to sensitive and insensitive beta/gamma film and selected filters (i.e., cadmium, tantalum) to 

measure thermal neutron radiation. The Hanford policy to process NTA film varied historically but 

basically involved the practice to read all NTA film for the 200 West plutonium facilities and, for other 

Hanford facilities, to process the NTA only if the photon dose was at least 100 mrem. This was based 

on the observation (Watson 1959) that neutron dose was always accompanied by photon dose. For 

the other facilities, potential neutron dose was considered to be relatively small compared to the 

photon dose. A neutron dose is recorded for all Hanford workers assigned an NTA film. If it was not

processed, a zero neutron dose is recorded. The earliest recorded neutron dose for Hanford workers 

occurred in 1950 (Buschbom and Gilbert 1993).

Five-Chip HMPD, January 1972 to June 1977. The five-chip HMPD incorporated a neutron dose 

capability that involved three of the five chips (i.e., 3, 4, and 5). The combination of these chips 

provided capabilities to estimate thermal (i.e., slow) and fast neutron components with the capability 

(chip 5) for an accurate beta/photon response correction (i.e., neutron-sensitive chips also respond to 

photon and high-energy beta radiation) (Kocher et al. 1971). Effective July 1, 1977, the dose 

algorithm was changed to use data for only four of the chips (i.e., not chip 5) to utilize the four-chip 

cards that were being implemented (Wilson et al. 1990). 

Four-Chip HMPD, July 1977 to December 1983. The HMPD dosimeter was modified to a four-chip 

design to accommodate introduction of a commercial reader system in the later 1970s that required 

the dosimeter cards to pivot around the center where chip 5 was located. Tens of thousands of 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 28 of 265

HMPD cards were fabricated with chip 5 removed. These modified cards were used in the original 

five-chip holders.

Five-Chip HMPD, January 1984 to December 1994. Routine dose evaluation with the five-chip 

HMPD was returned to service effective on January 1, 1984. Several refinements were made to this 

system (Wilson et al. 1990) to prepare for DOELAP performance testing. The HMPD was first 

accredited by DOELAP for performance testing in neutron categories in 1989 and reaccredited every 

subsequent (typically 2-year) accreditation cycle thereafter.

Commercial TLD System, January 1995 to Present. Hanford implemented a commercial Harshaw 

TLD system beginning on January 1, 1995. The neutron dosimeter system was originally a 

combination TLD and track-etch dosimetry (TED) system but essentially the TLD capability was used 

for all routine dose evaluations. Routine use of the TED capability has been discontinued because it 

did not accurately measure worker dose in the workplace (Scherpelz et al. 2000).

6.4.3 Calibration and Dosimeter Response Characteristics

In 1944, when the Hanford two-element personnel dosimeter was being implemented, an 

intercomparison test was performed with the Metallurgical and Clinton Laboratories to evaluate the 

dosimetry systems, which were essentially identical (Parker 1945). This testing led to the judgment 

that the Hanford system could be used for routine personnel dosimetry. The evaluation also 

concluded that greater attention to beta and low-energy X-rays was needed at Hanford and that 

neutron films (i.e., NTA) are useful only for higher neutron exposures than would normally occur at 

Hanford. These statements were made in 1945 prior to operation of many of the Hanford facilities. 

Later, it became evident that mixed beta/photon radiation fields and neutron radiation presented a 

significant technical challenge, which led to ongoing research and development in Hanford dosimetry 

technology [13].

Potential error in recorded dose is dependent on the dosimetry technology response characteristics to 

each radiation type, energy, and geometry; the methodology used to calibrate the dosimetry system; 

and the similarity between the radiation fields used for calibration and in the workplace. Early 

evaluations of Hanford workplace radiation fields were performed, such as for uranium by McAdams 

(1949a), plutonium surface dose (Roesch 1957; Keene 1957a), and neutron instruments by McAdams 

(1949b, 1950). The potential error is much greater for dosimeters with significant variations in 

response, such as the film dosimeters to low-energy photon radiation and the NTA and HMPD 

response to neutron radiation [14]. 

6.4.3.1 Hanford Beta/Photon Dosimeters

Hanford dosimeters were originally calibrated using 226Ra gamma, uranium beta, and 80-keV X-rays 

(HEW 1946). Routine irradiation in air (i.e., no phantom) of calibration film was done for each batch of 

film. This included 10 exposure levels from 100 to 30,000 mR to 226Ra gamma radiation, 7 exposure 

levels from 100 to 5,000 mrads to uranium beta radiation, and 7 exposure levels from 100 to 1,000 

mR from 80-keV X-ray radiation (HEW 1946). A set of calibration films was processed with all 

personnel dosimeters even if there was only one personnel assigned dosimeter processed (HEW 

1946). In the early 1950s, Hanford k-fluorescent X-ray capabilities were used to develop more 

precise dosimeter response characteristics for the lower energy photon fields in plutonium facilities 

(Wilson 1987; Fix, Gilbert, and Baumgartner 1994; Wilson et al. 1990). Studies by Fix et al. (1981, 

1982) describe technical characteristics of Hanford recorded dose compared to the delivered 

Hp(0.07) and Hp(10) dose equivalent based on work performed for Hanford’s participation in the 

DOELAP dosimeter performance testing that was formally required in the latter 1980s (DOE 1986). 

At that time, it was concluded that a 10% decrease in the recorded dose would result from on-
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 29 of 265

phantom calibration irradiations. This effect is partially compensated by the 3% increase in recorded 

dose resulting from the 137Cs dose to exposure conversion factor (Fix et al. 1982, Study 2).

No change in the recorded dose is proposed to account for the approximate 7% overestimate in the 

recorded dose prior to the implementation of on-phantom calibration or other similar comparatively 

small changes because of the overall uncertainty of changes made over the years. Table C.2 of 

Wilson et al. (1990) lists a chronology of changes to the Hanford TLD system. Wilson (1960b) 

measured a standard deviation of ±25% (one-sigma) based on numerous laboratory low-dose level 

photon irradiations performed to estimate the dosimetry detection level (i.e., about 30 mrem).

6.4.3.2 Hanford Beta/Photon Dosimeter Response Characteristics

Several studies of Hanford film dosimeter performance, stability of latent image, etc., were performed 

during the 1950s (Wilson 1957a,b, 1960a,b,c). As described in Wilson et al. (1990), many 

intercomparison and performance studies were done at Hanford and between Hanford and other 

MED/AEC/DOE facilities. These studies generally confirmed the acceptability of Hanford assessment 

of nonpenetrating and penetrating dose as defined at that time. Figure 6-4 shows the laboratory 

measured anterior-posterior (AP) photon energy response of the Hanford dosimeter systems. As 

noted in this figure, the film dosimeter OW response shows a significant over-response to lower 

energy photon radiation. Operationally, the over-response was so significant that some option was 

necessary to interpret the dosimeter OW response based on the anticipated radiation fields in the 

work environment. Hanford did use 80-kVp X-rays in 1946 (HEW 1946) to calibrate film used in 

dosimeters assigned to plutonium facility workers. The ratio of the OW to the filtered film response 

was routinely used in dose evaluation (Larson and Roesch 1954) to improve dose evaluation in mixed 

fields. An analysis is described in a letter from A. R. Keene to G. E. Backman in 1957 regarding the 

history beginning in 1949 of using a fraction (0.2) of the OW response to add to the penetrating dose 

in plutonium facilities with low-energy photons and no beta radiation (Keene 1957b). The Hanford 

recorded skin dose is calculated as the sum of the OW and S filtered film response. The recorded 

Hanford WB dose illustrated in Figure 6-3 was calculated using 20% of the OW film response in 

addition to the measured S film response using the historical Hanford dosimeter testing data in 

Appendix A of Wilson et al. (1990). As illustrated in Figure 6-3, the calculated WB dose for the lower 

energy photons characteristic of Hanford plutonium facilities is conservatively estimated using this 

practice in comparison with Hp(10). The practice is applicable only to workers in Hanford plutonium 

facilities.

0.1

1

10

100

0.01 0.1 1 10

R

e

l

a

t

i

v

e

R

e

s

p

o

n

s

e

Energy, MeV

Hp(10)

Film OW

Silver Shield

M ulti-Element Dosimeter Dose

TLD Do se

137Cs

Figure 6-4. Measured Hanford dosimeter photon response characteristics 

(Wilson et al. 1990).
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 30 of 265

Several studies of the HMPD were performed (Fix et al. 1981, 1982) in preparing for the DOELAP 

performance testing that included explicit identification of dose quantities (HPS 1983; DOE 1986) as 

measured in comparison to what is now referred to as the Personal Dose Equivalent, Hp(d), where d 

refers to a 0.07- or 10-mm depth in tissue. In general, only small changes (±10%) were necessary to 

improve comparison in laboratory studies with the deep, Hp(10), dose equivalent although additional 

changes were necessary to improve overall precision (Fix et al. 1982; Wilson et al. 1990).

In recent years, further studies of early dosimeter performance, primarily compared to Hp(10), have 

been made because of its use in worker health effect studies. The International Agency for Research 

on Cancer (IARC) conducted a dosimeter intercomparison study to higher energy (i.e., >100-keV) 

photons of 10 commonly used dosimetry systems used throughout the world (Thierry-Chef et al. 

2002). Two of the film dosimeter designs were from Hanford: (1) the two-element dosimeter design 

(identified as US-2) and (2) the multielement film dosimeter design (identified as US-8). The IARC 

Study considered that exposure to dosimeters worn by workers could be characterized as AP, 

rotational and isotropic irradiation geometries, or a combination thereof. Dosimeter response to 

selected photon energies was measured using two phantoms, which were used to simulate the effect 

of the worker’s body on the measured dosimeter response.

Hanford has conducted performance testing of historical film dosimeter designs using AP (Wilson et 

al. 1990) and angular (Fix, Gilbert, and Baumgartner 1994) irradiations on a phantom essentially 

identical to the phantom used in the IARC studies. These studies included lower energy (i.e., <100-

keV) photons that are significant in Hanford plutonium facilities. The Hanford study results for 

energies greater than 100 keV are consistent with the IARC results, showing an overestimate of 

Hp(10) for the two-element dosimeter. For energies less than 100 keV, the two-element dosimeter 

will underestimate the photon dose without using some method of adjustment such as a fraction of the 

dosimeter OW or silver shielded response. This potential under-response is evident in the original 

University of Chicago two-element dosimeter energy response curve (Pardue, Goldstein, and Wollan 

1944).

The performance of the multielement film dosimeter compared to Hp(0.07) and Hp(10) was analyzed 

using the multielement dosimeter results in Appendix A of Wilson et al. (1990). The results are 

presented in Table 6-4. This information provides good evidence that the multielement film dosimeter 

reasonably estimates Hp(10) and Hp(0.07). Application of the practice to include 20% of the OW dose 

to the penetrating dose applied to Hanford plutonium facilities, if applied to workers in the Hanford 

reactor and radiochemical facilities with primarily mixed beta and photon fields, would result in a 

significant overestimate of Hp(10) as noted in Table 6-4 for uranium and 90Sr/90Y exposures. 

A report by Fix, Gilbert, and Baumgartner (1994) describes laboratory measurements of Hanford film 

and thermoluminescent dosimeter angular response characteristics used to estimate the bias and 

uncertainty in recorded Hanford dose using methods developed by the National Research Council 

(1989) based on considerations of bias and uncertainty in radiological, environmental, and radiation 

field parameters. The report identifies biases and uncertainties in personnel dosimeter results for 

photon energies greater than 100 keV. Bias factors were found to primarily depend on the photon 

radiation energy, the geometry, and the dosimetry system.

6.4.3.3 Hanford Neutron Dosimeters

Historical aspects of Hanford neutron fields, NTA dosimeters, and calibration are described in Roesch 

(1951, 1954), Swanberg (1959) and Wilson (1960b,c) and a historical evaluation of Hanford NTA and 

HMPDs described by Fix, Wilson, and Baumgartner (1997b). Brackenbush et al. (1980) describes the 

energy response characteristics of NTA and thermoluminescent dosimeters, and these are 

characteristic of Hanford neutron dosimeters. Fundamentally, the NTA dosimeter is capable of an 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 31 of 265

Table 6-4. Analysis of multielement film dosimeter dose (Wilson et al. 1990).a

Source

Exposure 

(mR)b

Delivered dose, mremc Dosimeter dose Recorded dosed

Hp(0.07) Hp(10) Beta X-ray Gamma Skin WB

16 keV 40 43 15 0 40 0 40 14

80 86 30 16 78 7 101 34

160 173 61 106 160 0 266 56

59 keV 30 44 46 0 64 24 88 46

50 74 77 0 126 37 163 81

80 118 123 0 216 50 266 126

Cs-137 50 52 52 0 0 50 50 50

240 247 247 0 0 240 240 240

750 773 773 0 0 726 726 726

1,000 1,030 1,030 0 0 993 993 993

Sr-90/Y-90 50 50 0 74 0 0 74 0

240 240 0 302 4 0 306 1

750 750 0 1,000 16 0 1,016 6

1,000 1,000 0 1,340 18 0 1,358 6

a. Wilson et al. 1990, Appendix A, dosimeter data, average value shown in table.

b. Photon dose in mR and beta dose in mrad.

c. Exposure to dose conversion factors from DOELAP Standard (DOE 1986).

d. Skin dose = beta + X-ray + gamma. WB = gamma + 0.35 × beta

accurate dose estimate for higher energy neutron radiation greater than about 1 MeV because the 

NTA has a lower energy threshold of about 700 keV.

The Hanford TLD (Kocher et al. 1971) has a comparatively high response to thermal neutrons and is 

generally used to measure neutron radiation scattered from the workers body (i.e., the Albedo effect). 

The NTA and thermoluminescent neutron dosimeters must be calibrated to neutron spectra similar to 

that present in the workplace for accurate dose results. There are many Hanford reports on technical 

aspects of neutron source calibration (Fix, Wilson, and Baumgartner 1997b). Several address the 

controversy concerning whether a first-collision or multiple-collision neutron dose factor should be 

used. A significant change based on Hanford studies (Budd 1963) showed no significant statistical 

difference in response between NTA dosimeters exposed to PuBe and PuF4 neutron source 

irradiations in-air and on-phantom. Based on this, the identified action was to change to the multiplecollision Relative Biological Effectiveness (RBE) dose from a single collision RBE dose effective with 

the 2-week period ending July 12, 1963. The difference in recorded dose between the two calibration 

references was an increase in recorded neutron dose of about 35%.

6.4.3.4 Hanford Neutron Dosimeter Response Characteristics

Response characteristics of Hanford neutron dosimeters are described generally by Brackenbush et 

al. (1980), Kocher et al. (1971) and Fix et al. (1997b). Fundamentally, the NTA film response to 

neutron radiation decreases with decreasing neutron energy with essentially no response less than a 

“threshold” energy of approximately 400 keV. In actual Hanford workplace radiation fields, the 

threshold energy is substantially greater because of the NTA film response to photon radiation which 

makes reading the neutron-induced tracks more difficult and fading of the tracks which is most 

pronounced for lower energy neutron because the tracks are shorter. The threshold in Hanford 

plutonium facilities has been reported to be approximately 800 keV (Swanburg 1958). The albedo 

TLD response is comparatively high at lower energies and gradually declines. The TLD responds to 

all significant neutron radiation energies in Hanford workplaces albeit proper calibration is essential for 

accurate dose determination (Kocher et al. 1971; SRDB 15397). 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 32 of 265

6.4.4 Workplace Radiation Fields

Hanford operations are characterized by significant complex beta, photon, and neutron radiation fields 

in Hanford reactor, irradiated fuel processing, plutonium handling, and radioactive waste facilities [15]. 

Generally workplaces can be distinguished between those with significant beta and photon radiation 

exposures only and those with potential for neutron radiation exposures.

6.4.4.1 Beta/Photon Radiation

Field measurements of beta and primarily photon radiation spectra and dose have been performed on 

many occasions. Table 6-5 is a summary of several of those measurements that included the photon 

spectra. It is evident in the results from these measurements that the vast majority of photon dose is 

associated with higher energy photons with the exception of the plutonium facilities (308, 234-5) 

where 17-keV X-rays from plutonium and 60-keV photons from 241Am are significant [16].

Another source of workplace measurement data to evaluate beta and photon dose is presented in 

Nichols et al. (1972), in which data were collected from parallel field testing in 1970 and 1971 of the 

Hanford multielement film dosimeter and the HMPD that was implemented on January 1, 1972. 

Measurements were performed using dosimeters placed on water-filled carboys at 49 work locations 

in the Plutonium-Uranium Extraction Facility (PUREX) Facility, B-Plant, Plutonium Finishing Plant 

(PFP), 105-KE Building (reactor operating), 100-N (reactor not operating), and the 325-B, 325, and 

327 Buildings. Table 6-6 lists the collective nonpenetrating and penetrating dose measured with the 

Hanford film dosimeter and HMPD and, when available, the open window (nonpenetrating) and closed 

window (penetrating) ionization chamber “Cutie Pie” (CP) measurements. The latter section of this 

table includes results of measurements with selected calibration sources. The information in Table 6-

6 generally shows variability in the field measurements are similar to those of the calibration sources. 

A wide range of mixed beta and photon radiation and energies is characteristic of the Hanford 

facilities. The most significant difference in penetrating dose occurred at the B-Plant. This is likely 

associated with the relatively high nonpenetrating radiation dose indicative of beta and lower energy 

photons and the penetrating dose response of the HMPD to higher energy beta radiation as noted in 

Fix et al. (1982) and Wilson et al. (1990). The HMPD records a penetrating dose for higher energy 

beta radiation such as 90Sr/90Y, when there should be none, because there is only 380-mg/cm2 density 

thickness in the aluminum filter over the HMPD chip used to calculate the deep dose. The 

nonpenetrating response of the film dosimeter was routinely calibrated with a uranium slab source, 

whereas a 90Sr/90Y source was routinely used to calibrate the HMPD nonpenetrating response. There 

is an approximate factor of 2 difference in dosimeter response between these two sources and this is 

shown in this table (i.e., for 90Sr/90Y source irradiation, 690 mrem for film versus 315 mrem for TLD) 

[17].

6.4.4.2 Workplace Beta/Photon Dose Fraction

Essentially all Hanford radiological work areas involved beta/photon radiation covering a wide range 

of energies characteristic of the radionuclides being handled in the facilities and processes. Radiation 

beta/photon fields characteristic of Hanford facilities can be generally classified according to the IREP 

code input, radiation types, and energy ranges based on Hanford field measurements, the types of 

radionuclides and processes in the Hanford facilities. This is presented in Table 6-7 [18].

6.4.4.3 Neutron Radiation

Work areas at Hanford where there is a potential for neutron exposure include [19]:

• 100 Area

105-B, 105-C, 105-D, 105-DR, 105-F, 105-H, 105-KE, 105-KW, 105-N reactors
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 33 of 265

Table 6-5. Hanford workplace photon spectra measurements.

a

Facility Description Measurements Resultsb Reference

308 Bldg. Room background Gamma Am-241 (100%) Fix et al. 1981

Grinder hood bottom Gamma Am-241 (100%)

Pellet pressing station Gamma Am-241 (100%)

327 Bldg. Background A-cell Gamma Co-60 (85%), Cs-137 (8%), 

Mn-54 (8%)

Background G-cell Gamma Co-60 (79%), Cs-137 (9%), 

Mn-54 (12%)

200W, 242S Evaporator building, 

NE corner

Gamma Cs-137 (100%)

200W, diversion 

boxes

241-TX-302-C catch 

tank

Gamma Cs-137 (100%)

K2U Gamma Cs-137 (100%)

Rigging crew TLD (beta, gamma) High energy, indicative of 

photon radiation

B-Plant 

(225 Bldg)

A-Cell Gamma Cs-137 (100%)

Between B-C cells Gamma Cs-137 (100%)

Between D-E cells Gamma Cs-137 (100%)

F-cell Gamma Cs-137 (100%)

Room background Gamma Cs-137 (100%)

271B Pipe gallery –cell 9 TLD (beta, gamma) Indicative of 90Sr/90Y

324 Bldg. A-cell gallery Gamma Cs-137 (100%) Fix et al. 1982

C-cell gallery Gamma Cs-137 (100%)

Truck dock Gamma Cs-137 (100%)

331 Bldg. Office Gamma Tl-208 (90%), Cs-137 (10%) 

Change room (SE) Gamma Tl-208 (8%), Cs-137 (92%)

Change room (toilet) Tl-208 (64%), Cs-137 (36%)

Janitor’s closet Tl-208 (46%), Cs-137 (54%)

340 Bldg. 340-A outside Gamma Cs-137 (100%)

Control room Gamma Cs-137 (100%)

Decon area Gamma Cs-137 (100%)

Operations office Gamma Cs-137 (100%)

3730 Bldg Irradiation room Gamma Co-60 (100%)

Hallway Gamma Co-60 (100%)

234-5 Fluorinator hood Gamma <200 keV (99+%)

17 keV (~50%)

Roberson, 

Cummings, 

and Fix 1985

Photon energy, keV

<200 200-2000 >2000

234-5, Vault 4 Vault 4 entrance Gamma 13% 55% 33% Roberson and 

Cummings 

1986

234-5, Vault 1 Phantom Gamma 42% 55% 3%

Floor Gamma 50% 48% 2%

Entrance Gamma 17% 61% 22%

234-5, MT Room At hoods near 

entrance

Gamma 0% 83% 17%

234-5, C-Line, 

Room B

Toward neutron 

source

Gamma 92% 7% 1%

Toward room A Gamma 0% 98% 2%

Near entrance Gamma 58% 28% 14%

a. Only measurements that included photon spectra are listed.

b. Measured non-natural radionuclide significant to occupational exposure. 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 34 of 265

Table 6-6. Workplace measured nonpenetrating and penetrating 

collective doses (Nichols et al. 1972).

Facility

Nonpenetrating, mrad Penetrating, mrem

Film TLD CP Film TLD CP

PUREX 4,260 3,790 3,640 3,480 3,570 2,806

B-Plant 10,550 9,510 13,850 2,250 4,560 4,920

PFP 4,060 4,220 (np) 3,920 4,090 5,410

105-KEa 9,390 9,150 10,324 9,390 9,100 10,104

105-Nb 12,070 13,440 7,880 12,030 13,050 7,350

325-B 1,100 1,250 (np) 1,100 1,250 1,760

325 3,690 5,710 5,100 2,640 2,850 3,220

327 870 1,090 (np) 870 1,090 2,260

Calibration sources

Ra-226 260 310 (np) 260 310 300

PuF4 60 100 (np) 60 100 (np)

Sr-90/Y-90c 690 315 (np) 0 100 275

Cf-252 135 180 (np) 135 180 (np)

np=not provided in Nichols et al. (1972).

a. Plant operating.

b. Plant not operating

c. Film calibrated with uranium slab. TLD is calculated with 90Sr/90Y. There is 

about a factor-of-2 difference; results in this table illustrate this.

Table 6-7. Beta and photon radiation energies and percentages for Hanford facilities.

a

Process/

buildings Description

Operations

Radiation 

type

Energy 

selection, 

Begin End keV %

Fuel 

fabrication

Produced reactor fuel and target assemblies from uranium. Beta

Photon

>15

30–250

100

313, 306, 333 1945 1972 100

Reactors

During Operation: Highly dispersed fields of higher energy 

photon radiation fields from fission process, activation and fission 

product nuclides. Potentially narrow beams of higher energy 

neutron radiation from test ports, etc., into reactor core. Potential 

for significant airborne nuclides and there might be significant 

higher energy beta radiation. 

Beta

photon

>15

30–250

>250

100

25

75

Not in Operation: Highly dispersed fields of higher energy 

photon radiation fields from activation and fission product 

nuclides. No significant neutron radiation. There might be 

significant higher energy beta radiation during maintenance work 

resulting from fission products.

B Reactor 9/26/44 3/19/46

7/2/48 2/12/68

D Reactor 12/17/44 6/26/67

F Reactor 2/23/45 6/25/65

H Reactor 10/29/49 4/21/65

DR Reactor 10/50 12/31/64

C Reactor 11/18/52 4/25/69

KW Reactor 12/54 2/1/70

KE Reactor 2/55 1/28/71

N Reactor 12/63 1/6/87

FFTF 2/9/80 12/93
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 35 of 265

Process/

buildings Description

Operations

Radiation 

type

Energy 

selection, 

Begin End keV %

Processing 

plants

Radiochemical Operations: Highly dispersed fields of higher 

energy photon radiation fields from activation and fission product 

nuclides dominant to most exposure profiles. Potential for higher 

energy beta radiation during sampling and maintenance work 

from fission products. 

Beta

photon

>15 

30–250

>250

100

25

75

T Plant 12/26/44 3/56

B Plant 4/13/45 1956

S Plant (REDOX) 1/51 12/67

C Plant 7/52 7/67

A Plant (PUREX) 1/56 6/72

1983 1988

U Plant 3/52 1/58

UO3 Plant 56

Plutonium 

production 

Plutonium Component Production: Plutonium is machined 

into weapon components using glovebox assembly process with 

predominant close anterior exposure to workers. Radiation 

characteristics in this area involve significant lower energy 

photons and neutron radiation. Photon <30

30–250

25

Plutonium Storage: Radiation characteristics in this area 75

generally involve dispersed lower energy neutron radiation and 

scattered photons, including 60-keV Am-241 gamma ray.

231-Z 1/16/45

Plutonium Finishing Plant (234-5Z) 1949 1980

Calibrations

Hanford Site calibration of instruments and dosimeters Beta

photon

>15

30–250

>250

100

25

75

3745-A, 3745-B, 318 1945

Waste 

handling

Radiation characteristics highly dependent on source of waste, 

but typically fission product nuclides (Sr/Y-90, Cs-137) are 

dominant. 

Beta

photon

>15

30–250

>250

100

50

50 200 East and West 1953

a. Hanford documentation (Roberson, Cummings, and Fix 1985; Roberson and Cummings 1986; Rathbun 1989).

• 200 Area

271-U facility cinder block building attachment to 221-U

224-T facility to concentrate plutonium solutions and store sources

231-Z plutonium isolation facility

232-Z incinerator and leach facility

234-5Z primary plutonium handling facility

236-Z Plutonium Reclamation Facility

242-Z americium recovery facility

2736-Z plutonium vaults

• 300 Area 

308 Plutonium Fuels Pilot Plant (PFPP)

309 Plutonium Recycle Test Reactor (PRTR)

318 Radiological Calibrations Facility

324 Chemical and Materials Engineering Laboratory 

3745A Calibrations Laboratory

3745B Accelerator Facility

• 400 Area

Fast Flux Test Facility (FFTF)
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The circumstances of neutron exposure at these facilities are different and can be divided according 

to the facility of worker primary employment based on the method of primary neutron radiation 

generation. At the 200 and 300 Area plutonium facilities, neutron radiation is generated from 

plutonium either by spontaneous fission or, importantly, by alpha particle interaction with light 

elements such as oxygen, fluorine, and beryllium. These interactions are commonly referred to as 

alpha-n reactions. At the Hanford 100 and 400 Area nuclear reactor facilities, neutrons are generated 

by fission of uranium and plutonium in the reactor core. These two methods of neutron generation 

comprise the majority of the neutron exposure to workers at the Hanford Site. Therefore, this TBD 

subdivides neutron exposure of workers according to three general areas: (1)100 Area single-pass 

cooling reactors, (2) 200 and 300 Area plutonium facilities, and (3) 300 Area and Hanford Site 

research and development facilities. Potential neutron exposure at the 300 area laboratory facilities 

covers a broad range of research activities in support of the 100 Area reactor facilities; support of 

chemical processing of irradiated fuel in the 200 Areas; separation, purification and fabrication of 

plutonium; accelerator; X-ray diffractometers, medical isotope production, etc.

Attachment A presents selected Hanford measurements of neutron spectra (Fix et al. 1981, 1982; 

Roberson, Cummings, and Fix 1985; Brackenbush, Baumgartner, and Fix 1991; Endres et al. 1996) 

and dose (Fix et al. 1981, 1982; Roberson, Cummings, and Fix 1985; Brackenbush, Baumgartner, 

and Fix 1991; Endres et al. 1996; Scherpelz, Fix, and Rathbone 2000) measured at selected Hanford 

plutonium facilities on many occasions beginning in the 1970s with the availability of modern 

instrumentation. These measurements used several methods at different times to measure neutron 

dose, including Tissue Equivalent Proportional Counters (TEPCs), which are considered to provide an 

accurate measurement of neutron dose (Brackenbush et al. 1991; Scherpelz et al. 2000), as well as 

other portable neutron survey instruments (Snoopy, remball, etc.) and dosimeters (i.e., HMPDs, 

commercial TLDs, and TEDs). Neutron energy spectrum measurements primarily used multisphere 

(Bonner) sphere spectrometers as well as 3

He spectrometers, and NE-213 liquid scintillation 

spectrometers. Table 6-8 summarizes Hanford reports that included measured neutron spectra.

Table 6-8. Hanford workplace neutron spectra measurements.

a

Facility Description Measurementsa,b Reference

308 Bldg. Fuel storage pit area MS, TEPC, Rascal, HMPD Fix et al. 1981

Plutonium storage vault MS, TEPC, Rascal

Fuel pin storage box area MS, TEPC, Rascal

Bare fuel assembly MS, TEPC, Rascal, HMPD

234-5Z Glovebox H-9A MS, TEPC, Snoopy, HMPD

Glovebox HC-9B MS, TEPC, Snoopy, HMPD

2736-Z Six locations in building MS, TEPC, Snoopy, HMPD

324 Bldg Pu storage vault MS, He-3, TEPC, HMPD Fix et al. 1982

FFTF Operating deck MS, He-3, TEPC, HMPD, 

234-5Z Hood HA-23 Area Snoopy

2736-Z Storage vault, Room 1 MS, TEPC, HMPD Roberson, 

Cummings and Fix 

1985

Storage vault, Room 4

236-Z Miscellaneous Treatment

234-5Z Process line C, Room B

234-5Z Pu metal, PuF4 and PuO2 with selected 

thicknesses of acrylic shielding

MS, TEPC, HMPD Brackenbush et al. 

1991

234-5Z Frontside–storeroom MS, TEPC, TLD, TED Endres et al. 1996

Frontside–near shops

Backside–glovebox

Backside–glovebox

Pu metal, PuF4 and PuO2 with selected 

thicknesses of acrylic shielding

a. Only measurements that included neutron spectra are listed.

b. MS = multisphere, TEPC = Tissue Equivalent Proportional Counter.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 37 of 265

6.4.4.4 Workplace Neutron Dose Fraction

The AEC held a series of Personnel Neutron Dosimetry Workshops to address problems experienced 

by its sites concerning accurate measurement of neutron dose. The first workshop was held 

September 23–24, 1969 (Vallario, Hankins, and Unruh 1969), with the stated concern: “for 

intermediate energy (i.e., >0.4 eV to <700 keV) ... neutron sources, NTA personnel neutron 

dosimeters cannot be effectively used. This leaves a gap in the personnel dosimetry program which 

at many installations may be quite serious.” The workshops were generally limited to representatives 

from sites with active personnel neutron dosimetry programs and continued for a number of years. 

The 11th Workshop was held in 1991 (Rabovsky, Jones, and Pettengill 1991). The significance of the 

underestimated neutron dose became evident with studies being conducted to implement TLDs.

The HMPD was implemented on January 1, 1972. Hanford dosimetrists conducted detailed field 

measurements in the early 1970s to base the calibration of the TLD on the neutron energy spectra in 

the work environment. Studies reported by Nichols et al. (1972) involved the simultaneous placement 

of NTA dosimeters and TLDs on 2-gal polyethylene jugs filled with water and placed at selected 

workplace locations. A TEPC was used to measure the dose from fast neutrons. Data from Nichols 

et al. (1972), which are summarized in Table 6-9, indicate wide variability between the results for the 

different measurement techniques. However, the data illustrate the general under-response of the 

NTA film dosimeter results compared with the TEPC and TLD results [20].

Table 6-9. Parallel workplace measured NTA and HMPD 

neutron dose (Nichols et al. 1972).

Location

Fast neutron dose, mrem

Snoopy TEPC NTA TLD

105-KE

X-1 60 270 0 530

Top #23 1,400 1,700 470 4,100

Mon 0 0 0 60

Front face 50 900 0 250

308 Bldg.

Rm 208 2,000 2,700 270 3,700

Corr #7 4,200 14,100 1,270 11,100

Vent rm 30 30 0 0

Rm C 700 730 70 870

234-5Z Bldg.

17 DC 340 NMa 0 100

HC-11 280 NM 0 180

9B top stairs 410 NM 100 440

9B under stairs 280 NM 60 450

Rm 221 410 790 170 460

Rm 192 510 620 950 490

Rm 192-C 150 230 310 240

Rm 193 380 500 770 600

2731-Z 200 NM 60 50

a. NM = not measured.

Following implementation of the HMPD on January 1, 1972, AEC headquarters staff conducted a 

detailed review of recorded neutron dose for Hanford personnel using a committee of technical 

experts from Hanford, Savannah River Site (SRS), and other AEC facilities (Biles 1972). Central to 

this investigation was the selection of 18 long-term Hanford workers for detailed evaluation. The AEC 

study concluded that for plutonium facility workers the neutron dose was underestimated. The study 

concluded also that no Hanford worker exceeded the WB dose limit of 5 × (N-18) rem using the 

neutron-to-photon (NP) dose ratios shown in Table 6-10. The study also concluded that because 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 38 of 265

Hanford was using the best available dosimeter technology there would be no change in the recorded 

dose of record. The AEC study also concluded that the gamma radiation dose as measured by the 

film dosimeter was reasonably accurate and comparable with the photon dose measured by the TLD.

Table 6-10. AEC Study NP dose ratios (Biles 1972).

Period

NP dose ratio Comment

Plutonium

workers

Maintenance

workers

1961–1972 2.01 1.60 NP ratio as measured by the TLD during the period of use, 

January 1–July 1, 1972, is reasonably representative of 

production conditions since introduction of heavy shielding 

materials (i.e., lead, lead glass, water walls). [21]

1956–1960 1.36 1.00 NP ratio determined by applying a one-third reduction in the ratio 

for the period from 1956 through 1960 based on the use of less 

shielding to reduce exposure from lower energy X-ray and 

gamma radiation emitted by plutonium. As stated in the report, 

there was an approximate one-third reduction in photon dose 

during the period following 1960 when heavy shielding was 

installed and production was comparable.

1948–1955 1.23 1.00 NP ratio determined by applying another reduction of 10% in the 

ratio for the period from 1948 through 1955 when essentially no 

shielding other than thin plastic hood windows were used in the 

process areas. In the report, it was estimated that low-energy 

photons contributed about 10% of the penetrating gamma dose.

Attachment A contains neutron spectra measurement results for several Hanford facilities including 

separation of the dose fraction according to the IREP input energy classifications. A summary of the 

analysis of the neutron dose fraction for the Hanford facilities with neutron radiation exposure is 

shown in Table 6-11. For several particularly early facilities extensive effort would be required to 

retrieve workplace survey data that, even if available, might not contain sufficient neutron spectra data 

comparable to the measurements done in later years at Hanford with much improved instrumentation. 

Therefore, the neutron category of 0.1 to 2 MeV was selected on the basis that typically this provides 

the highest organ dose conversion factors in Appendix B of NIOSH (2007b).

6.5 Monitored Hanford Workers–Measured Dose

Hanford workers were assigned personnel dosimeters on entry into radiologically controlled areas. 

Workers with one or more recorded dose of record are considered to be monitored. The facilities 

where work was performed is evaluated from the DOE-provided documentation. Workplace location 

information usually according to work area only is interpreted from several types of claim 

documentation, as available, such as:

• Earlier handwritten dosimetry log sheets

• Dosimeter change request sheets

• Temporary dosimeter forms, might have building along with area

• Incident or contamination reports if available

• Maybe training records, but this usually just gives an area

• Computer Aided Telephone Interview

• X-ray examination documentation

If it is not feasible to identify the workplace then “default” facilities are assumed that maximize the 

calculated dose.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 39 of 265

Table 6-11. Hanford facility neutron dose fractions [22].

Process Description/buildings

Neutron energy

(MeV)

Default dose 

fraction (%)

Reactors During reactor operation: low-level neutron exposure through shielding on the face of the 

reactors and through test ports. 

100 Area B, D, F, H, DR, C, KW, KE, N 0.1–2 100

300 Area 305, 309, 318 (prior to 1985 ), 326 0.1–2 100

400 Area FFTF 0.1–2

2–20

50

50

Plutonium Plutonium finishing process: plutonium enters the process as PuF4 and is then fired into 

production pucks. Work is primarily conducted in gloveboxes with predominant close anterior 

exposure to workers. Radiation levels at the beginning of the process are fairly constant while 

levels at end of process are closely related to production levels. 

Plutonium facilities (200 Areas)

(202-A, 224-B, 224-T, 233-S, 231-Z, 232-Z, 234-5Z, 236-

Z, 242-Z, 2736-Z) 0.1–2

2–20

90

10 Plutonium handling facilities (300 Area)

(308, 309, 325)

Research

Hanford 300 Area facilities and some miscellaneous Hanford Site facilities such as the critical 

mass laboratories were used to test and evaluate processes to be used in the reactor, processing 

and plutonium production facilities. The 305 test reactor was used to test structural materials and 

fuel used in the Hanford 100 Areas and 300 Area accelerator and calibration sources were used 

to test and calibrate Hanford radiation detection instrument and dosimeter systems. A wide range 

of potential neutron spectra would be expected. However, the selection of the 0.1-to-2-MeV 

category provides the highest organ dose conversion.

100 Area–120 Bldg.

200 Area 209-E, 271-U 0.1–2 100

300 Area 309, 318, 321, 324, 3745A, 3745B

6.5.1 Photon Dose Adjustments

No adjustment in the recorded neutron dose is considered necessary. The 1972 AEC study stated 

that the photon dose of record was reasonably comparable between the film and thermoluminescent 

dosimeters (Biles 1972). The IARC study (Theirry-Chef et al. 2002) and Wilson et al (1990) studies 

have shown reasonable comparison in the recorded photon dose with the historical Hanford 

dosimeters with the general observation that generally earlier doses measured with the two-element 

film dosimeter were likely too high. Hanford did incorporate practices to account for the potential 

underestimate of the deep dose with the two-element from the low-energy photon dose component in 

Hanford plutonium facilities. There was also significantly higher energy photon radiation associated 

with fission product contamination of the plutonium that tends to minimize the potential underestimate.

6.5.2 Photon Organ Dose Conversion Factors

The measured photon dose is used with the dose conversion factors (DCFs) to calculate organ doses 

of interest using the external dose reconstruction implementation guidelines (NIOSH 2007). For 

measured photon dose for all years (film badge and TLD), the DCFs from deep dose equivalent to 

organ dose should be used. Wilson et al. (1990) states “workers are typically facing the work being 

done, and for routine radiation exposure over long time periods, the front of the torso can be expected 

to receive the largest cumulative exposure.” As such, it is recommended that the 100% AP (front-toback) geometry should be assumed for the irradiation geometry and for conversion to organ dose. 

6.5.3 Neutron Dose Adjustments

Adjustments to the Hanford recorded neutron dose are necessary to arrive at a favorable-to-claimant 

dose considering the uncertainty associated with the recorded dose as follows: [23].
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 40 of 265

• Neutron doses determined prior to January 1, 1972 with the NTA film dosimeter are likely too 

low and an NP dose ratio as discussed in Section 6.7.3 should be used to assign a favorable 

dose to the claimant.

• Neutron dose measurements with the workplace performance-validated TLD implemented in 

1972 are considered accurate with the exception of a period when the recorded neutron dose 

was too low due to use of a four-chip Hanford TLD as follows:

1978 through 1983. Adjusted neutron dose = 1.35 × recorded neutron dose

6.5.4 Neutron Weighting Factor

Adjustment to the neutron dose is necessary to account for the change in neutron quality factors 

between historical and current scientific guidance as described in NIOSH (2007b). Hanford neutron 

calibration factors determined from National Institute of Standards and Technology (NIST)-calibrated 

sources are used directly without modification for field conditions (Brackenbush, Baumgartner, and Fix 

1991). The quality factor is incorporated in the NIST calibration methodology, which used flux-todose-rate conversion factors for varying neutron energies for each calibration source. Flux-to-doserate conversion factors were based on NCRP Report 38 (NCRP 1971). The NCRP report lists both 

flux-to-dose-rate conversion factors and associated quality factors. Table 6-12 summarizes historical 

changes in the quality factors, the average NCRP 38 quality factor for the neutron energy groups used 

as input to IREP, the associated ICRP Publication 60 (ICRP 1991) weighting factor and the ratio to 

convert from NCRP Report 38 to ICRP Publication 60 (see ORAUT-OTIB-0055, ORAUT 2006a).

Table 6-12. Conversion from NCRP Report 38 (NCRP 1971) neutron quality factors to ICRP 

Publication 60 (ICRP 1991) weighting factors.

Neutron energy

(MeV)

Historical dosimetry 

guidelinesa

NCRP Report 38 group 

averaged quality factorb

ICRP Publication 60 

neutron weighting factor Ratioc

Thermal 3 2.35 5 2.13

0.5 eV–10 keV 10

10 keV–100 keV 5.38 10 1.86

100 keV–2 MeV 10.49 20 1.91

2 MeV–20 MeV 7.56 10 1.32

20 MeV–60 MeV 6.96d 5 1.00e

a. First Tripartite Conference at Chalk River in 1949 (Warren et al. 1949; Fix, Gilbert, and Baumgartner 1994); National 

Bureau of Standards Handbook 59 (NBS 1954; also known as NCRP Report 17; and Taylor 1971.

b. See Figure 3-1.

c. Ratio of the ICRP Publication 60 weighting factor to the group averaged NCRP 38 quality factor each neutron energy 

group. 

d. “Not applicable” is usually inserted here rather than the NCRP group averaged value of 6.96, which is larger than the 

ICRP Publication 60 weighting factor of 5 for 20-to-60-MeV neutrons and results in a non-favorable-to-claimant 

reduction in the corrected dose for this neutron energy group.

e. Ratio for adjusting neutron dose from NCRP Report 38 quality factor to ICRP Publication 60 weighting factor is set equal 

to unity instead of 0.7 (i.e., 5/6.96) to avoid a reduction in the recorded neutron dose for this neutron energy group.

DOE is in the process of implementing ICRP Publication 60 (ICRP 1991) neutron weighting factors 

into the routine determination of the recorded neutron dose. For Hanford, this is scheduled to begin 

effective January 1, 2010. Thereafter, no adjustment in the recorded neutron dose will be necessary. 

NIOSH is in the process of confirming these dates with DOE for the respective DOE sites.

6.6 MONITORED HANFORD WORKERS – MISSED DOSE

Wilson (1960b) conducted a detailed examination of the LOD for the Hanford dosimetry system used 

in 1960. The design of the Hanford multielement film dosimeter implemented in 1957 included the 

OW and 1-mm silver filtered region design of the two-element film dosimeter used at Hanford from 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 41 of 265

1944 to 1957. Therefore, in the Hanford studies, dose results with these different dosimeter systems 

could be evaluated as described in Wilson et al. (1990). Wilson (1960b) described three changes in 

1960 that led to a lower detection level of about 15 mrem at the 90% confidence level involving: (1) 

elimination of nonisotropic effect of calibration source, (2) automated film processing and (3) change 

to the more sensitive DuPont 508 film. He noted in this report a detection level of 40 mrem at the 

95% confidence level for the Hanford two-chip dosimeter system with the DuPont 502 film used prior 

to these changes. An important consideration in this analysis concerned the level of potential missed 

dose. Wilson describes the analysis of 49 batches of Hanford routine calibration results that indicated 

a 25% standard deviation at the 30-mrem calibration level based on the optical density readings. 

Based on an analysis of the capabilities of the densitometer used to process the film, he estimated a 

likelihood of 0.33 (1/3) that a dose of 15 mrem would not be detected. The likelihood that this would 

occur for each successive monthly exchange for an entire year would be (0.33)12 or about 1 in a 

million. Based on the 13 exchanges during the year at that time, he estimated a maximum potential 

missed dose of 195 mrem (i.e., 15 × 13). Conversely, Wilson estimated that about 8% of the time a 

positive dose would be recorded for dosimeters that received no exposure. A similar analysis could 

be performed for the dosimeter used prior to 1960 with an estimate that about 30 mrem would be 

detected one-third of the time.

Hanford did use a practice of locating dosimeters at the badge control building for each operating area 

for each person expected to routinely enter. Therefore, some Hanford workers had dosimeters 

simultaneously located at several different Hanford areas. Dosimeters from each of these areas were 

processed and a dose assigned to the worker. In many cases, a zero dose was recorded for all the 

dosimeters. Assuming a worker had dosimeters at seven Hanford work areas and using the 40-mrem 

LOD noted in the previous paragraph for the two-element dosimeter with 502 film, a potential missed 

dose of 140 mrem (i.e., 7 × 40/2) using OCAS-IG-001 (NIOSH 2007b) for each exchange period or, if 

this occurred throughout the year, potential missed dose of 1,680, 3,360 and 6,720 mrem for monthly, 

biweekly, and weekly exchange periods, respectively, could have occurred. Often, the assigned 

missed dose for a monitored worker with zero recorded dose will unrealistically exceed the dose for 

other workers with recorded positive dose. It is recommended in this TBD that the guidance of 

OCAS-IG-001 (NIOSH 2007b) be applied to the recorded dose for each exchange period regardless 

of the number of dosimeters assigned to a worker (i.e., one for each operating area). Using the 

analysis of Wilson et al. (1990), the likelihood of all dosimeters reading zero for an exchange period 

when there is positive dose can be calculated as (0.33)y where y is the number of areas [24].

The analysis of missed recorded dose for Hanford workers has been separated according to photon 

and neutron missed dose [25]. 

6.6.1 Photon Missed Dose

Missed photon dose for Hanford workers occurs when a zero dose is recorded for the dosimeter 

measured dose for any response less than the site dose recording threshold. Methods to be 

considered if there are periods during a working career for which no doses were recorded have been 

examined by Watson et al. (1994). In general, estimates of the missed dose can use dose results for 

coworkers or the recorded dose for the same worker before and after the period of missed dose. 

However, these situations require careful examination. The missed dose for dosimeter results is 

particularly important for earlier years when recording thresholds were higher and dosimeter 

exchange was more frequent.

NIOSH (2007b) describes options to calculate the missed dose. The recommended option is to 

estimate a potential missed dose where LOD/2 is multiplied by the number of zero or less than LOD/2 

dose results. LODs for the Hanford beta and photon dosimeters normally cited are based on 

laboratory irradiations. Actual LODs are higher because of additional uncertainty in actual field use 

and the use of dose recording thresholds. Table 6-13 summarizes the potential missed dose. 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 42 of 265

Reasonable LODs are listed in this table for most applications for film dosimeters based on Wilson 

(1960b, 1987), NIOSH (1993), National Research Council (1989), and Wilson et al. (1990) and for 

TLDs from Fix et al. (1982) and Rathbone (2002).

Table 6-13. Hanford beta/photon dosimeter period of use, type, LOD, exchange 

frequency, and potential annual missed dose.

Period of usea Dosimeter

LODb

(rem)

Exchange 

frequency

Hanford beta/photon dosimeters

Prior to October 1944 PIC 0.005 Dailyc (n=250)

October 1944–December 1950 Hanford two-element film 0.040 Weekly (n=52)

January 1951–March 1957 0.040 Biweekly (n=26)

April 1957–May 1957 Hanford multielement film 0.030 Biweekly (n=26)

May 1957–December 1971 0.030 Monthly (n=12)

January 1972–December 1994 Hanford TLD 0.020 Monthly (n=12)

0.020 Quarterly (n=4)

January 1995 to 2003 (ongoing) Harshaw TLD 0.010 Monthly (n=12)

0.010 Quarterly (n=4)

a. For many years, Hanford workers had a dosimeter assigned to each operating area where they 

worked.

b. Estimated LODs for each dosimeter technology in the workplace. Dose values were recorded 

at levels less than the LOD

c. Not routinely exchanged.

6.6.2 Neutron Missed Dose

Neutron radiation was present in the Hanford 100 Area reactors; 400 Area FFTF; 300 Area 

accelerator (3754B) and neutron source calibrations (3745A, 318 and U-271 Buildings); and 200 and 

300 Area plutonium facilities. There is potential for significant missed neutron dose among workers in 

the plutonium facilities where workers separated and finished plutonium (i.e., 202-A, 224-B, 224-T, 

231-Z, 232-Z, 233-S, 234-5Z, 236-Z, 242-Z, 2736-Z, 271-U, 308 Plutonium Fabrication Pilot Plant, 

309 PRTR, and 324 laboratory) for use in nuclear weapons. Workers were close to the plutonium and 

in the early years actually physically moved the plutonium from one work location to the next. The 

approach recommended for use to calculate the neutron missed dose can be divided into two periods: 

(1) prior to 1972, and (2) after 1971 as follows:

Prior to 1972: During this period the recorded neutron doses were too low. The missed neutron 

dose is calculated by multiplying the dosimeter missed photon dose by an NP dose ratio (see 

Section 6.7).

After 1971: During this period the Hanford TLD was used. In this case, the missing dose is based on 

the LOD of the dosimeter. Table 6-14 summarizes the reported limits of detection and the calculated 

annual missed dose for the periods. 

6.7 UNMONITORED HANFORD WORKERS

There should generally not be any occupationally exposed unmonitored Hanford workers because 

Hanford procedures (Parker 1948b) required that any worker entering a radiological controlled area 

be assigned a dosimeter. However, there might be some situations regarding work activities outside 

the 100, 200, 300 and 400 Operating Areas that might involve comparatively low-level exposure.

6.7.1 Coworker Assigned Photon Dose

An estimated photon dose to unmonitored Hanford workers can be determined from monitored 

coworkers. ORAUT-OTIB-0020 (ORAUT 2008a) provides general instructions to evaluate the 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 43 of 265

Table 6-14. Hanford neutron dosimeter period of use, type, LOD, exchange 

frequency, and potential annual missed dose.

Period of use Dosimeter

Exchange 

frequency

LOD 

(rem)a

October 1944–December 1949 PICs with B-10 enriched 

liners

Dailyb (n=250) 0.010

January 1950–December 1950 NTA Weekly (n=52) 0.080

January 1951–March 1957 Biweekly (n=26) 0.080

April 1957–May 1957 Biweekly (n=26) 0.080

May 1957–December 1971 Monthly (n=12) 0.080

TLD 

January 1972–December 1994 HMPD–4 or 5 chips Monthly 0.050

January 1995–present Harshaw TLD Monthly 0.015

a. Estimated film dosimeter photon radiation detection levels before 1972 and neutron dosimeter 

LODs after 1971.

b. Dosimeter not routinely assigned.

measured and missed doses for monitored Hanford workers to arrive at a favorable-to-claimant dose 

to be assigned to unmonitored workers. Attachment B contains the details of the evaluation of 

Hanford coworker dose to be assigned to unmonitored workers. These measured doses do include 

an analysis of the missed dose which is particularly significant for the earlier years with higher LODs 

and frequent dosimeter exchanges (weekly or biweekly). Attachment B, Table B-2 provides the 50th-, 

95th-, and 99th-percentile coworker penetrating (gamma) and nonpenetrating doses. Figure 6-5 

shows the trend in the coworker assigned 95th percentile in comparison with the 95th percentile for 

the measured penetrating WB dose.

Figure 6-5. Annual Hanford external coworker 95th-percentile penetrating doses modified to account 

for missed dose in comparison with 95th-percentile measured dose (rem).
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 44 of 265

6.7.2 Construction Trade Workers

Construction Trade Workers (CTWs) measured doses are increased to account for uncertainty for 

reasons described in ORAUT-OTIB-0052 (ORAUT 2007b). For extended employment periods 

without a measured dose, consideration is necessary as to whether to assign an unmonitored dose 

using the coworker doses presented in Attachment B. In this case, the measured coworker 

penetrating annual dose has been multiplied by a factor of 1.4 (per ORAUT-OTIB-0052) and the 

missed dose determined using OCAS-IG-001 guidance. Attachment B, Table B-3 provides the 50th-, 

95th-, and 99th-percentile CTW doses to be assigned. Figure 6-6 illustrates the annual dose to be 

assigned in comparison with the 95th-percentile assigned coworker penetrating (gamma) doses and 

the 95th-percentile measured doses.

Figure 6-6. Annual Hanford 95th-percentile penetrating CTW assigned doses in comparison with 

95th-percentile coworker assigned and measured doses (rem). 

6.7.3 Neutron-to-Photon Dose Ratio 

There are numerous examples of workers exposed to neutron radiation prior to 1972 in which zero 

neutron dose results were recorded and particularly prior to implementation of the multielement 

neutron dosimeter in 1958 (Buschbom and Gilbert 1993). A spreadsheet (Yamauchi 2006) of Hanford 

worker NTA processing results during the period from 1950 to 1961 was developed by DOE in the 

preparation of PNNL-11196 by Fix, Wilson and Baumgartner (1997b). The decision to stop 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 45 of 265

assignment of NTA film personnel neutron dosimeters to Hanford single-pass cooling production 

reactor and N Reactor workers was made effective during April 1966 (DUN 1966). Therefore, this can 

be considered an unmonitored exposure and an estimate of the dose based on NP dose ratio 

distributions determined from workplace instrument measurements of paired neutron and photon 

doses and using post-1971 TLD measurements of paired neutron and photon measured doses. A 

substantial effort was made to obtain relevant survey records from the DOE Richland Operations 

Office (RL) archives. In the process of doing this, an extensive list of relevant historical documents 

was collected and developed into a timeline of radiation-associated events. The timeline was used in 

the analyses for the Hanford 100, 200 and 300 Area facilities. The timeline is presented in 

Attachment D, Table D-2. This approach to reconstruct dose to Hanford workers is consistent with 

the 1972 AEC review (Biles 1972) of pre-1972 NTA neutron dose results in Hanford plutonium 

facilities. The photon dose was reliably measured and essentially any significant Hanford neutron 

dose was accompanied by significant photon dose.

Issues to be considered to arrive at a favorable-to-claimant ratio for pre-1972 Hanford facility 

operations with potential neutron exposure of workers are presented for each of the primary operating 

areas in the following sections.

6.7.3.1 100 Area Single-Pass Cooling Reactors.

All of the Hanford single-pass cooling reactors (B, C, D, DR, F, H, KE, KW) were shut down as of 

January 1971 prior to the implementation of the HMPD in 1972. As described in Taulbee et al. (2008) 

Hanford neutron and photon radiation survey records were collected and used to evaluate and 

subsequently develop an NP ratio to reconstruct neutron doses to workers around Hanford’s singlepass reactors that operated from 1945 to 1972. A total of 5,773 paired neutron and photon 

measurements extracted from 57 boxes of survey records were used in the development of the NP 

ratio, Figure 6-7. The development of the NP ratio enables the use of the recorded photon radiation 

dose from an individual’s personnel dosimeter to be used to estimate the unmonitored neutron dose. 

The Pearson rank correlation between the neutron and photon measurements was 0.71, indicating a 

reasonable degree of correlation (i.e., values approaching 1.0 show strongest correlation) between 

increasing photon dose and increasing neutron dose.

The NP ratio was found to be somewhat higher in the upper levels of the reactor compared to the 

front face, ground, and the experimental levels. Information obtained through an interview with a 

retired radiological control technician (Fix 2007a; Bihl 2008a) indicated that the upper levels were not 

frequented by workers, and the relatively large number of measurements made was due to routine 

monitoring requirements for the higher exposure areas. Based on the information provided in an 

interview (Fix 2007a), the most plausible NP ratio is on the order of 0.6. Giving the benefit of the 

uncertainty to the claimant, the assumption is made that the distribution of measurements is a 

reasonable favorable-to-claimant assumption. Therefore the overall NP ratio is calculated to be 0.8.

The NP ratio was examined across all of Hanford’s single-pass reactors and across the period from 

1945 through 1971 (Taulbee et al. 2008). There did not appear to be any major differences in the 

ratio across reactors or time. Even though the power level and the dose rate increased over time, the 

NP ratio remained relatively constant. As a result the application of the NP ratio can be considered 

reasonable across all of the Hanford single-pass reactors from 1944 through 1971.

NP Ratio Application

The NP ratio should be applied to all reactor area workers who wore a film dosimeter (i.e., issued a 

dosimeter) to estimate the neutron dose. The NP ratio data best fit a lognormal distribution with a 

geometric mean (GM) of 0.8, a geometric standard deviation (GSD) of 3.0, and the upper 95th 

percentile of this distribution was 4.8 (Figure 6-8). This distribution is combined with measured and 

missed dose distributions using Monte Carlo methods described in ORAUT-OTIB-0012, Technical 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 46 of 265

Photon Dose Rate (mR/hr)

0.1 1 10 100 1000 10000

Neutron Dose Rate (mrem/hr)

0.1

1

10

100

1000

10000

Pearson Correlation = 0.71

Spearman Correlation = 0.55

n=5773

50th % NP ratio 0.8:1

95th % NP ratio 4.75:1

Current TBD 50th % NP ratio 0.4:1

Figure 6-7. Single-pass reactor paired neutron and photon survey 

measurements.

Information Bulletin: Monte Carlo Methods for Dose Uncertainty Calculations (ORAUT 2005a). The 

resulting total neutron dose should be partitioned for input into IREP assuming that 10% is < 10 keV, 

10% is due to neutrons between 10 and 100 keV and 80% is from neutrons from 0.1 to 2 MeV 

(Taulbee et al. 2008).

Percentile

1 2 5 10 20 30 50 70 80 90 95 98 99

Neutron to Photon (NP) Ratio - All Data

0.01

0.1

1

10

Equation 3

Lognormal Distribution

GM = 0.8

GSD = 2.95

95th% = 4.75

n=5773

Figure 6-8. Probability distribution of the NP ratio. The thin solid line 

represents the equation 3 fit.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 47 of 265

Construction Workers

Based on interviews with former workers, workers on minor construction projects at Hanford would 

sometimes work in neutron zones when the reactor was operating. They would, however, have 

received a photon dosimeter prior to commencing work. Therefore, if a construction worker received 

a dosimeter from the 100 Area, the dose reconstructor should assume neutron exposure occurred 

unless there is other information indicating the construction work was only conducted while the reactor 

was shut down or in a non-neutron radiation exposure area [i.e., work area was not conducted in the 

process monitoring room, front face (C elevator), assembly work area, outer rod rooms, viewer, 

experimental levels, top of the unit, balcony, C or D machinery rooms, or the winch level]. Most 

notably, if the work was conducted only in the disassembly basin area, no neutron dose should be 

assigned. 

Specific Locations

Generally the standard NP ratio with a GM of 0.8 with a GSD of 3.0 should be used for all workers 

unless an individual’s records indicate that they worked in an area with only photon exposure such as 

in refueling when the reactor was not in operation or in a specific area of the reactor. For example, if 

records indicate a worker was assigned to a special project such that they were on the X levels for 

their full shift for multiple weeks, the measured lognormal distribution with a GM of 0.5 and a GSD of 

2.97 (Table 6-15) should be used for dose reconstruction. When a dose reconstructor has information 

that an individual’s work was only on the top of the reactor during operations, the measured NP ratio 

with a GM of 2.33 and a GSD of 1.84 should be applied.

Table 6-15. Lognormal parameters of NP ratio for Hanford 

reactors (Taulbee et al. 2008).

Work 

location

NP ratio

GM GSD 95th percentile

General work location

General 0.8 3.0 4.8

Specific work locations

-9-ft level 0.83 1.70

Front face 0.50 2.79

X levels 0.50 2.97

Upper levels 2.33 1.84

The eight Hanford 100 Area single-pass cooling reactors (B, D, F, H, DR, C, KW, and KE, in order of 

startup) were operated between September 1944 and January 1971, as summarized in Table 6-16

(DeNeal 1970). 

Table 6-16. Operating history of Hanford single-pass 

production reactors (DeNeal 1970).

Reactor Startup Deactivation Max power levela

B 09-26-1944 02-12-1968 2210

D 12-17-1944 06-26-1967 2165

F 02-25-1945 06-25-1965 2040

DH 10-29-1949 04-21-1965 2140

DR 10-03-1950 12-30-1964 2015

C 11-18-1952 04-25-1969 2500

KW 01-04-1955 02-01-1970 4400

KE 04-17-1955 01-29-1971 4400

a. Power in megawatts, held for 24 hours.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 48 of 265

6.7.3.2 100 Area N Reactor 

Attachment E contains a technical basis for neutron dose reconstruction for Hanford 100 Area N 

Reactor Workers during the period of its operation from December 1963 through January 1987. The 

design of the N Reactor was different from the 100 Area single-pass reactors in that primary coolant 

water was recirculated under pressure, allowing for much higher operating temperatures and, as is 

typical of commercial light-water reactors, substantial buildup in the coolant system of neutron 

activation and fission product nuclides resulting in increased significance of penetrating photon 

radiation fields generally, and of beta/photon radiation fields in maintenance work of reactor 

components. The N Reactor core was surrounded by special layers of reflector graphite, watercooled thermal shields constructed of boron steel and cast iron, and by a primary shield of highdensity concrete. Helium gas formed the pile atmosphere within a sealed system that prevented 

worker access without reactor operator knowledge while the reactor was operating. A fog spray 

system at both the front and rear reactor faces was provided for contamination control and cooling in 

case of a loss of contaminated steam from the core. These design features tended to limit 

opportunities for worker neutron radiation exposure. Throughout the years of N Reactor operation 

extensive administrative and technical limits were in effect such as in the form of operating safety 

limits and process standards. Startup of the reactor was particularly complex, involving a complete 

building radiation survey at stated levels of power ascension (Berrett and Hall 1964). The radiation 

environment at N Reactor was divided into five protective zones with different shielding and entry 

requirements (Bunch, 1962). 

• Zone 1, which is adjacent to the charge face, the discharge face, and the top of the reactor. 

No access is possible to this zone during operation. Monitored access is possible during 

reactor shutdown. This zone is operated at a negative pressure relative to Zone 2.

• Zone 2, which includes secondary radiation areas such as the inner and outer rod rooms, the 

gas system, the flux and rupture monitor room, the ball system, and the ventilation exhaust 

system from Zone 1. Normally, no access to the restricted areas of Zone 2 will be required 

during operation but limited emergency access is possible. Zone 2 is operated at a negative 

pressure relative to Zone 3.

• Zone 3 is a normal access or buffer zone with free access at all times except perhaps for quite 

abnormal conditions. This zone includes most of the work regions and corridors around the 

reactor in which metal handling and other routine operations are conducted.

• Zone 4 is an unlimited access area with essentially no elevated radiation exposure during 

normal operations.

• Zone 5 is defined as a warranted access area in which continuous access is maintained at all 

time including emergencies. Zone 5 is limited to the main control room and the main 

instrument room beneath the main control room.

Interestingly, although Hanford had available portable radiation protection instrumentation to readily 

measure neutron exposure in the workplace (WHC 1988) and there were requirements for surveys 

when there was a potential for significant exposure, few of the hundreds of Hanford survey forms 

examined actually included results of surveys for neutron radiation exposures. There were 

requirements for neutron surveys during startup at defined power levels in power ascension testing. 

Nearly 1 year of testing during 1964 was necessary for the N Reactor to achieve the design power of 

4,000 MW (thermal) on December 9, 1964 (WHC 1988, Chapter 14). During testing in 1964, elevated 

photon and neutron radiation levels were measured (Greenborg and Berry 1964) emerging through N 

Reactor steam vent penetrations that are located in the bottom shield of the reactor and open to the 

southeast and southwest corners of the ball hopper retrieval system. The corrective action consisted 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 49 of 265

of adding a pipe offset to achieve a labyrinth design and providing additional shielding. This action 

was required for purposes of radiation protection and to reduce the possibility of neutron activation of 

system components in the ball recovery room (Hall 1964).

A collaborative effort with DOE Hanford Radiological Records was conducted with the objective to 

select only the N Reactor worker recorded neutron and photon doses (i.e., actually shallow, deep, 

neutron, X-ray, eye dose categories) from 1964 through 1987 separately from doses for workers at 

the other single-pass reactors (which stopped operations in January 1971) and other Hanford 

operating areas. The methods used to select this data are described in Attachment E. The query 

resulted in dose results for a total of 592 selected workers for whom there were a total of 4,825 dose 

records with a collective dose of 3,301,070 mrem of photon penetrating dose. A scatter plot of the 

recorded annual shallow, neutron and extremity dose normalized to the recorded deep (photon) dose 

for each worker and each year is shown in Figure 6-9. The shallow and deep doses are closely 

associated as would be expected because the majority of the shallow dose results from penetrating 

photon radiation. As noted in Attachment E, there is essentially no correlation between the recorded 

neutron and photon doses overall. There were only 30 annual dose records with photon and neutron 

doses ≥30 mrem, respectively; and only 14 records for TLD-only results. The explanation is likely that 

there are few occasions when workers receive a measurable neutron exposure, whereas significant 

photon dose is received in many routine work tasks including when the reactor was not operating and 

there was no neutron exposure. This lack of correlation between photon and neutron recorded doses 

was also observed by investigators analyzing a large amount of commercial power reactor neutron 

and photon measured doses (Eisenhauer and Schwartz 1983).

N-Reactor (1963-87) Worker Dose Pattern

0.001

0.01

0.1

1

10

100

1955 1960 1965 1970 1975 1980 1985 1990

Year

Recorded Dose/(Deep Dose)

Shallow/Deep

Neutron/Deep

Extremity/Deep

NTA TLD NTA Stopped

Figure 6-9. Trend of 100-N worker recorded shallow, neutron, and extremity annual 

dose to recorded deep dose for 4,777 records with deep annual dose >0. 

The ratio of the collective neutron dose measured with the TLD system during 1973 and 1974 was 

0.002 and 0.004, respectively, of the collective measured photon dose. There was a single worker 

who had TLD-measured neutron dose during 4 years (1972–0.027 rem, 1974–0.003 rem, 1977–0.042 

rem, 1978–0.027 rem) and for the other years there was no measured neutron dose (1973, 1975, 

1976, 1979, 1980, 1981, 1982, 1983, 1984, 1985 and 1986). Attachment E describes the logic for two 

identified options. One option is to base the NP ratio on the single worker who had TLD-measured 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 50 of 265

neutron dose during 4 years (1972–0.027, 1974–0.003, 1977–0.042, 1978–0.027) and for the other 

years there was no measured neutron dose (1973, 1975, 1976, 1979, 1980, 1981, 1982, 1983, 1984, 

1985 and 1986). In this option the 50th-percentile (i.e., GM) is equal to 0.04 and to the maximum NP 

ratio a factor of 2 greater (i.e., 0.08) which is assumed in this analysis to be approximately the 95thpercentile. The second option is to utilize the statistical parameters for a lognormal distribution of the 

14 TLD results. There is a large difference in the assigned neutron dose between these two options 

(i.e., Option #1: GM = 0.04, 95th percentile = 0.08; Option #2: GM = 0.06, 95th Percentile = 0.4) as 

shown in Table E-5. Certainly, the most favorable to claimant option is provided using Option #2. 

The assigned neutron doses must also incorporate the ICRP Publication 60 weighting factor, which 

for the neutron category of 0.1 to 2 MeV is equal to 1.91 (ICRP 1991), and thus a further increase in 

assigned neutron dose of nearly a factor of 2 will occur. Attachment E illustrates the significant 

assigned neutron dose that would be assigned in the 1972–1986 TLD period compared to the TLDmeasured dose if this approach was applied in dose reconstruction.

NP Ratio Application

For the period prior to January 1, 1972, to estimate the assigned neutron dose, a NP ratio should be 

applied to all N Reactor area workers with a DOE-reported dose (including zero) at Hanford to 

estimate the neutron dose. The distribution of NP dose ratios recommended to result in a favorableto-claimant neutron dose estimate has a GM of 0.06, a GSD of 3.1, and an upper 95th percentile of 

0.4. This distribution is combined with measured and missed dose distributions using Monte Carlo 

methods described in ORAUT-OTIB-0012 (ORAUT 2005a). The resulting total neutron dose should 

be partitioned for input into IREP assuming that 100% is associated with neutron energies from 0.1 to 

2 MeV.

Construction Workers

Based on interviews with 100-N workers including persons who worked at 100-N throughout its entire 

operating history, all workers including construction workers were subject to controls regarding entry 

and exit from identified workplace zones. Protective practices were described in Special (or 

Radiation) Work Permits (SWPs), including requirements for assigned personnel dosimeters and 

other worker protective actions as needed (extremity dosimeters, respirator, full-time monitoring 

support, etc.). During the period from 1964 through 1971 when the Hanford neutron dosimeters were 

not assigned, if a construction worker had a DOE-reported dose at the N Reactor, the dose 

reconstructor should assume neutron exposure occurred unless there is other information indicating

the construction work was conducted only while the reactor was shut down or in a non-neutron 

exposure area (i.e., in the 100-N area outside of the reactor building 105 or outside of steam 

generator building 109).

Specific Locations

Considering that 100-N Area reactor workers might have worked at one or more of the other reactor 

areas, determining that a worker worked solely at the 100 Area N Reactor could be difficult. General 

Electric Corporation (GE), Douglas United Nuclear (DUN), and United Nuclear Industries (UNI) were 

responsible at different times for operation of all the 100 Area reactors. The last of the single-pass 

reactors, KE and KW, terminated operations during January 1971 (see Attachment D, Table D-2). 

The general 100 Area single-pass reactor NP ratio (i.e., GM = 0.8, GSD = 3.0) should be used if there 

is doubt as to the location of employment of a worker in the Hanford 100 Area reactors prior to 

January 1971. If it can be determined that a worker was employed only at the N Reactor, the NP 

dose ratio distribution parameters shown in Table 6-17 should be used.

The assigned neutron doses determined using the NP ratios in Table 6-17 must also incorporate the 

ICRP Publication 60 weighting factors for the 0.1 to 2 MeV neutron category (ICRP 1991). This 

requires multiplication of the assigned dose by a factor of 1.91 for the IREP Parameter 1 input.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 51 of 265

Table 6-17. Lognormal parameters of NP ratio for Hanford 

N Reactor (Attachment E).

Work location

NP ratio

GM GSD 95th percentile

General work location

N Reactor 0.06 3.1 0.4

6.7.3.3 200 Area Plutonium Facilities

Attachment F contains a technical basis for neutron dose reconstruction for Hanford 200 Area 

Plutonium Facilities. A team of health physicists examined many boxes of DOE Hanford archives to 

identify and retrieve workplace radiation survey records particularly the records with paired photon 

and neutron measurements and the technical references of historical radiation-associated events as 

shown in Attachment D, Table D-2. The selected records are included in the SRDB and the SRDB 

references are included in the analysis files. Table 6-18 summarizes the types of records, the records 

selected for analysis of the NP ratio for the 200 Area Plutonium Facilities and the basis for the 

selection.

Table 6-18. Hanford 200 Area plutonium facility NP ratio survey records (see Attachment F).

Description

No. of 

records

Selected 

for NP 

analysis Basis for selection

2003 claim TLD data 186 186 Paired post-1971 TLD measurements with neutron 

and photon dose, respectively ≥ 20 mrem.

1972 AEC study, film data 189 0 Paired pre-1972 NTA data are suspect.

1972 AEC study, TLD data 113 113 Paired post-1971 TLD measurements with neutron 

and photon dose, respectively ≥ 20 mrem.

1962–1971 Radiation Control 

Reports, film data

177 0 Paired pre-1972 NTA data are suspect.

1972–1976 Radiation Control 

Reports, TLD data

16 0 TLD data are suspect because of comparatively 

low measured neutron dose. The presence of an 

albedo material, which is essential for TLD 

performance, in the measurements is not known.

1962-1976 Radiation Control 

Reports, instrument data

161 161 All of the instrument measured doses by trained 

health physics technicians are considered to be of 

good quality. Technical reports, instrument 113 114

Workplace surveys, instrument 1,195 845

Total 2,150 1,419

Hanford plutonium facility operations involve substantial sensitive information particularly during the 

period of construction and operation during the 1940s to 1960s and even today information is still 

classified. An important consideration in the retrospective analysis of neutron exposure to workers in 

relation to the measured photon dose concerns the specifics of the isotopic mix of plutonium and also 

fission product contamination. The fission product contamination resulted in significant higher energy 

photon exposure to plutonium facility workers (Smith 1958; Chitwood 1960; Hopkins and Crocker 

1961; Watsen 1964; Slind 1966). Type of fuel (i.e., uranium natural or level of 235U enrichment, mixed

uranium and plutonium oxide or thorium) and the reactor irradiation time in megawatt-days is directly 

associated with the isotopic composition of the plutonium handled at PFP. There are also issues 

associated with the effectiveness of the T-Plant, B-Plant, REDOX, and PUREX processing with 

respect to the type and concentration of potential fission product contaminants (zirconium, ruthenium, 

etc.) as well as inventories handled at PFP associated with Buy-Back Program and various national 

and international research activities. Broadly speaking, the plutonium is categorized as weapons or 

reactor (or fuel) grade as shown in Attachment F, Figure F-2. Worker neutron exposure is highly 

associated with the concentration of 240Pu, which increases in the irradiated fuel with the total reactor 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 52 of 265

exposure (i.e., megawatt-days). Reactor-grade fuel typically receives much higher exposures as 

compared to weapons-grade fuel and will result in higher exposures to workers.

As described in Attachment F, 1,346 Hanford 200 Area Plutonium Facility neutron and photon 

radiation survey records were collected as shown in Figure 6-10 and used to evaluate and 

subsequently develop an NP ratio to reconstruct neutron doses to workers. The Pearson rank 

correlation between the neutron and photon measurements was 0.76, indicating a reasonable degree 

of correlation between increasing photon dose and increasing neutron dose. A total of 1,419 

measured NP ratio measurements (i.e., one reference did not provide measured neutron and photon 

dose rates but only the NP ratio measured values) extracted from several sources as listed in 

Table 6-18 were used in the development of the NP ratio shown in Figure 6-11. 

Figure 6-10. Hanford 200 Area plutonium facility NP ratio measurements.

As described in Attachment F, the NP ratio was found to be dependent on the workplace and 

measurement method. As noted in previous evaluations of neutron dose levels, the fluorination hood 

area showed the highest measured photon (and neutron) dose rates and NP dose ratios. As noted in 

the documents in Attachment D, Table D-2, it was Hanford practice to monitor worker exposures and 

to rotate workers if cumulative doses approached regulatory limits. The AEC investigation in 1972 of 

Hanford worker neutron doses concluded that no worker exceeded regulatory dose limits (Biles 1972). 

This is consistent with the interview information for several Hanford Site Experts described in 

Attachment F. 

NP Ratio Application

The NP ratio should be applied to all Hanford 200 Area plutonium handling facilities workers who wore 

a film dosimeter (i.e., issued a dosimeter) to estimate the neutron dose. This distribution is combined 

with measured and missed dose distributions using Monte Carlo methods described in ORAUT-OTIB0012 (ORAUT 2005a). The resulting total neutron dose should be partitioned for input into IREP 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 53 of 265

Figure 6-11. Probability distribution of the 200 Area plutonium facility NP ratio for 

instruments and dosimeters (Attachment F). 

assuming that 10% is due to neutrons between 10 AND 100 keV and 90% is from neutrons from 0.1 

to 2 MeV (Attachment F).

Construction Workers

Based on interviews with persons who worked at Hanford plutonium facilities beginning as early as 

1947 and with collective work experience extending essentially throughout the entire operating period 

of PFP operations, all workers (including construction workers) were subject to controls regarding 

entry and exit from identified workplace zones. Protective practices were described in Special or 

Radiation Work Permits. All workers in this facility were assigned personnel dosimeters and for all 

years the assigned NTA dosimeters were processed. All PFP work areas involved some potential for 

neutron radiation exposure. Therefore, if a construction worker had a DOE-reported dose at the 

Hanford 200 Area plutonium facilities, the dose reconstructor should assume neutron exposure 

occurred.

Specific Locations

Any worker in a 200 Area plutonium facility should be considered to have received potential neutron 

exposure. In Attachment F, analysis of 1,419 NP ratio measurements is described and a summary 

presented in Table 6-19 for various selections of the data. The data for all 1,419 NP measurements 

shows a NP dose ratio distribution with a GM of 1.13, a GSD of 2.30, and a 95th percentile of 4.47. 

The plutonium fluorination hood shows the highest instrument measured neutron and photon dose 

ratio distribution with a GM of 1.68, a GSD of 2.57 and a 95th percentile of 7.94 but when combined 

with the 1972 and later TLD data shows an overall NP ratio distribution with a GM 0f 0.82, a GSD of 

2.56 and a 95th percentile of 3.85. The TLD data show much less variability than the instrument 

measured photon and neutron doses, which are made with different instruments.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 54 of 265

Table 6-19. Lognormal parameters of NP ratios for Hanford 200 Area plutonium facilities 

(Attachment F).

Workplace measurements No. GM GSD 95th% Fita

All data: TLDs + Instruments 1,419 1.13 2.30 4.47 0.18

TLD data–ALL 299 0.69 2.36 2.83 0.06

TLD data–2003 claims 186 0.73 2.10 2.47 0.09

TLD data–AEC study 113 0.63 2.77 3.37 0.06

Instrument data–all 1,120 1.29 2.17 4.64 0.22

Instrument data–radiation control reports 161 1.23 2.74 6.45 0.13

Instrument data–fluorination hoods 7A/9A & 7C/9B 71 1.68 2.57 7.94 0.19

Instrument data–hood 7A/9A 17 1.95 2.61 9.47 0.23

Instrument data–hood 7C/9B 54 1.60 2.57 7.56 0.20

Instrument data–technical reports 113 0.53 2.83 2.94 0.06

Instrument data–workplace surveys 846 1.47 1.80 3.85 0.23

Fluorination hoods instrument plus TLD worker measured 370 0.82 2.56 3.85 0.07

The 7A/9A and 7C/9B fluorination hoods represent a bounding Hanford plutonium facility workplace 

condition because of the higher measured NP dose ratio but also significantly because of the 

significantly greater measured photon (and neutron) radiation dose rates as shown in Table 6-20. 

This workplace location shows a measured neutron dose rate distribution with a GM of 14.41 

mrem/hr, a GSD of 1.17 mrem/hr, and a 95th percentile of 32.86 mrem/hr.

Table 6-20. Measured neutron dose rates for Hanford 200 Area plutonium facilities.

Workplace

No. of 

points

Neutron dose rate, mrem/hr

GM GSD 95th percentile

Fluorination Hoods 71 14.41 1.65 32.86

Button line 62 2.90 1.53 5.82

Other 28 1.00 1.17 1.29

For glovebox workers, the guidance in OCAS-TIB-010 (NIOSH 2005) for plutonium glovebox workers 

should be applied as needed. The assigned neutron doses determined using the NP ratios in 

Table 6-20 must also incorporate the ICRP Publication 60 weighting factors for a default neutron dose 

fraction of 10% and 90% (ICRP 1991) for the 0.01-to-0.1-MeV and 0.1-to-2-MeV neutron categories, 

respectively. This requires multiplication of the assigned dose by factors of 1.86 and 1.91, 

respectively, for the IREP parameter 1 input. This approach will result in significant assigned neutron 

dose for the period prior to January 1, 1972.

6.7.3.4 300 Area Reactor, Plutonium and Miscellaneous Hanford Research Facilities

The Hanford 300 Area Reactor and Plutonium research, development, and testing facilities, the 300 

Area Radiological Calibrations facilities, and the site critical mass laboratory facilities did involve 

neutron radiation exposure of workers as evidenced by (1) the types of operations, (2) routine 

assignment of nuclear track emulsion (i.e., NTA) film, and (3) information in the routine radiation 

monitoring periodic reports listed in Attachment D, Table D-2. Operations in these facilities supported 

the much larger 100 Area reactor and 200 Area chemical processing and plutonium chemicalmetallurgical facilities. Extensive radiation surveys were taken of these facilities because Hanford 

radiation safety standards applied to all facilities in the 100, 200, and 300 Area facilities. Events in 

these facilities are included in the various Hanford routine reports noted in Attachment D, Table D-2. 

Attachment G contains a technical basis for neutron dose reconstruction for Hanford 300 Area reactor 

and plutonium facilities and Hanford miscellaneous research facilities other than the 100 Area reactor 

and 200 Area plutonium facilities.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 55 of 265

NP Ratio Application

The recommended dose reconstruction parameters to be applied for 300 Area reactor, plutonium, and 

miscellaneous Hanford facility research workers based on workplace information and the extensive 

instrument and TLD measurements obtained for the 100 Area single-pass reactors and the 200 Area 

Plutonium facilities are: 

• TLD-measured neutron dose should be used from January 1, 1972 to date. 

• Prior to 1972, the measured (and missed) photon dose should be multiplied by an NP dose 

ratio to arrive at an assigned neutron dose. The selection of the NP dose ratio is based on 

comparison of 300 Area Facility Process with the 100 or 200 Area production facilities. For 

example, the 305 test reactor would utilize the distribution of measured NP dose ratios for the 

single-pass cooling production reactors and the Building 308 plutonium fuels facility would 

utilize the distribution of measured NP dose ratios for the 200 Area plutonium finishing plant. 

In this approach, NP ratios determined from extensive workplace measurements in the 100 

Area reactor and 200 Area plutonium facilities, respectively, would be applied to workers in the 

300 Area reactor and plutonium facilities based on favorable-to-claimant judgment by the dose 

reconstructor. Neutron exposures in the 120 Building and 209-E critical mass laboratories to 

workers did occur but were relatively insignificant for routine operations because of the 

significant shielding and remote operation. Under all circumstances there was substantial 

photon radiation that was reasonably accurately measured in all facilities and for all periods 

that accompanied the neutron radiation. The parameters of the NP dose distribution are 

shown in Table 6-21.

Table 6-21. Summary of measured neutron dose rates for application to Hanford 300 Area 

and Hanford facilities with some potential for neutron exposure.

Process Reference

Neutron to photon dose ratio

GM GSD 95th percentile

100 Area single-pass cooling reactors Taulbee et al. 2008 0.8 3.0 4.8

100 Area N Reactor Attachment E 0.06 3.1 0.4

200 Area plutonium–Not a glovebox worker Attachment F 1.1 2.3 4.5

200 Area process line–glovebox worker Attachment F 1.7 2.6 7.9

For glovebox workers, the guidance in OCAS-TIB-010 (NIOSH 2005) for plutonium glovebox workers 

should be applied as needed. These NP ratios must be adjusted to incorporate the ICRP Publication 

60 weighting factors (ICRP 1991). The assumed neutron energy IREP input category is assumed to 

be 0.1 to 2 MeV. Therefore, the values in the above table are multiplied by a factor of 1.91. It is 

evident that using this approach will result in significant assigned neutron dose for the period prior to 

January 1, 1972.

Construction Workers

Based on interviews with persons who worked in the Hanford 300 Area facilities (308, 318, 321, 3745) 

beginning in the early 1950s with collective work experience extending essentially throughout the 

entire period of 300 Area Facility operations, all workers, including construction workers, were subject 

to controls regarding entry and exit from identified workplace zones. Construction workers at critical 

mass and miscellaneous facilities in the 100 and 200 Areas had similar requirements. Protective 

practices were described in Special or Radiation Work Permits including the assignment of personnel 

dosimeters as well as other worker protective needs such as respirators, other dosimeters and 

monitoring support. Many 300 Area facilities involved some potential for neutron radiation exposure. 

Therefore, if a construction worker had a DOE-reported dose in a facility in the Hanford 300 Area, the 

dose reconstructor should assume neutron exposure occurred.
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Specific Locations

The majority of workers in the Hanford 300 Area and Hanford Site supporting research facilities did 

not have potential for significant neutron radiation exposure relative to potential photon radiation 

exposure. However, there was potential neutron exposure in many different facilities from a wide 

variety of causes including neutron-emitting radioactive nuclides, reactors, and fissile materials. 

Therefore, it is particularly important to determine if a neutron exposure was physically possible (i.e., 

potential neutron radiation from reactor, accelerator, alpha emitting nuclides, or neutron emitting 

nuclides) based on workplace processes and job activities for a worker to determine if a neutron dose 

should be assigned. Once the TLD was used beginning on January 1, 1972, the neutron dose was 

reliably measured along with potential beta and photon radiation.

6.7.3.5 NP Dose Ratio Summary

NP dose ratio distributions developed in previous sections for Hanford reactor and plutonium facility 

workers are summarized in Table 6-22. The assigned neutron dose is calculated by applying these 

ratios to the recorded photon dose and the calculated missed photon dose, respectively. It should be 

noted that if the Energy Employee has recorded neutron dose, the assigned neutron dose should be 

compared with the recorded neutron dose and the assigned dose used only if it is greater [26].

Table 6-22. Hanford NP dose ratio summary [27].

Process Description/buildings

NP ratio

GM GSD Upper 95th %

Reactors During reactor operation: low-level neutron exposure through shielding on the face of the 

reactors and through test ports. 

B, D, F, H, DR, C, KW, KE Reactors 0.8 3.0 4.8

N Reactor 0.06 3.1 0.4

300 Area Test Reactors (305, 309, 318, 326) 0.8 3.0 4.75

400 Area FFTF N/A

Plutonium 

production

Plutonium finishing process: plutonium enters the process as PuF4 and is then fired into 

production buttons. Work is primarily conducted in gloveboxes with predominant close 

anterior exposure to workers. Radiation levels at the beginning of the process are fairly 

constant while levels at the end of the process are closely related to production levels. 

Plutonium Facilities (200 Areas) (224-T, 231-Z, 232-Z, 234-5Z, 236-Z, 242-Z, 2736-Z, 271-U)

Plutonium Laboratories (300 Area) (308, 309, 324)

Non-glovebox worker 1.1 2.3 4.5

Glovebox worker 1.7 2.6 7.9

Critical Mass 

Laboratory

Highly shielded laboratory facilities used to test limits of criticality reactor and geometry 

conditions.

120, 209E 1.1 2.3 4.5

Research and 

Development

Wide variety of Hanford 300 Area facilities used to test and evaluate processes used in the 

100 Area reactor and 200 Area chemical processes and plutonium separation, purification, 

and handling. Hanford Site instrument and dosimeter development, testing and calibration 

was done in 300 Area facilities. 

3745A, 3745B, 318, 1.1 2.3 4.5

a. Applicable to facilities with significant potential for neutron exposure and prior to TLD use.

6.8 UNCERTAINTY 

Uncertainty in the reconstructed organ dose encompasses a wide array of sources such as 

incomplete monitoring, measurement error, and the effectiveness of Hanford radiation safety 

practices. IREP organ dose input for a claimant for each year of employment consists of the annual 

dose in Parameter 1 and measures of uncertainty in Parameters 2 or 3 depending on the selected 

probability distribution. Judgment has been used to achieve favorable-to-claimant organ dose 

estimates as described in the following sections.
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6.8.1 Measured Photon Dose

Uncertainty in the measured dosimeter photon radiation dose for Hanford historical dosimeters has 

been evaluated in several studies as highlighted in the following:

• Wilson (1960b) conducted a detailed examination of the LOD for the Hanford dosimetry 

system based on the analysis of 49 batches of Hanford routine calibration results that 

indicated a 25% standard deviation at the 30-mrem calibration level based on optical density 

readings. Based on an analysis of the capabilities of the densitometer used to process the 

film, he estimated a likelihood of 0.33 (1/3) that a dose of 15 mrem would not be detected. 

The likelihood that this would occur for each successive monthly exchange for an entire year 

would be (0.33)12 or about 1 in a million. Based on the 13 exchanges during the year at that 

time, he estimated a maximum potential missed dose of 195 mrem (i.e., 15 × 13). Conversely, 

Wilson estimated that about 8% of the time, a positive dose would be recorded for dosimeters 

that received no exposure. A similar analysis could be performed for the dosimeters used 

prior to 1960 with an estimate that about 30 mrem would be detected one-third of the time.

• BNWL-542, The Establishment and Utilization of Film Dosimeter Performance Criteria 

(Unruh et al. 1967), contains discussion of proposed personnel film performance criteria that 

includes statistical analysis of Hanford calibration dosimeters during the period from 1950 to 

1964, which included more than 600 measurements on each of several exposures levels of 

gamma, beta and 17-keV X-ray radiations. The records evaluated and tabulated in Table 6-23 

were for 11 exposure levels of gamma and 8 for X-ray radiation.

Table 6-23. Bias and variance features for Hanford film dosimeter 

records.

Type of 

radiation

Exposure 

(mrem) Mean

Relative 

error

Percent of measurements 

within ±2 sigma

Gamma

0 5.18 430 95.4

15 14.50 186 99.0

30 29.53 35 94.3

60 57.96 19 95.8

90 88.87 14 96.0

120 120.74 10 95.0

180 179.24 8 97.6

240 237.72 6 95.7

300 301.46 5 96.0

500 499.36 4 99.1

750 749.82 0.7 99.1

X-ray

0 -9.49 -34 96.6

10 10.13 28 95.8

20 20.34 17 94.9

40 39.85 11 95.7

60 59.93 8 96.0

80 79.68 8 96.6

120 120.27 4 96.4

160 159.60 4 99.0

The criteria in this document were used to develop performance testing criteria used in a study 

of 35 government, military and commercial dosimeter processors at that time.

• PNL-7447, Description and Evaluation of the Hanford Personnel Dosimeter Program From 

1944 Through 1989 (Wilson et al. 1990), contains several results of quality evaluations of 

Hanford dosimeters to include examination of the results of blind audit dosimeters. The 
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authors identified bias factors for the Hanford facilities using each of the Hanford dosimetry 

systems. They defined the bias factor to be a ratio of the Hp(10) dose to the recorded dose. 

These factors are presented in Table 6-24.

Table 6-24. Uncertainty in beta/photon Hp(10) in Hanford facilities (Wilson et al. 1990).

Facility type

Beta/photon field 

description Dosimeter type

Bias factor 

rangea

Min. Max. Comments

Fuel 

fabrication

Uranium beta and 

gamma radiation

Two-element film 0.5 1.6 Recorded WB dose 

approximates Hp(10) response 

results noted in this TBD.

Multiple-element film 0.7 1.3

TLD 0.8 1.2

Reactor High-energy beta and 

photon radiation.

Two-element film 0.5 1.7 Recorded WB dose 

approximates Hp(10) response 

results noted in this TBD 

because predominant photon 

energy >100 keV. 

Multiple-element film 0.7 1.4

TLD 0.8 1.2

Fuel 

reprocessing

Generally mixed beta 

and photon radiation

Two-element film 0.5 1.6 Recorded WB dose 

approximates Hp(10) response 

results noted in this TBD 

because predominant photon 

energy >100 keV.

Multiple-element film 0.7 1.3

TLD 0.7 1.3

Plutonium 

finishing

Predominant photon 

energy <100 keV.

Two-element film (b) (b) Significant uncertainty is 

associated with dose estimates 

in low-energy photon fields 

with the two-element 

dosimeter.

Multiple-element film 1.0 2.0

TLD 0.6 1.4

Waste and 

laboratory

Generally mixed beta 

and photon radiation

Two-element film 0.5 1.6 Recorded WB dose closely 

approximates Hp(10) response 

results noted in this TBD 

because predominant photon 

energy >100 keV.

Multiple-element film 0.7 1.3

TLD 0.8 1.2

a. Bias factor defined as ratio of Hp(10) to recorded WB photon dose.

b. No estimate provided by the authors.

• PNL-10066, An Assessment of Bias and Uncertainty in Recorded Dose from External Sources 

of Radiation for Workers at the Hanford Site (Fix et al. 1994), involving irradiation of Hanford 

film and thermoluminescent dosimeters on a phantom to a selection of photon radiation 

exposures with energy >100 keV at selected angles of 0°, ±45°, ±90°, ±135°, and 180°. This 

information along with measured beta and photon radiation dosimeter responses on phantom 

in PNL-7447 (Wilson et al. 1990) provided information used to estimate uncertainty in 

measured dose for workplace AP, rotational, and posterior-anterior exposures for predominant 

photon energies. The approach used in this report was considered to be an elaboration of the 

approach used to quantify the bias and uncertainty in estimated doses for personnel exposed 

to radiation as a result of atmospheric testing of nuclear weapons between 1945 and 1962 

(National Research Council 1989). The approach was developed by the National Research 

Council Committee on Film Badge Dosimetry in Atmospheric Tests. It involved quantifying 

both bias and uncertainty from four sources and then combining them to obtain an overall 

assessment using methods used in the evaluation of bias and uncertainty for persons exposed 

to radiation from an atmospheric nuclear detonation (National Research Council 1989). In this 

approach, uncertainty is evaluated from laboratory uncertainty (i.e., calibration, processing), 

radiological uncertainty (i.e., spectrum, wearing, and backscatter), environmental uncertainty 

(i.e., consequences of light, moisture, and high temperatures), and uncertainty resulting from 

converting recorded measurements of exposure to estimates of deep dose. The assessment 

was based on the assumption that uncertainties from individual sources followed independent 

lognormal distributions. For each uncertainty source, a factor is assigned reflecting bias (B) 
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and a 95% uncertainty factor (K); the uncertainty factor was determined so that the interval 

obtained by dividing and multiplying by this factor would include 95% of all observations. 

Assessment of these factors was based on careful evaluation of the available evidence but, 

because evidence was not adequate for rigorous statistical treatment of most uncertainties, 

subjective judgments were also required. Once the individual sources were evaluated, an 

overall bias factor was obtained by multiplication and an overall uncertainty factor obtained 

through lognormal propagation of errors. The results of this analysis for Hanford workers (for 

facilities other than plutonium facilities) are presented in Table 6-25.

Table 6-25. Overall bias and uncertainty due to variation and uncertainties regarding energy levels 

and geometry in recorded dose as an estimate of deep dose (Fix, Gilbert, and Baumgartner 1994).

Hanford dosimetry system

Bias magnitude and range Uncertainty factors

Overall biasa Range in biasb Systematicc Randomd

Two-element film (1944–56) 1.27 1.13–1.60 1.2 1.8

Multielement film (1957–71) 1.02 0.86–1.12 1.1 1.4

Multielement thermoluminescent (1972–83) 1.12 1.04–1.16 1.05 1.2

Multielement thermoluminescent (1984–93) 1.01 0.95–1.05 1.05 1.2

Commercial TLDe (1995-2003) 1.00 0.95-1.05 1.05 1.2

a. Based on the distribution of energy levels and geometry judged most likely. Divide recorded dose by the table's bias 

value to calculate deep dose. Note that this use of bias factor does not apply to plutonium facilities.

b. Range of overall bias factors based on alternative distributions of energy levels and geometry.

c. Systematic uncertainty resulting from lack of knowledge regarding actual distributions of energy levels and geometry.

d. Random uncertainty resulting from variation among workers in energy levels and geometry.

e. Performance equal to or better than previous Hanford dosimeters.

• The Study of a Selection of 10 Historical Types of Dosimeter: Variation of the Response to 

Hp(10) with Photon Energy and Geometry of Exposure (Thierry-Chef et al. 2002) was done in 

support of the IARC 15-Country Epidemiologic Study (Cardis et al. 2005). IARC conducted a 

dosimeter intercomparison study involving irradiations on-phantom of 10 dosimetry systems 

used throughout the world in AP, rotational, and isotropic geometries to three selected >100-

keV photon beams. Two of the film dosimeter designs were from Hanford. These studies 

provided similar overall assessments in that for the tested irradiations, the Hanford doses 

determined with the multielement film and thermoluminescent dosimeters showed reasonable 

accuracy with the delivered deep dose (i.e., bias factors of 1.01 to 1.12, random uncertainty 

95th percentile of 1.2 to 1.4). The Hanford two-element dosimeter used prior to 1957 

overestimated the delivered deep dose (i.e., bias factor of 1.27, random uncertainty 95th 

percentile of 1.2-1.4). As noted in the Wilson et al. (1990) report, the two-element dosimeter 

will underestimate the deep dose in the low-energy photon plutonium facilities unless Hanford, 

as noted in Hanford reports, did assign 20% of the nonpenetrating dose to the deep dose.

6.8.2 Measured Neutron Dose

As noted in this report, the recommended dose reconstruction approach is to not use the recorded 

neutron dose prior to January 1, 1972. The recorded dose is likely too low. The recommended 

approach is to estimate a favorable-to-claimant neutron dose using the measured and missed photon 

dose, with adjustments, multiplied by an NP dose ratio. The recommended NP dose ratio is favorable 

to the claimant. However, there are several studies of measured neutron dose uncertainty for 

Hanford neutron dosimeters. Uncertainty in the measured dosimeter neutron dose is closely 

associated with the evaluation of uncertainty in the dosimeter photon or penetrating dose because the 

accuracy in neutron dose determination is often dependent on the level of photon dose. There is 

typically greater variability for the measured neutron dose because of the approximate 9-order-ofmagnitude range in potential neutron energies (i.e., 0.001 eV to ~ 20 MeV) in the workplace, the 

energy-dependent response characteristics of the dosimeter, and basically greater variability in the 

neutron dose response because of a greater number of interaction dependencies.
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• BNWL-542, The Establishment and Utilization of Film Dosimeter Performance Criteria 

(Unruh et al. 1967), contains results of applying the proposed personnel film performance 

criteria to a group of 35 government, military, and commercial dosimetry laboratories. The 

results as tabulated by the original researchers are shown in Tables 6-26 and 6-27 for thermal 

and fast neutron results, respectively. Not all laboratories had neutron dose capabilities.

Table 6-26. Test irradiations–thermal neutrons (Unruh et al. 1967).

Processor

number

Relative error Bias as % of dose

Given dose (mrem) Given dose (mrem)

60 120 382 60 120 382

1 225 245 0 17 18 -47

2 495 320 356 267 358 366

3 8 4 5 2 -1 -9

4 347 415 37 417 417 393

5 – – – – – –

6 – – – – – –

7 17 16 4 13 11 15

8 24 14 6 -8 0 2

9 215 122 14 633 467 419

10 420 527 203 550 500 524

11 174 145 83 617 558 628

12 8 16 10 52 44 39

13 – – – – – –

14 – – – – – –

15 – – – – – –

16 – – – – – –

17 – – – – – –

18 – – – – – –

19 – – – – – –

20 68 20 13 83 92 42

21 – – – – – –

22 – – – – – –

23 – – – – – –

24 – – – – – –

25 0 0 0 25 -17 -15

26 – – – – – –

27 – – – – – –

28 – – – – – –

29 19 21 22 -75 -82 -81

30 33 32 4 40 -3 -7

31 – – – – – –

32 340 212 131 683 633 246

33 – – – – – –

34 3,447 122 414 1300 675 340

35 – – – – – –

Average 365 139 81 288 229 178

6.8.3 Measured Beta Dose

Uncertainty in the measured dosimeter beta or nonpenetrating dose is closely associated with the 

evaluation of uncertainty in the dosimeter photon or penetrating dose because the same dosimeter 

responses are being evaluated. There is typically greater variability for the nonpenetrating or beta 

component for film dosimeters in particular because of the much greater response (i.e., compared to 

shielded film response) from lower energy photons. However, the performance of the dosimeter to 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 61 of 265

Table 6-27. Test irradiations–fast neutrons (Unruh et al. 1967).

Processor

number

Percent Relative error Bias as % of dose

Given dose (mrem) Given dose (mrem)

200 262 787 200 262 787

1 27 8 21 -93 -76 -66

2 448 348 105 220 99 -27

3 17 33 41 30 15 14

4 61 86 120 5 3 51

5 21 23 12 8 9 7

6 26 66 22 65 53 62

7 43 26 13 19 8 10

8 – – – – – –

9 19 43 54 14 50 25

10 92 79 204 90 99 105

11 12 73 21 55 53 42

12 56 27 15 25 21 15

13 27 12 20 80 92 91

14 17 5 1 49 38 46

15 – – – – – –

16 61 21 38 60 69 76

17 – – – – – –

18 – – – – – –

19 31 28 36 90 111 140

20 11 7 10 12 11 6

21 – – – – – –

22 – – – – – –

23 31 26 30 115 95 93

24 115 72 57 110 111 89

25 27 23 16 8 -6 18

26 22 25 13 32 28 23

27 12 15 74 41 38 29

28 – – – – – –

29 25 51 39 80 92 80

30 7 12 6 -75 -73 -72

31 59 46 31 145 156 152

32 33 55 70 80 61 20

33 16 23 13 -1 14 -2

34 124 315 193 -47 31 12

35 – – – – – –

Average 53 57 47 45 45 38

lower energy photons from filtered X-ray sources and beta sources were routinely done. Several 

studies as highlighted in the following:

Wilson (1960b) conducted a detailed examination of the LOD for the Hanford dosimetry system based 

on the analysis of 49 batches of Hanford routine calibration results that indicated a 25% standard 

deviation at the 30-mrem calibration level based on optical density readings. Based on an analysis of 

the capabilities of the densitometer used to process the film, he estimated a likelihood of 0.33 (1/3) 

that a dose of 15 mrem would not be detected. The likelihood that this would occur for each 

successive monthly exchange for an entire year would be (0.33)12 or about 1 in a million. Based on 

the 13 exchanges during the year at that time, he estimated a maximum potential missed dose of 195 

mrem (i.e., 15 × 13). Conversely, Wilson estimated that about 8% of the time, a positive dose would 

be recorded for dosimeters that received no exposure. A similar analysis could be performed for the 

dosimeter used prior to 1960 with an estimate that about 30 mrem would be detected one-third of the 

time.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 62 of 265

• BNWL-542, The Establishment and Utilization of Film Dosimeter Performance Criteria

(Unruh et al. 1967), contains discussion of proposed personnel film performance criteria that 

includes statistical analysis of Hanford calibration dosimeter during the period from 1950 to 

1964, which included more than 600 measurements on each of several exposure levels of 

gamma, beta and 17-keV X-ray radiations. The records evaluated and tabulated in Table 6-28 

were for 11 exposure levels for beta radiation.

Table 6-28. Relative error values for electron exposure of Hanford film 

dosimeters, 1950–1964 (Unruh et al. 1967).

Type of 

radiation

Exposure 

(mrem)

Hanford reported doses

Meana

Percent relative 

error

Percent of measurements 

within ± 2 sigma

Beta

0 9.03 460 97.3

15 14.31 137 95.7

30 30.42 59 95.1

60 59.09 31 95.8

90 87.30 24 94.6

120 117.88 18 96.3

180 178.15 16 97.6

240 241.12 12 96.7

300 298.93 12 94.2

500 498.55 5 96.6

750 749.46 1 98.8

a. Reported doses in mrem.

6.9 SHALLOW DOSE

6.9.1 Assigned Shallow Dose

Hanford practice was to assign to the skin the sum of the penetrating WB dose from photon, neutron, 

and tritium and to add the nonpenetrating dose from beta and low-energy photon radiation. In this 

manner, all measured dose components were assigned to the skin. There is uncertainty with respect 

to reconstructing the skin dose in workplace situations because of the complex mixed radiation fields 

and the range of parameter effects associated with geometry, shielding and dosimeter response. 

Figure 6-12 illustrates that in parallel workplace studies in 1970 and 1971 of thermoluminescent and 

film dosimeters that the film measured nonpenetrating dose was typically greater than the TLD 

measured nonpenetrating dose. Guidance on determining the reconstructed skin dose can be 

obtained from Attachment C for Hanford workers.

6.9.2 Assigned Extremity Skin Dose

There is uncertainty with respect to reconstructed extremity skin dose because of geometry, shielding 

and dosimeter response parameters. It has been Hanford practice to assign to the extremities all 

recorded WB skin dose (i.e., beta, photon, neutron and tritium) and also to assign any measured 

extremity dose. Extremity dosimeters were routinely assigned to Hanford radiation workers who 

directly handled uranium, plutonium or beta emitting nuclides with a significant potential to result in a 

significant extremity dose and certainly whenever the extremity dose might be more limiting than the 

measured WB dose. Hanford dosimeter processing procedures in 1946 clearly describe practices to 

prepare rings and pads (i.e., film mounted on a rubber pad to be placed in the hands or other places 

of the body were a ring could not be used) and practices to calibrate these dosimeters using radium, 

uranium and X-ray (80 kVp) irradiations (HEW 1946). Durum (1946) describes badge and contact 

exposures in Hanford 300 Area Building 313-314 fuel canning operations. A 7 day weighted average 

exposure of 776 mrep to the skin of the finger was determined. The maximum hand exposure was 
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0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

1.1

1.2

1.3

1.4

1.5

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5

F

i

l

m

,

r

a

d

TLD, rad

Figure 6-12. Comparison of Hanford film and TLD nonpenetrating dose results

(Nichols et al. 1972).

determined to be 234 mrep/day for the finish machining task stated to be a continuous operation. 

Ongoing concern for potential significant hand exposures is evident in many of the early plutonium 

finishing plant studies listed in Attachment D, Table D-2. Several reports were prepared by Helgeson. 

A standard monitoring practice was to establish a factor between WB and extremity exposures to 

determine when the extremity dose would be limiting and, as such, when extremity dosimeters should 

be assigned. Hanford did initiate preparation of daily and weekly worker restricted dose lists (HEW 

1946) which listed workers with film or PIC results exceeding 100 mR. Analysis of the dose to be 

assigned to workers on these lists was necessary prior to incurring any further exposure. Certainly 

this is one factor involved in the policy for each worker to be assigned two PICs and to record the 

lower dose because of the substantial tendency of the PIC to over-estimate the dose.

The factor is typically based on radiation guidelines for the extremity, skin, and whole body, which 

have varied over the years. At the 1949 meeting in Chalk River, Canada, among U.S., United 

Kingdom, and Canadian nuclear weapon development organizations, several aspects of operational 

health physics were defined (Taylor 1971). The identified limits were:

Whole body–0.3 rem/wk;

Skin–0.5 rem/wk and 

Extremity–1.5 R/wk.

Based on comparison of the dose limits, it would not be necessary to monitor the extremity dose 

unless it was greater than a factor of about 5 multiplied by the WB dose, otherwise the WB dose 

would be limiting. Therefore, it is recommended that the measured WB dose be increased by a factor 

of 5 to assign a dose to the extremities based on the premise that extremity dosimeters would have 

been assigned and the dose reported for any higher exposures [28].

6.9.3 Assigned Pre-October 1944 Extremity and Skin Dose

Natural uranium fuel fabrication for Hanford reactors was begun during 1943 (DuPont 1945). The 

Hanford film dosimeter was first used at the B Reactor during September 1944 (Wilson 1987). The 

Hanford PIC was implemented during January 1944 and used to determine the official dose of record 

until the film dosimeter system was available. However, the Hanford PIC had little response to 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 64 of 265

Uranium beta radiation. Durum (1946) describes monitoring practices and measurements of the 

whole body, hand and extremity skin doses received in Hanford Buildings 313 and 314 fuel fabrication 

operations. These measurements involved the placement of extra film badges on all Bldg. 313-314 

personnel for a period of about two-days (Bldg 314 done and then Bldg. 313). Time studies were 

made using stop watches for those operations known to involve considerable uranium metal contact. 

Only operations with actual or near-actual contact were considered. Table 6-29 summarizes the 

maximum assigned doses during a work day. For work with uranium metal prior to October 1944, 

dose reconstructors should assign a skin dose for the relevant employment period. The equivalent 

annual dose is presented in Table 6-29 which is approximately the maximum potential dose to be 

considered for assignment (i.e., October 1943 through September 1944). 

Table 6-29. Maximum assigned pre-October 1944 skin 

dose in Hanford reactor fuel fabrication (Durum 1946).

Dosimeter location

Skin dose, mrem

Per day Per year

Whole body skin 65 23,725

Hand dose 234 85,410

Finger dose 776 283,240

a. Measured dose from bare metal.

b. Weighted 7-day average exposure.

6.10 NON-SITE-SPECIFIC FACTORS

6.10.1 Adjustment for Glovebox Workers

There is uncertainty with respect to the reconstructed organ dose in the lower abdomen for workers 

working substantially in a chemical bench top environment such as the Hanford plutonium facility 

glovebox operators. Guidance in OCAS-TIB-0010, Best Estimate External Dose Reconstruction for 

Glovebox Workers (NIOSH 2005), should be used to adjust the measured photon dose to Hanford 

workers in identified Hanford 200 and 300 Area plutonium facilities notably 231-Z, 234-5, and 308 

where extensive and long-term glovebox work was conducted. Generally this correction should be 

considered for any worker with a glovebox checked on the Computer Assisted Telephone Claim form 

and whether the identified places of work did include glovebox or other benchtop work environments.

6.10.2 Construction Trade Workers

There is uncertainty with respect to the reconstructed organ dose for Construction Trade Workers 

because of the nature of their work activities in maintaining Hanford facilities and equipment. An 

adjustment factor of 1.4 multiplied by the organ dose components for each year of Hanford 

employment is recommended as described in ORAUT-OTIB-0052, Parameters to Consider When 

Processing Claims for Construction Trade Workers (ORAUT 2007b).

6.11 ATTRIBUTIONS AND ANNOTATIONS 

Where appropriate in the preceding text, bracketed callouts have been inserted to indicate 

information, conclusions, and recommendations to assist in the process of worker dose 

reconstruction. These callouts are listed in this section with information that identifies the source and 

justification for each item. Conventional references are provided in the next section that link data, 

quotations, and other information to documents available for review on the Oak Ridge Associated 

Universities Team (ORAU) servers.

Jack Fix served as the initial Subject Expert for this document. Mr. Fix was previously employed at 

the Hanford Site; his work involved management, direction, or implementation of radiation protection 

and/or health physics program policies, procedures, or practices related to atomic weapons activities 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 65 of 265

at the Site. This revision and earlier revisions have been overseen by a Document Owner who is fully 

responsible for the content, including all findings and conclusions. Mr. Fix continues to serve as a 

Site Expert for this document because he possesses or is aware of information relevant to the 

reconstruction of radiation doses experienced by claimants who worked at the Site. In all cases 

where such information or prior studies or writings are included or relied on by Mr. Fix, those materials 

are fully attributed to the source. Mr. Fix’s Disclosure Statement is available at www.oraucoc.org.

Fred Duncan assumed responsibility as Document Owner for this document in September, 2008. Mr. 

Duncan replaced Edward Scalsky when Mr. Scalsky’s employer declared a new corporate conflict of 

interest for the Hanford Site. Mr. Scalsky continues to participate on this document team in the 

appropriate role of Subject Expert in compliance with the NIOSH Conflict or Bias policy.

[1] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

Hanford workers do have recorded nonpenetrating doses of record [see Buschbom and Gilbert 

(1993)], and this is included in this TBD as Attachment C.

[2] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This judgment is based on Mr. Fix’s experience in occupational dose reconstruction. 

[3] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The data used to prepare this figure were obtained from statistical tables included PNL-8909 

(Buschbom and Gilbert 1993) of the Hanford Health and Mortality Study worker cohort.

[4] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This judgment is based on the dose reconstruction recommendation presented in later 

sections of this TBD to assign, as appropriate based on claimant work activities, an annual 

neutron dose for each year of Hanford employment prior to the use of the TLD beginning in 

1972, using a distribution of the NP dose ratio. 

[5] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This judgment is based on Mr. Fix’s perspective on the historical development of personnel 

dosimetry systems and the performance studies conducted historically leading to the adoption 

of ANSI/HPS N13-11-1983 (HPS 1983).

[6] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This judgment is based on Mr. Fix’s experience in the preparation of Fix, Wilson and 

Baumgartner (1997b), during which a database of all Hanford NTA processing results from 

1950 through about 1961 was developed from the paper records obtained from the Federal 

Record Center.

[7] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The data for a single claimant were obtained from the DOE dose records for this person for 

employment at Hanford.

[8] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

Mr. Fix was the Hanford External Dosimetry Program Project Manager in 1995. The 

commercial Harshaw dosimetry systems became effective with the January 1, 1995, dosimeter 

issue to Hanford workers.

[9] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

Reference to the routine comparison of pocket ionization chamber PIC and film dosimeter 

results is based on judgment of the information in the Manual of Standard Procedures: 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 66 of 265

Personnel Meters (HEW 1946), Valentine (1965), and the respective routine organizational 

reports presented in Attachment D, Table D-2. 

[10] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The first computer system for radiological records was introduced in 1958 as described in 

Wilson (1987). Before this, it was necessary to record the assigned dose manually on forms. 

Fix, Carbaugh, and MacLellan (2001) enables a person to view the forms used. In addition, 

DOE provided historical dose forms that provide a means to view these forms for the 

respective years.

[11] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The methods used to record dose at Hanford are described in Fix, Carbaugh, and MacLellan 

(2001).

[12] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The precise period of accreditation of the Hanford External Dosimetry Program is a matter of 

record available from the DOELAP. The stated year of 1989 is based on Mr. Fix’s recollection 

as chair of the DOELAP Oversight Board. 

[13] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This statement is based on judgment by Mr. Fix on the challenge presented by mixed beta/ 

photon radiation fields and neutron radiation and on his experience in accurate measurements 

of these fields, his role on the DOELAP Oversight Board, and in the content of national 

dosimeter performance standards such as ANSI/HPS N13.11-1983 (ANSI HPS 1983).

[14] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The judgment presented is based on Mr. Fix’s assessment of the association of dosimeter 

error on dosimeter response and workplace radiation characteristics. For example, see 

Wilson et al. (1990).

[15] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The judgment of complex radiation fields in the workplace is based on consideration of the 

types of processes and radionuclides at Hanford. The 10-year review by Parker (1954) could 

be consulted for a description.

[16] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

These statements are based on judgment by Mr. Fix and require knowledge of the gamma 

energies associated with the radionuclides in Table 6-9. The prevalent 60Co (1.17 and 1.33 

MeV) and 137Cs (0.662 MeV) in several facilities are generally considered to be higher energy 

gamma radiation, whereas in Hanford plutonium facilities 241Am (59 KeV) is considered to be 

of low to intermediate energy and the 17-keV radiation (prevalent X-ray from plutonium) is 

considered to be low- energy.

[17] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This statement is supported in Nichols et al. (1972, pp. 3 and 7) and in Fix et al. (1981, 

Study 5).

[18] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The radiation dose fractions presented to segregate beta, photon, and neutron dose 

components into IREP input categories are based on judgment by Mr. Fix.

[19] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007.

The list of Hanford facilities with a potential for neutron exposure was developed from Hanford 
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 67 of 265

Site Profile Section 2 (ORAUT 2007c), experience with Hanford facilities, and historical 

documentation. The early reactor facility 305 should be included in the 300 Area list.

[20] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The data in Table 6-14 were obtained from Table II of Nichols et al et al. (1972).

[21] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This statement and the judgment identified in this table by Mr. Fix of the effects of angular 

response on recorded dose is based on Mr. Fix’s assessment of the complex interactions that 

involved dosimeter angular response and workplace radiation fields.

[22] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

Table 6-29 contains summaries of the neutron dose fractions for different facilities, the factor 

to transform the neutron dose of record to incorporate ICRP Publication 60 weighting factors 

(ICRP 1991), and the overall factor that can be used by the dose reconstructor. The process

is explained in OCAS-IG-001 (NIOSH 2007b) and in ORAUT-OTIB-0055 (ORAUT 2006a).

[23] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This represents the judgment of Mr. Fix and is substantially based on information in Fix, 

Wilson, and Baumgartner (1997b).

[24] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This statement is originally provided in Wilson (1960b, p. 1) on the potential missed dose for 

Hanford workers with dosimeters located simultaneously at several Hanford area dosimeter 

exchange gatehouses.

[25] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

This represents the judgment of Mr. Fix and is substantially based on information in Fix, 

Wilson, and Baumgartner (1997b) and explained in the succeeding sections.

[26] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The recommendation to use the claim-specific neutron-to-photon NP dose ratio if higher than 

the recommended default values is to ensure that the neutron dose of record for the claimant 

is not reduced.

[27] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The neutron-to-photon NP dose ratios are a summary of the values developed in the previous 

text.

[28] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The information in this section is based on the judgment of Mr. Fix recommending to the dose 

reconstructor, depending on the target tissue, consideration to assign an extremity dose in the 

event that monitoring for extremity dose is not performed and an extremity dose is not reported 

by DOE.

[29] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. December 2009. 

The statement that the operation of the PFP has discontinued as of December 2009 is based 

on judgment by Mr. Fix. 

[30] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

The statement about research and development in Hanford 300 facilities in preparation for 

operation of the 400 Area FFTF is based on judgment by Mr. Fix.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 68 of 265

[31] Fix, Jack J. Dade Moeller & Associates. Senior Health Physicist. March 2007. 

Appendix A tables summarize neutron spectral information from measurements described in 

the respective references. The 0.1- to 2-MeV category represents a substantial component in 

each workplace, and it alone could be used (i.e., assign 100%) as an analysis that is favorable 

to claimants.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 69 of 265

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GLOSSARY

absorbed dose, D

Amount of energy (ergs or joules) deposited in a substance by ionizing radiation per unit mass 

(grams or kilograms) of the substance and measured in units of rads or grays. See dose.

accreditation 

For external dosimetry, the assessment of whether or not a personnel dosimetry system meets 

specific criteria. The assessment includes dosimeter performance and the associated quality 

assurance and calibration programs. 

accuracy 

The characteristics of an analysis or determination that ensures that both the bias and 

precision of the resultant quantity will remain within the specified limits.

albedo dosimeter 

Thermoluminescent dosimeter that measures the thermal, intermediate, and fast neutrons 

scattered and moderated by the body or a phantom from an incident fast neutron flux.

algorithm 

Set of rules or steps for solving a problem, especially for calculating a value. 

alpha radiation 

Positively charged particle emitted from the nuclei of some radioactive elements. An alpha 

particle consists of two neutrons and two protons (a helium nucleus) and has an electrostatic 

charge of +2. 

boron trifluoride (BF3) chamber or counter 

Proportional counter using gaseous boron trifluoride (BF3) to detect slow neutrons from their 

interactions with boron.

backscatter 

Reflection or refraction of radiation at angles over 90 degrees from its original direction.

beta particle (β) 

See beta radiation.

beta radiation 

Charged particle emitted from some radioactive elements with a mass equal to 1/1,837 that of 

a proton. A negatively charged beta particle is identical to an electron. A positively charged 

beta particle is a positron.

Bonner Sphere

See multi-sphere neutron spectrometer.

calibration blank

Dosimeter not exposed to radiation. This dosimeter establishes the dosimetry system base 

line or zero dose value.

collective dose equivalent (CDE) 

Sum of the dose equivalents of all individuals in an exposed population in units of person-rem 

or person-sievert. See dose.
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curie (Ci) 

Traditional unit of radioactivity equal to 37 billion (3.7 × 1010) becquerels, which is 

approximately equal to the activity of 1 gram of pure 226Ra.

Cutie Pie (CP) 

Portable radiation survey meter with a pistol grip and a large cylindrical ionization chamber.

deep absorbed dose (Dd) 

Absorbed dose in units of rem or sievert at a depth of 1 centimeter (1,000 milligrams per 

square centimeter) . See dose.

deep dose equivalent (DDE, Hd, Hp(10)) 

Dose equivalent in units of rem or sievert for a 1-centimeter depth in tissue (1,000 milligrams 

per square centimeter). See dose.

densitometer 

Instrument that uses a photoelectric cell to measure the transition of light through developed 

X-ray film to determine the optical density.

density reading

See optical density.

DOE Laboratory Accreditation Program (DOELAP) 

Program for accreditation by DOE of DOE site personnel dosimetry and radiobioassay 

programs based on performance testing and the evaluation of associated quality assurance, 

records, and calibration programs. 

dose 

In general, the specific amount of energy from ionizing radiation that is absorbed per unit of 

mass. Effective and equivalent doses are in units of rem or sievert; other types of dose are in 

units of roentgens, rads, reps, or grays

dose equivalent (H, DE) 

In units of rem or sievert, product of absorbed dose in tissue multiplied by a weighting factor 

and sometimes by other modifying factors to account for the potential for a biological effect 

from the absorbed dose. See dose.

dose equivalent index

Historical measure for neutron source calibration defined by the International Commission on 

Radiation Units and Measurements as the sum of the maximum dose equivalents delivered 

within a sphere at any depth for the respective neutron energies even though the maximum 

dose occurred at different depths and discounting the outer 0.07-millimeter-thick shell. Also 

called unrestricted dose equivalent index.

dosimeter

Device that measures the quantity of received radiation, usually a holder with radiationabsorbing filters and radiation-sensitive inserts packaged to provide a record of absorbed dose 

received by an individual. See albedo dosimeter, film dosimeter, neutron film dosimeter, 

pocket ionization chamber, thermoluminescent dosimeter, and track-etch dosimeter.
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dosimetry system

System for assessment of received radiation dose. This includes the fabrication, assignment, 

and processing of external dosimeters, and/or the collection and analysis of bioassay samples, 

and the interpretation and documentation of the results. 

DuPont 552 film packet 

Film packet containing DuPont 502 sensitive film and DuPont 510 insensitive film.

DuPont 558 film packet 

Film packet containing DuPont 508 film with sensitive and insensitive emulsions on either side.

element 

One of the known chemical substances in which the atoms have the same number of protons. 

Elements cannot be broken down further without changing their chemical properties. 

Chemical symbols for the elements consist of either a single letter or a combination of letters, 

some of which descend from the Latin names [e.g., Au from aurum (gold), Fe from ferrum

(iron)]. This glossary indicates elements by their names. Specific isotopes appear as their 

standard chemical symbols with the number of protons and neutrons in the nucleus. For 

example, the isotope of uranium that contains 92 protons and 143 neutrons can appear as 

235U, U-235, or uranium-235 

error

Difference between the correct, true, or conventionally accepted value and the measured or 

estimated value. Sometimes used to mean estimated uncertainty. See accuracy and 

uncertainty. 

exchange period (frequency)

Period (weekly, biweekly, monthly, etc.) for routine exchange of dosimeters. Also called 

exchange frequency.

exposure

(1) In general, the act of being exposed to ionizing radiation. See acute exposure and chronic 

exposure. (2) Measure of the ionization produced by X- and gamma-ray photons in air in units 

of roentgens.

exposure-to-dose-equivalent conversion factor for photons (Cx)

Ratio of exposure in air to the dose equivalent at a specified depth in a material of specified 

geometry and composition. Cx factors are a function of photon energy, material geometry 

(e.g., sphere, slab, or torso), and material composition (e.g., tissue-equivalent plastic, soft 

tissue without trace elements, or soft tissue with trace elements). 

extremities 

The portion of the arm from and including the elbow through the fingertips and the portion of 

the leg from and including the knee and patella through the toes. 

fast neutron 

Neutron with energy equal to or greater than 10 kiloelectron-volts. This type of neutron causes 

fission in some isotopes (e.g., 238U, 239Pu). See intermediate neutron and slow neutron.

favorable to claimants

In relation to dose reconstruction for probability of causation analysis, having the property of 

ensuring that there is no underestimation of potential dose, which often means the assumption 
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of a value that indicates a higher dose than is likely to have actually occurred in the absence of 

more accurate information. See probability of causation.

field calibration

Dosimeter calibration based on radiation types, intensities, and energies in the work 

environment.

film

(1) In the context of external dosimetry, radiation-sensitive photographic film in a light-tight 

wrapping. See film dosimeter. (2) X-ray film.

film density

See optical density.

film dosimeter

Package of film for measurement of ionizing radiation exposure for personnel monitoring 

purposes. A film dosimeter can contain two or three films of different sensitivities, and it can 

contain one or more filters that shield parts of the film from certain types of radiation. When 

developed, the film has an image caused by radiation measurable with an optical 

densitometer. Also called film badge.

filter

Material used (1) in a dosimeter to adjust radiation response to provide an improved tissue 

equivalent or dose response and (2) in an X-ray machine to selectively absorb photons from 

the beam to reduce unnecessary exposure of individuals or to improve radiographic quality.

first collision dose 

Measure for neutron radiation that relates dose to neutron flux through a thin layer of tissue. A 

graph referred to as the first collision curve derives from the assumption that the probability of 

two or more interactions per neutron is negligible. Because the charged secondary radiation 

from fast neutrons is short range, the first collision dose in irradiated material is nearly the 

same as the absorbed dose.

free-field dose equivalent

Dose equivalent for neutron radiation in free space with no background from air and room 

scattering and no source asymmetry.

gamma radiation 

Electromagnetic radiation (photons) of short wavelength and high energy (10 kiloelectron-volts 

to 9 megaelectron-volts) that originates in atomic nuclei and accompanies many nuclear 

reactions (e.g., fission, radioactive decay, and neutron capture). Gamma photons are identical 

to X-ray photons of high energy; the difference is that X-rays do not originate in the nucleus. 

Geiger-Müller counter 

Most common radiation detection and measuring instrument, usually known simply as a 

Geiger counter, it is a gas-filled tube containing electrodes between which there is a voltage 

potential but no current flow. When ionizing radiation passes through, a short, intense pulse of 

current passes from one electrode to the other. The number of pulses per second (or counts 

per minute) indicates the rate of ionizing events in the tube. 
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glovebox

Enclosure with special rubber gloves through which an operator can handle radioactive or 

toxic material without risk of injury or contamination normally operated at a slightly reduced 

pressure so that air leakage, if any, is inward.

gray (Gy)

International System unit of absorbed radiation dose, which is the amount of energy from any 

type of ionizing radiation deposited in any medium; 1 Gy equals 1 joule per kilogram or 

100 rads.

helium-3 (3

He) spectrometer 

Instrument that measures neutron energy spectra based on neutron interactions with 3

He to 

produce a triton (particle with 2 protons and one neutron) and a proton, which are detected by 

a proportional counter.

induced radioactivity

Radioactivity produced in certain materials as a result of nuclear reactions particularly the 

capture of neutrons.

intermediate neutron 

Neutron with energy between 0.5 electron-volts and 10 kiloelectron-volts. See fast neutron

and slow neutron.

ionizing radiation

Radiation of high enough energy to remove an electron from a struck atom and leave behind a 

positively charged ion. High enough doses of ionizing radiation can cause cellular damage. 

Ionizing particles include alpha particles, beta particles, gamma rays, X-rays, neutrons, 

high-speed electrons, high-speed protons, photoelectrons, Compton electrons, 

positron/negatron pairs from photon radiation, and scattered nuclei from fast neutrons. See 

alpha radiation, beta radiation, gamma radiation, neutron radiation, photon radiation, and X-ray 

radiation.

isotope 

One of two or more atoms of a particular element that have the same number of protons 

(atomic number) but different numbers of neutrons in their nuclei (e.g., 234U, 235U, and 238U). 

Isotopes have very nearly the same chemical properties. See element.

kiloelectron-volt (keV) 

Unit of particle energy equal to 1,000 (1 × 103

) electron-volts.

limit of detection (LOD) 

Minimum level at which a particular device can detect and quantify exposure or radiation. Also 

called lower limit of detection and detection limit or level. 

luminescence

Emission of light from a material as a result of some excitation. See thermoluminescence.

Manhattan Engineer District (MED)

Subdivision of the U.S. Army Corps of Engineers that administered the World War II 

Manhattan Project to develop the first nuclear bomb. The word Manhattan was chosen to 

divert attention from the Project’s real purpose. The U.S. Atomic Energy Commission 

assumed control of MED facilities and activities in 1946.
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minimum recorded dose

Based on a policy decision, the minimum dose level that is routinely recorded. A closely 

related concept is the dose recording interval. Hanford has generally recorded minimum 

doses of 10 mrem and at intervals of 10 mrem (i.e., 10, 20, 30, etc.).

megaelectron-volt (MeV) 

Unit of particle energy equal to 1 million (1 × 106

) electron-volts. 

multiple-collision neutron dose 

Dose in relation to the neutron flux through tissue based on the assumption that two or more 

interactions per neutron occurs and results in greater energy deposition.

multi-sphere neutron spectrometer 

Spectrometer that consists of a series of neutron-moderating spheres of tissue-equivalent 

material with a neutron detector in the middle of the respective spheres. Algorithms are used 

to calculate the neutron spectra.

nuclear track emulsion, type A (NTA) 

Film sensitive to fast neutrons made by Eastman Kodak. The developed image has tracks 

caused by neutrons that are visible under oil immersion with about 1,000-power magnification.

neutron (n) 

Basic nucleic particle that is electrically neutral with mass slightly greater than that of a proton. 

There are neutrons in the nuclei of every atom heavier than normal hydrogen. See element.

neutron-to-photon dose ratio 

Ratio applied to the photon fraction to estimate the unmeasured neutron dose based on 

knowledge and measurements in a specified location.

neutron film dosimeter

Film dosimeter with a nuclear track emulsion, type A, film packet.

neutron radiation 

Radiation that consists of free neutrons unattached to other subatomic particles emitted from a 

decaying radionuclide. Neutron radiation can cause further fission in fissionable material such 

as the chain reactions in nuclear reactors, and nonradioactive nuclides can become 

radioactive by absorbing free neutrons. See neutron.

nonpenetrating dose (NP, NPEN)

Dose from beta and lower energy photon (X-ray and gamma) radiation which does not 

penetrate the skin. It is often determined from the open window dose minus the shielded 

window dose. See dose.

open window (OW) 

Area of a film dosimeter that has little to no radiation shielding (e.g., only a holder and visible 

light protection). See film dosimeter.

operating area

Designation of Hanford major operational work areas among the respective fuel fabrication 

(e.g., 300 Area), reactor operations (e.g., 100B, 100C, 100D, 100DR, 100F, 100H, 100KE, 

100KW, and 100N), chemical separations (e.g., U-, T-, B-, UO3, REDOX, and PUREX Plants), 

plutonium finishing (Z-Plant), research and development (e.g. 300 and 3000 Areas), and 

transportation, communication, and general site support (e.g., 600, 700, and 1100 Areas).
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optical density

Measure of the degree of opacity of photographic or radiographic film defined as OD = log10

(I0/I), the base-10 logarithm of the ratio of the reference light intensity I0 (without film) to the 

transmitted light intensity (through the film) Also called film density and density reading. 

pencil dosimeters

See pocket ionization chamber. 

penetrating dose (PEN) 

Dose from moderate to higher energy photons and neutrons that penetrates the outer layers of 

the skin. See dose.

plutonium tetrafluoride (PuF4) source 

Neutron source for dosimetry evaluation that duplicates the neutron energies in plutonium 

facilities. At Hanford it was used in the 200 Area Z-Plant (the Plutonium Finishing Plant).

personal dose equivalent [Hp(d)] 

Dose equivalent in units of rem or sievert in soft tissue below a specified point on the body at 

an appropriate depth d. The depths selected for personal dosimetry are 0.07 millimeters 

(7 milligrams per square centimeter) and 10 millimeters (1,000 milligrams per square 

centimeter), respectively, for the skin (shallow) and whole-body (deep) doses. These are 

noted as Hp(0.07) and Hp(10), respectively. The International Commission on Radiological 

Measurement and Units recommended Hp(d) in 1993 as dose quantity for radiological 

protection. 

photon

Quantum of electromagnetic energy generally regarded as a discrete particle having zero rest 

mass, no electric charge, and an indefinitely long lifetime. The entire range of electromagnetic 

radiation that extends in frequency from 1023 cycles per second (hertz) to 0 hertz. 

photon dose fraction

Fraction of the measured photon dose that is multiplied by the neutron-to-photon dose ratio to 

estimate the unmeasured neutron dose.

pocket ionization chamber (PIC) 

Cylindrical monitoring device commonly clipped to the outer clothing of an individual to 

measure ionizing radiation. A PIC can be self-reading or require the use of a outside device to 

be able to read the dosimeter. Also called pencil, pocket pencil, pencil dosimeter, and pocket 

dosimeter.

precision

Describes dispersion of measurements in relation to a measure of location or central 

tendency. 

probability of causation (POC, PC) 

For purposes of dose reconstruction for the Energy Employees Occupational Illness 

Compensation Act, the percent likelihood, at the 99th percentile, that a worker incurred a 

particular cancer from occupational exposure to radiation.

quality factor (Q, QF) 

Principal modifying factor (which depends on the collision stopping power for charged 

particles) that is employed to derive dose equivalent from absorbed dose. The quality factor 
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multiplied by the absorbed dose yields the dose equivalent. See dose, relative biological 

effectiveness, and weighting factor.

rad

Traditional unit for expressing absorbed radiation dose, which is the amount of energy from 

any type of ionizing radiation deposited in any medium. A dose of 1 rad is equivalent to the 

absorption of 100 ergs per gram (0.01 joules per kilogram) of absorbing tissue. The rad has 

been replaced by the gray in the International System of Units (100 rads = 1 gray). The word 

derives from radiation absorbed dose. 

radiation

Subatomic particles and electromagnetic rays (photons) with kinetic energy that interact with 

matter through various mechanisms that involve energy transfer.

radiation monitoring

Routine measurements and the estimation of the dose equivalent for the purpose of 

determining and controlling the dose received by workers.

radioactivity

Property possessed by some elements (e.g., uranium) or isotopes (e.g., 14C) of spontaneously 

emitting energetic particles (electrons or alpha particles) by the disintegration of their atomic 

nuclei. See radionuclide. 

random error 

When a given measurement is repeated and the values do not agree exactly. The causes of 

the disagreement between the values must also be the causes of their differences from the 

true value. See systematic error. 

relative biological effectiveness (RBE) 

Ratio of the absorbed dose of a reference radiation to the absorbed dose of a test radiation 

that produces the same biological effects, other conditions being equal. A factor applied to 

account for differences between the amount of cancer effect produced by different forms of 

radiation.

rem

Traditional unit of radiation dose equivalent that indicates the biological damage caused by 

radiation equivalent to that caused by 1 rad of high-penetration X-rays multiplied by a quality 

factor. The sievert is the International System unit; 1 rem equals 0.01 sievert. The word 

derives from roentgen equivalent in man; rem is also the plural.

roentgen (R) 

Unit of photon (gamma or X-ray) exposure for which the resultant ionization liberates a positive 

or negative charge equal to 2.58 × 10-4 coulombs per kilogram (or 1 electrostatic unit of 

electricity per cubic centimeter) of dry air at 0°C and standard atmospheric pressure. An 

exposure of 1 R is approximately equivalent to an absorbed dose of 1 rad in soft tissue for 

higher energy photons (generally greater than 100 kiloelectron-volts). 

scattering

Change in direction of radiation by refraction or reflection, often accompanied by a decrease in 

radiation due to absorption by the refracting or reflecting material.
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shallow absorbed dose (Ds)

Absorbed dose at a depth of 0.07 millimeters (7 milligrams per square centimeter) in a material 

of specified geometry and composition.

shallow dose equivalent [SDE, Hs, Hp(0.07)] 

Dose equivalent in units of rem or sievert at a depth of 0.07 millimeters (7 milligrams per 

square centimeter) in tissue equal to the sum of the penetrating and nonpenetrating doses.

shielding

Material or obstruction that absorbs ionizing radiation and tends to protect personnel or 

materials from its effects.

Sievert (Sv)

International System unit for dose equivalent, which indicates the biological damage caused 

by radiation. The unit is the radiation value in gray (equal to 1 joule per kilogram) multiplied by 

a weighting factor for the type of radiation and a weighting factor for the tissue; 1 Sv equals 

100 rem.

sigma pile

Device used to obtain thermal neutrons for calibration purposes.

silver shield(s)

Hanford term for 1-millimeter and 0.13-micrometer shields covering the film packet in the early 

Hanford personnel film dosimeters.

skin dose

See shallow dose equivalent.

slow neutron 

Neutrons with energy less than 1 electron-volt. See fast neutron and intermediate neutron.

Snoopy

Portable neutron monitoring instrument with a moderated BF3 detector. See boron trifluoride 

(BF3) chamber.

systematic error 

When a given measurement is repeated and the values differ from the true value by the same 

amount. See random error.

thermal neutron 

Neutron in thermal equilibrium with its surroundings having an average energy of 

0.025 electron-volt. 

thermoluminescence 

Property that causes a material to emit light as a result of heat.

thermoluminescent dosimeter (TLD)

Device for measuring radiation dose that consists of a holder containing solid chips of material 

that, when heated by radiation, release the stored energy as light. The measurement of this 

light provides a measurement of absorbed dose. 
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tissue equivalent

Substance with response to radiation equivalent to tissue. A tissue-equivalent response is an 

important consideration in the design and fabrication of radiation measuring instruments and 

dosimeters.

Tissue Equivalent Proportional Counter (TEPC)

Device that measures absorbed dose from neutron radiation in materials nearly equivalent to 

tissue. Analysis of the counter data determines the effective weighting factor and the dose 

equivalent for that radiation.

TLD chip

Small block or crystal of lithium fluoride in a thermoluminescent dosimeter. A TLD-600 

dosimeter contains a chip made from more than 95% 6

Li for neutron radiation detection, and a 

TLD-700 dosimeter contains a chip made from more than 99.9% 7

Li for photon and beta 

radiation detection. Also called crystals.

track-etch dosimeter (TED) 

Device for evaluation of fast neutron dose through examination of traces left by the neutrons 

on the Columbia Resin Number 39 emulsion.

U.S. Atomic Energy Commission (AEC) 

Federal agency created in 1946 to assume the responsibilities of the Manhattan Engineer 

District (nuclear weapons) and to manage the development, use, and control of nuclear energy 

for military and civilian applications. The U.S. Energy Research and Development 

Administration and the U.S. Nuclear Regulatory Commission assumed separate duties from 

the AEC in 1974. The U.S. Department of Energy succeeded the U.S. Energy Research and 

Development Administration in 1979.

uncertainty 

Standard deviation of the mean of a set of measurements. The standard error reduces to the 

standard deviation of the measurement when there is only one determination. See accuracy, 

confidence level, and error. Also called standard error. 

whole-body (WB) dose 

Dose to the entire body excluding the contents of the gastrointestinal tract, urinary bladder, 

and gall bladder and commonly defined as the absorbed dose at a tissue depth of 

10 millimeters (1,000 milligrams per square centimeter). Also called penetrating dose. 

See dose.

X-ray

See X-ray radiation. 

X-ray radiation 

Electromagnetic radiation (photons) produced by bombardment of atoms by accelerated 

particles. X-rays are produced by various mechanisms including bremsstrahlung and electron 

shell transitions within atoms (characteristic X-rays). Once formed, there is no difference 

between X-rays and gamma rays, but gamma photons originate inside the nucleus of an atom. 

Z-Plant

Hanford facility consisting of several buildings where plutonium is processed (also known as 

234-5-Z Building).
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TABLE OF CONTENTS

SECTION TITLE PAGE

A1. 100 Area Reactor Facilities ..................................................................................................100

A2. 200 and 300 Area Plutonium Facilities .................................................................................101

A3. Neutron Energy Spectra.......................................................................................................102

LIST OF TABLES

A-1 Laboratory-measured dose fractions from PuF4 ................................................................... 104

A-2 200 Area measured dose fractions....................................................................................... 105

A-3 300 Area measured dose fractions....................................................................................... 105

A-4 400 Area measured dose fractions....................................................................................... 105

LIST OF FIGURES

A-1 Neutron spectra for Hanford 400 Area FFTF........................................................................ 101

A-2 Degradation in neutron energy spectra for bare, 2.54 cm and 5.08 cm of 

acrylic plastic shielding with neutron energy groups overlay................................................. 103

A-3 Neutron energy spectra recorded at Hanford PFP 234-5Z ................................................... 103

A-4 Neutron spectra for Hanford 308 and 324 facilities............................................................... 104

Hanford researchers have made neutron spectra and dose measurements in several Hanford 

workplaces as early as the late 1940s using various methods to estimate the neutron spectra. 

Beginning in the 1960s approximately, more sophisticated methods to measure neutron spectra 

became available. The measured spectra in this attachment have been used to evaluate the 

selection of the IREP input energy category (shown in shaded colors on the graphs) for Hanford 

facilities. 

A1. 100 AREA REACTOR FACILITIES

Substantial reactor core neutron energy fluence measurements were routinely collected for the 

Hanford single-pass cooling production reactors. However, only a few relevant workplace neutron 

radiation spectra measurements for Hanford single-pass reactors that operated from 1945 (100 B) 

through 1971 (100 KE) have been located. The measurements of most interest are during reactor 

operation. Neutron spectrum measurements were made in the early 1980s at two locations at the 

FFTF in the 400 Area (Fix et al. 1982) as shown in Figure A-1.

The data in Figure A-1 might not be indicative of routine operations. At that time of the 

measurements, a stainless-steel research thimble in one of the bundle tubes allowed neutrons to 

stream from the core to the head compartment. The neutron spectrum was highly scattered, resulting 

in significantly lower neutron energies. Highly scattered neutron fields are likely characteristic of 

Hanford single-pass reactor workplace fields and this resulted in the relatively low NTA 

ATTACHMENT A

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Page 1 of 6
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1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E-07 1.E-06 1.E-05 1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02

Energy, meV

Dose Equivalent, rem

FFTF #1

FFTF #2

Figure A-1. Neutron spectra for Hanford 400 Area FFTF (Fix et al. 1982).

measurements. The HMPD used in these measurements showed an over-response of about a factor 

of 6 compared to the multisphere measurements because of the highly degraded neutron spectrum. 

Although indirectly applicable, measurements of neutron spectra and dose and personnel dosimeter 

performance in U.S. nuclear power reactors reported by Endres et al. (1981) concluded that NTA 

emulsions are not sensitive to the leakage spectra that might be present in commercial power reactor 

plants.

A2. 200 AND 300 AREA PLUTONIUM FACILITIES

Plutonium production at Hanford began January 16, 1945 (Marceau et al. 2002, Chapter 2, Section 4), 

in what is often called Z-Plant or the PFP 231-Z Plutonium Isolation Facility in the Hanford 200 Area. 

At that time, Hanford-produced plutonium nitrate was shipped to the Los Alamos National Laboratory 

for use in producing nuclear weapons. On July 5, 1949, the PFP 234-5Z facility provided the 

capability for Hanford to convert plutonium nitrate to metallic plutonium. The initial 234-5Z plutonium 

finishing equipment was termed the “Rubber Glove” line because it depended on personnel working 

with a series of 28 stainless-steel gloveboxes, 55 m long, to move the plutonium mixtures manually 

through the finishing process (Fix, Wilson, and Baumgartner 1997b). 

On March 18, 1952, a Remote Mechanical A (RMA) Line began operation. The RMA Line performed 

all the process steps in plutonium metal production and fabrication except Task 1 (feed makeup and 

purification), which continued in the 231-Z facility. The RMA Line was in six rooms at 234-5Z. In mid1957, the RMA Line was modified for a continuous calcination and hydrofluorination process that 

essentially handled the Task 1 activities previously done at 231-Z (i.e., all processing tasks). Many 

projects were undertaken at PFP 234-5Z from 1957 to 1961 to accommodate the significant increase 

in throughput. The most significant of these were the construction of the remotely operated series of 

gloveboxes (RMC) Button Line and the RMC Fabrication Line which still required substantial operator 

and maintenance personnel contact (Lini 2008). Both of these began operation in the mid-1960s. 

The RMC Line (button and fabrication components) consisted of a completely self-contained, remotely 

operated series of gloveboxes similar to the RMA Line areas (Fix, Wilson, and Baumgartner 1997b).

ATTACHMENT A

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Neutron dose is associated with the overall Hanford plutonium production process in which plutonium 

from the processing facilities was brought into PFP as a liquid nitrate solution. At the PFP, plutonium 

was precipitated as an oxalate, converted to a fluoride, and reacted at high temperature with metallic 

calcium, forming the metal (Ballinger and Hall 1991). Neutron radiation was particularly enhanced 

during the fluorination step in the process because of plutonium fluoride (PuF4) alpha neutron (α,n) 

reactions. As of December 2009, the Hanford 200 Area plutonium facility is no longer in operation

[29].

Research and development work with nuclear fuel was conducted in the Hanford 300 Area, 

particularly at the 308 Building PFPP, 309 Building PRTR, and in the 324 Building chemical and 

materials engineering hot cell laboratories. Pilot work was performed in the 300 Area facilities in 

preparation for the 400 Area FFTF construction and operation [30]. 

A3. NEUTRON ENERGY SPECTRA

PuF4 is the most significant source, historically, of neutron exposure to workers in the Hanford 200 

Area plutonium facilities. Figure A-2 shows measurements by Brackenbush, Baumgartner, and Fix 

(1991) of a PuF4 source with no shielding, 2.54 cm of acrylic plastic, and 5.08 cm of acrylic plastic 

shielding between the source and the detector system to illustrate the effect on the plutonium 

spectrum of increasing thicknesses of the acrylic in the glovebox sides. A PuF4 source was used to 

calibrate Hanford personnel dosimeters beginning in 1958 (Fix, Wilson, and Baumgartner 1997b). 

This figure shows that, although different neutron spectra were measured, similarities were observed 

in the general shape of the degraded PuF4 spectrum. The energy of the dose equivalent peak is 

centered at approximately 1 MeV. Similar plutonium source and acrylic shielding measurements were 

reported in Endres et al. (1996) in association with field evaluations of the Harshaw commercial TLD 

and TED system implemented on January 1, 1995. The results of these measurements led to the 

eventual elimination of the TED component in routine personnel monitoring because the TED 

substantially underestimated the neutron dose. This occurred because the TED did not respond to 

the substantial lower energy neutron spectrum from stored plutonium in the current Hanford PFP 

operation. There are many similarities between NTA film and TED characteristics, including physical 

size, direct neutron responding device, angular response, and a lower energy neutron response 

threshold. The TED has a significantly better energy threshold of about 100 keV compared to the 

NTA film threshold of about 700 keV, but showed unacceptable capabilities to measure neutron dose. 

Neutron radiation spectra measurements in Figure A-3 are documented in Fix et al. (1981, Study 4) 

and in Roberson, Cummings, and Fix (1985) at the PFP 234-5Z Building “C” Line, Room B, selected 

gloveboxes, and the 2736-Z plutonium vault. The 234-5Z locations are where plutonium nitrate was 

converted to plutonium fluoride with the associated high neutron flux rates. This location provided the 

highest neutron flux rates at Hanford. The original data were depicted as dose equivalent rates; 

however, for simplicity of calculation, a 1-hour exposure was assumed to use dose equivalent.

As noted in Roberson, Cummings, and Fix (1985), the HMPD was originally calibrated in neutron 

fields encountered in 234-5Z, and this calibration has been maintained over the years. Therefore, the 

estimate of personnel neutron dose equivalent has remained tied to the original measurements 

regardless of the neutron source used to calibrate the dosimeter. 

Neutron spectrum measurements were made in the early 1980s at research and development 

laboratories in the 300 Area (Fix et al. 1982). Figure A-4 shows measurements at selected locations 

including plutonium storage vaults in the 308 and 324 Buildings.

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Figure A-2. Degradation in neutron energy spectra for bare, 2.54 cm and 5.08 

cm of acrylic plastic shielding with neutron energy groups overlay

(Brackenbush, Baumgartner, and Fix 1991).

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E-07 1.E-06 1.E-05 1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02

Energy, MeV

Dose Equivalent, rem

234-5 Glove Box H-9A

234-5 Glove Box HC-9B

2736-Z Pu Vault

234-5, "C" Line

Figure A-3. Neutron energy spectra recorded at Hanford PFP 234-5Z ”C” line, 

glovebox, and plutonium storage vault (Fix et al. 1981, Study 4; Roberson, 

Cummings, and Fix 1985).

The highest neutron energy group (>20 MeV) was not used because operations at Hanford did not 

produce a significant component of neutrons of this energy. The dose for each neutron energy group 

was calculated by multiplying the neutron flux (Ø) provided in the references by Roberson, 

Cummings, and Fix (1985) and Brackenbush, Baumgartner, and Fix (1991) by the corresponding fluxto-dose-rate conversion factors (DCF) found in NCRP Report 38 (NCRP 1971). The neutron doses in 

each NCRP 38 energy interval are summed to develop the four neutron group doses. The dose 

fraction (Df) for each neutron energy group (n) was calculated by dividing the neutron group dose by 

the total dose (DT) using equation A-1.

PuF4 Spectra Degradiation

1.00E-07

1.00E-06

1.00E-05

1.00E-04

1.00E-03

1.00E-02

1.00E-01

1.00E+00

1.E-07 1.E-06 1.E-05 1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02

Energy, MeV

Dose Equivalent, rem

Bare PuF4

2.54 cm Acrylic Shielding

5.08 cm Acrylic Shielding

PuF4 Spectra Degradation

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1.E-08

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-07 1.E-06 1.E-05 1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02

Energy, MeV

Dose Equivalent, rem

Bare Fuel Subassembly

Above Fuel Storage Pit

Pu Storage Vault

324 Pu Vault

Figure A-4. Neutron spectra for Hanford 308 and 324 facilities (Fix et al. 1982).

T

i

i i

f n D

E DCF

D E

∑

=

( )

( )

φ

(A-1)

where:

Ø(Ei) = Neutron flux of the ith energy bin;

DCFi = NCRP Report 38 flux-to-dose-rate conversion factor for the ith energy bin (NCRP 

1971);

DT = Total dose.

Table A-1 lists the neutron dose fractions by energy group using data measured by Roberson, 

Cummings, and Fix (1985).

Table A-1. Laboratory-measured dose fractions from PuF4.

Neutron energy 

group

Shielding of PuF4 sourcea

0 cm (bare) 2.54 cm 5.08 cm

<10 keV 0.00 0.00 0.01

10–100 keV 0.00 0.00 0.00

0.1–2 MeV 0.06 0.85 0.89

2–20 MeV 0.94 0.15 0.10

Favorable-to-claimant dose fractions

0.1–2 MeV 0.1 0.9 0.9

2–20 MeV 0.9 0.1 0.1

a. Thickness of acrylic shielding between source and detector.

Table A-2 lists selected neutron dose fractions by energy group using the measured neutron spectra 

or 200 Area PFP vault and glovebox locations presented in Fix et al. (1981) and Roberson, 

Cummings, and Fix (1985). The estimated default dose fractions for these PFP locations are similar 

to the 2.54- and 5.08-cm acrylic plastic shielded spectra shown in Figure A-2.

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Table A-2. 200 Area measured dose fractions.

Energy 

group

Glovebox 

H-9B

Glovebox 

HC-9B

2736Z 

Vault

234-5Z C 

Room B

<10 keV 0.03 0.02 0.05 0.02

10–100 keV 0.04 0.04 0.04 0.03

0.1–2 MeV 0.84 0.87 0.80 0.88

2–20 MeV 0.09 0.07 0.11 0.07

Favorable-to-claimant dose fraction default values

0.1–2 MeV 0.9 0.9 0.9 0.9

2–20 MeV 0.1 0.1 0.1 0.1

Table A-3 lists selected neutron dose fractions by energy group using the measured neutron spectra 

for 300 Area locations presented in Fix et al. (1982).

Table A-3. 300 Area measured dose fractions.

Energy 

group

308–Bare fuel 

subassembly

308–Above fuel 

storage pit

308–Pu 

storage vault

324 Pu 

vault

<10 keV 0.00 0.02 0.01 0.02

10–100 keV 0.00 0.04 0.03 0.03

0.1–2 MeV 0.64 0.73 0.75 0.88

2–20 MeV 0.36 0.21 0.21 0.07

Favorable-to-claimant dose fraction default values

0.1–2 MeV 0.6 0.8 0.8 0.9

2–20 MeV 0.4 0.2 0.2 0.1

Table A-4 lists selected neutron dose fractions by energy group using the measured neutron spectra 

for 400 Area FFTF locations presented in Fix et al. (1982). As reported in Fix et al. (1982), these 

measurements were taken at a time when a stainless steel research thimble was in one of the tubes 

and allowed neutrons to stream from the core to the head compartment. This is not a usual operating 

mode. Even with the streaming, the spectra show significantly reduced energy because of scatter.

Table A-4. 400 Area measured dose fractions.

Energy group FFTF #1 FFTF #2

<10 keV 0.4 0.3

10–100 keV 0.5 0.4

0.1–2 MeV 0.1 0.3

2–20 MeV 0.0 0.0

Favorable-to-claimant dose fraction default values

10–100 keV 0.5 0.5

0.1–2 MeV 0.5 0.5

The Radiation Effectiveness Factors used in the IREP to calculate the POC are less for the 10-to-100-

keV category compared to the primary fission spectrum energy group (0.1 to 2 MeV) (Kocher, 

Apostoaei, and Hoffman 2005). Combining neutron energy groups into the primary 0.1-to-2-MeV 

fission spectrum group is a reasonable and favorable-to-claimant simplification of the dose 

calculation. The tables described above include the neutron energy favorable-to-claimant default 

values [31].

ATTACHMENT A

WORKPLACE NEUTRON SPECTRA MEASUREMENTS 

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TABLE OF CONTENTS

SECTION TITLE PAGE

B1. Purpose ...............................................................................................................................106

B2. Background..........................................................................................................................106

B3. Applications And Limitations ...............................................................................................107

B4. Hanford Coworker Data Development..................................................................................108

B5. Hanford Coworker Annual Dose Summaries........................................................................ 109

B6. Penetrating Dose Values Based on ORAUT-OTIB-0052 Guidance for 

Selected Construction Trade Workers..................................................................................111

LIST OF TABLES

B-1 Missed external doses based on the main body of this TBD and ORAUTOTIB-0017 ........................................................................................................................... 109

B-2 Annual Hanford external coworker doses modified to account for missed 

dose..................................................................................................................................... 111

B-3 Annual Hanford external penetrating coworker doses modified in 

accordance with ORAUT-OTIB-0052 ................................................................................... 112

B1. PURPOSE

The purpose of this attachment is to provide information to allow ORAU Team dose reconstructors to 

assign doses to workers at the Hanford Site who have no or limited monitoring data, based on site 

coworker data. The data in this attachment are to be used in conjunction with ORAUT-OTIB-0020, 

Use of Coworker Dosimetry Data for External Dose Assignment (ORAUT 2008a). 

B2. BACKGROUND

An analysis of external coworker dose was performed to permit dose reconstructors to complete 

certain cases for which external monitoring data are unavailable or incomplete Cases not having 

complete monitoring data can fall into one of several categories, including:

• The worker was unmonitored and, even by today’s standards, did not need to be monitored 

(e.g., a nonradiological worker).

• The worker was unmonitored, but by today’s standards would have been monitored.

• The worker might have been monitored but the data are not available to the dose 

reconstructor.

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• The worker might have partial information, but the available information is insufficient to permit 

a dose reconstruction to occur.

As described in ORAUT-OTIB-0020, some cases not having complete monitoring data can be 

processed based on assumptions and methodologies that do not involve coworker data (ORAUT 

2008a). For example, many cases falling in the first category above can be processed by assigning 

ambient external and internal doses based on information in the relevant site TBDs.

As described in the body of this TBD, Hanford began operations in 1944 using in-house dosimeter 

and processing technical support. Routine Hanford practices appear to have required assigning 

dosimeters to all workers who entered a controlled radiation area. The trends in the number of 

workers who were monitored, the number of monitored workers with positive recorded dose, and the 

collective dose do not show any abrupt changes that might be indicative of significant changes in 

photon dosimetry or assignment of dosimeters. Additionally, there does not appear to be any 

significant administrative practice that would jeopardize the integrity of the recorded dose of record.

B3. APPLICATIONS AND LIMITATIONS

1. Some Hanford Site workers might have worked at one or more other major sites within the 

DOE complex during their employment history. The data presented in this attachment are 

specific to Hanford. Assignment of unmonitored external doses from multiple site employment 

typically requires the availability of External Coworker Dosimetry Data TIBs for all relevant 

sites. The Hanford Site worker recorded annual doses do include all measured dose for 

“rover” workers working at more than one Hanford operational area.

2. Recorded non-penetrating (skin) doses for workers in Hanford Bldg 313-314 fuel fabrication 

facilities are under-estimated for employment prior to October 1944 when implementation of 

the Hanford film dosimetry program occurred (Wilson 1987). The Hanford PIC was used 

during 1944 but was incapable of accurate measurement of the non-penetrating beta dose. 

3. Summary statistics based on Hanford dosimetry data presented in this attachment do not 

extend beyond 1989 because data beyond 1989 were not available from the Comprehensive 

Epidemiologic Data Resource (CEDR). However, the absence of these data (and the 

subsequent development of dose distributions) should not interfere with the processing of 

most Hanford cases having a lack of external dosimetry data because well before 1989 the 

monitoring and reporting practices at the site ensured that essentially all workers with a 

potential for external radiation exposure were monitored and the results are readily accessible. 

4. The data presented in this attachment address penetrating radiation from gamma radiation 

and nonpenetrating radiation from beta radiation (or low-energy photons for work involving 

plutonium and/or chemical processing and waste operations). Neutron data are not 

presented. However, the locations on the Hanford Site at which neutron exposures were 

possible are limited to certain site areas and facilities, and the main body of this document 

establishes a method for assigning neutron doses when relevant. Therefore, the main body 

should be used as the basis for assigning neutron doses, when relevant, in addition to the 

photon and/or beta doses assigned in accordance with this attachment.

5. For the years 1972 and later, external onsite ambient doses should not be included in addition 

to the coworker doses assigned in accordance with this attachment, because any such doses 

ATTACHMENT B

HANFORD COWORKER DOSE ASSIGNMENT 

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HANFORD COWORKER DOSE ASSIGNMENT 

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would have been included in the dosimetry results reported by the site that were used as the 

basis for the coworker dose distributions presented below. Prior to 1972, coworker doses 

assigned in accordance with this attachment must be supplemented by the appropriate 

external onsite ambient dose in accordance with the instructions in ORAUT-PROC-0060 

(ORAUT 2006c).

B4. HANFORD COWORKER DATA DEVELOPMENT

Dosimetry data for monitored Hanford workers from the CEDR databases maintained by DOE were 

selected for this evaluation. The CEDR data evaluated represented primarily annual penetrating and 

nonpenetrating dosimetry data provided by the Hanford Site, which pertain to the shielded and “openwindow minus shielded” dosimetry readings, respectively, and exclude neutron doses. Starting in 

1982, multiple badge readings are recorded in CEDR for some Hanford workers; however, this was a 

relatively small fraction of the total, and the adjustments made for partial years of employment (see 

Section 7) are likely to account for any data that do not encompass a full year. In addition, starting in 

1983 the CEDR data included the reported shallow dose, not the nonpenetrating dose. Thus, for 

these years, the nonpenetrating doses were derived by subtracting the reported penetrating doses 

from the reported shallow doses.

Between 1957 and 1971, the Hanford Site film dosimeter included a third measurement (in addition to 

the standard shielded and open-window measurement) using a special filter covering a portion of the 

film designed to allow the assessment of X-ray doses. Thus, doses in this period were reported as 

beta, gamma, and X-ray. A fraction (0.65) of the X-ray dose was assumed to contribute to 

nonpenetrating dose, and the remainder (0.35) was assumed to contribute to penetrating dose. 

Because the CEDR data include the X-ray doses reported by the site for this period, the coworker 

dose evaluations described in this TIB include an upward adjustment of the reported beta and gamma 

doses during this period by adding 65% and 35% of the reported X-ray doses, respectively, to arrive 

at the reported nonpenetrating and penetrating doses.

The validity of the CEDR data was confirmed by selecting a sampling of claimant dosimetry data 

submitted by the site as part of the EEOICPA Subtitle B program and comparing it to the pertinent 

CEDR data. A review of annual data for 10 claimants covering 297 worker-years of employment at 

Hanford indicated excellent agreement between the two data sets. Specifically, the reported 

penetrating and nonpenetrating data in the CEDR database were found to correspond to the reported 

external and “skin minus external” annual doses reported in the site Radiological Exposure System. It 

is concluded that the CEDR data are acceptable for the development of coworker doses for the 

Hanford Site, with adjustments made for the reported X-ray doses as appropriate, as described 

above.

Adjustment for Missed Dose

According to the External Dose Reconstruction Implementation Guideline (NIOSH 2007b), missed 

doses are to be assigned for dosimeter readings <LOD to account for the possibility that doses were 

received but not recorded by the dosimeter or reported by the site. Annual missed doses are 

calculated by multiplying the number of <LOD dosimeter readings by the dosimeter LOD and 

summing the results. These values are used as the 95th percentile of a lognormal distribution for the 

purpose of calculating probability of causation; thus, in IREP the calculated annual missed doses are 

multiplied by 0.5 and entered in Parameter 1, and a value of 1.52 is entered in Parameter 2, to 

represent the geometric mean and GSD, respectively.

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The assignment of missed doses for monitored workers is particularly significant for Hanford 

claimants prior to 1951 when workers were monitored weekly, and between 1951 and 1957 when 

workers were monitored biweekly. Table B-1 lists the maximum annual missed dose by era and type 

of radiation (penetrating gamma and nonpenetrating) based on information for film and 

thermoluminescent dosimeters presented in the main body and Attachment C, Section C.1(B). 

Measured doses using PICs during 1943 and 1944 was not included in this analysis.

Special Considerations

Certain aspects of the external dosimetry practices at the Hanford Site documented in the TBD2 were 

considered in the analysis of the site data. These include:

• In some cases, values less than the dosimeter LOD were reported by the site. For example, 

values as low as 10 or 20 mR were reported even though the penetrating LOD was considered 

to be 40 mrem (or 40 mR) prior to 1972.

Table B-1. Missed external doses based on the main body of this TBD and ORAUT-OTIB-0017

(ORAUT 2005c).

Period

Penetrating 

LOD (rem)

Non-penetrating 

LOD (rem)a Exchange frequency

Maximum annual missed dose (rem)

Penetrating Nonpenetrating

1944a–1950 0.04 0.05 Weekly 2.080 2.600

1951–1956 0.04 0.05 Biweekly 1.040 1.300

1957 0.04 0.05 Variedb 0.720 0.900

1958–1971 0.04 0.05 Monthly 0.480 0.600

1972–1994 0.02 0.03 Monthlyc 0.240 0.360

1994–present 0.01 0.05 Monthlyc 0.120 0.600

a. Hanford instituted a routine weekly exchange and the use of film dosimeters in October 1944.

b. The exchange frequency was biweekly through May 1957, then monthly. A total of 18 exchanges were assumed for the 

year.

c. The TBD indicates that either monthly or quarterly exchange frequencies were used. Monthly exchanges have been 

assumed here to ensure favorability to the claimant.

• The data available to analyze coworker doses represent annual dose summaries for individual 

workers. Because these data include partial work years, the average annual doses reported 

tend to underestimate the average annual doses received by employees who worked an entire 

year.

As described in Section B.5 below, a favorable-to-claimant approach was adopted in the development 

of coworker dose summaries, and this approach should account for any underestimate of doses to 

radiological workers at the Hanford Site based on the considerations described above.

B5. HANFORD COWORKER ANNUAL DOSE SUMMARIES

Based on the information and approaches described above, Hanford coworker annual external 

dosimetry summaries were developed for use in the evaluation of external dose for certain claimants 

potentially exposed to workplace radiation, but with no or limited monitoring data provided by DOE. 

These summaries were developed using the following steps:

1. As described in Section B.4 above, the penetrating and nonpenetrating doses available from 

CEDR, which represented annual summary data, were modified to account for partial years of 

employment. This adjustment was made by analyzing the NIOSH-OCAS Claims Tracking System 

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HANFORD COWORKER DOSE ASSIGNMENT 

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(NOCTS) employment data for Hanford workers and adjusting the reported doses upward by an 

appropriate multiplier corresponding to the average fraction of a year an employee worked at the 

site. For example, if in a particular calendar year the average employment period for all Hanford 

employees in NOCTS was 11 months, the CEDR annual doses were multiplied by 12/11, or 1.09. 

This permits the dose reconstructor to assign an appropriate prorated dose to account for partial 

years of employment or potential exposure. A factor of 4 was applied for the year 1944 when 

monitoring at the site did not begin until October.

2. For the years 1957 through 1971, when X-ray doses were reported separately in addition to the 

reported gamma and beta doses, but were not included in the reported annual penetrating and 

nonpenetrating doses, the penetrating and nonpenetrating doses were modified by adding 35% 

and 65% of the reported positive X-ray doses, respectively (main text; ORAUT 2005c).

3. The 50th-, 95th-, and 99th-percentile annual penetrating and nonpenetrating doses were derived 

for two scenarios: excluding and including reported zeroes.

4. The 50th-, 95th-, and 99th-percentile doses based on the exclusion of zeroes were used as the 

basis for the coworker data set, because these are representative of radiological worker doses 

which are the principal focus of the coworker studies. However, to ensure favorability to the 

claimant, for penetrating radiation the percentile doses with zero results included were evaluated, 

and if the addition of one-half of the maximum annual nonpenetrating missed doses (listed in 

Table B-1) to these percentile doses resulted in values exceeding the percentile doses based on 

the exclusion of zeroes, the latter were replaced with the former. Missed doses were not added to 

both the penetrating and nonpenetrating results because the nonpenetrating results reported by 

the site reflect the difference between the open-window and shielded measurements, and 

assigning missed dose to both measurements would result in a double counting because a 

positive shielded measurement exceeding the nonpenetrating minimum detection level (MDL) 

would appear as a positive open-window measurement. To ensure favorability to the claimant, the 

nonpenetrating MDLs were assigned in the calculations (because they exceed the penetrating 

MDLs), and the values were apportioned to the penetrating doses (because penetrating doses are 

assigned as gamma radiation, which in IREP cannot have a negative effect because the radiation 

effectiveness factors for gammas are equal to or greater than for >15-keV electrons).

5. The results are presented in Table B-2 below. These percentile doses should be used for 

selected Hanford workers with no or limited monitoring data using the methodologies outlined in 

Section 7.0 of ORAUT-OTIB-0020 (ORAUT 2008a).

Doses to organs impacted only by penetrating radiation (e.g., organs other than the skin, breast and 

testes) are calculated based only on the “Gamma” columns in Table B-2 combined with the 

appropriate organ DCFs (NIOSH 2007b). Doses to the skin, breast and testes (and any other cancer 

location potentially impacted by nonpenetrating radiation) are determined based on both the “Gamma” 

and “Non-penetrating” columns; gamma doses are assigned as photons with an energy range 

consistent with information in this document, and nonpenetrating doses are assigned as electrons >15 

keV with corrections applied to account for clothing attenuation or other applicable considerations, or 

photons <30 keV, depending on the employment location and job description.

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HANFORD COWORKER DOSE ASSIGNMENT 

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B6. PENETRATING DOSE VALUES BASED ON ORAUT-OTIB-0052 GUIDANCE FOR 

SELECTED CONSTRUCTION TRADE WORKERS

Table B-3 contains penetrating dose values that have been adjusted using the guidance given in 

Section 8.0 of ORAUT-OTIB-0052, Parameters to Consider When Processing Claims for Construction 

Trade Workers (ORAUT 2007b) This guidance is applicable for construction trade workers who meet 

the criteria given in Section 3.0 of ORAUT-OTIB-0052.

Table B-2. Annual Hanford external coworker doses modified to 

account for missed dose (rem).

Year

Gamma

99th%

Gamma

95th%

Gamma

50th%

Nonpen

99th%

Nonpen

95th%

Nonpen

50th%

1944 3.096 2.176 1.300 3.363 1.448 0.240

1945 3.294 2.430 1.336 4.215 0.631 0.071

1946 2.917 2.125 1.448 5.944 1.421 0.297

1947 2.113 1.708 1.369 3.130 1.081 0.222

1948 1.805 1.541 1.334 5.400 1.096 0.149

1949 1.818 1.572 1.357 3.895 1.076 0.215

1950 2.107 1.721 1.357 3.222 1.535 0.239

1951 2.263 1.278 0.685 4.276 2.047 0.212

1952 2.504 1.541 0.721 2.782 1.046 0.155

1953 2.691 1.815 0.779 2.828 1.477 0.188

1954 3.053 1.863 0.720 2.438 1.260 0.175

1955 3.246 2.059 0.717 2.230 1.287 0.200

1956 3.344 2.306 0.682 2.262 1.189 0.141

1957 3.325 2.318 0.650 1.755 0.942 0.119

1958 3.236 2.599 0.321 1.326 0.695 0.074

1959 2.867 2.237 0.300 2.120 1.122 0.127

1960 3.276 2.756 0.311 2.622 1.419 0.162

1961 3.293 2.877 0.364 1.938 1.001 0.075

1962 3.406 3.018 0.452 1.695 0.805 0.108

1963 3.389 2.981 0.406 1.715 0.760 0.050

1964 3.437 3.018 0.505 1.954 0.690 0.042

1965 4.849 3.880 0.881 2.338 0.905 0.098

1966 3.574 2.690 0.524 1.881 0.841 0.056

1967 4.118 3.179 0.385 3.161 1.476 0.073

1968 3.473 2.801 0.436 2.253 0.890 0.084

1969 3.529 2.905 0.354 2.147 0.923 0.075

1970 3.689 3.159 0.323 2.623 1.267 0.092

1971 3.776 2.726 0.394 2.978 1.237 0.165

1972 3.458 2.339 0.293 1.060 0.565 0.090

1973 3.380 2.142 0.246 1.729 0.535 0.055

1974 3.473 2.099 0.283 1.253 0.513 0.068

1975 3.337 1.933 0.283 1.201 0.549 0.080

1976 3.091 1.667 0.226 0.741 0.359 0.069

1977 3.748 2.188 0.206 1.026 0.365 0.052

1978 2.934 1.252 0.214 0.530 0.237 0.034

1979 2.967 1.257 0.202 0.662 0.276 0.044

1980 2.658 0.968 0.203 0.551 0.293 0.045

1981 2.596 1.103 0.191 0.620 0.425 0.092

1982 2.980 1.432 0.191 0.533 0.329 0.057

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Year

Gamma

99th%

Gamma

95th%

Gamma

50th%

Nonpen

99th%

Nonpen

95th%

Nonpen

50th%

1983 3.081 1.933 0.180 0.603 0.261 0.045

1984 2.785 1.643 0.191 0.723 0.321 0.034

1985 2.911 1.849 0.180 0.834 0.297 0.034

1986 2.851 1.985 0.180 0.714 0.312 0.022

1987 2.260 1.048 0.195 0.403 0.135 0.015

1988 0.360 0.236 0.180 0.101 0.045 0.011

1989 0.508 0.236 0.180 0.124 0.034 0.011

Table B-3. Annual Hanford external penetrating coworker 

doses (rem) modified in accordance with ORAUT-OTIB0052 (ORAUT 2007b). 

Year Gamma 99th % Gamma 95th % Gamma 50th %

1944 3.814 2.526 1.300

1945 4.092 2.882 1.350

1946 3.564 2.455 1.508

1947 2.439 1.871 1.397

1948 2.007 1.637 1.348

1949 2.025 1.681 1.379

1950 2.430 1.889 1.380

1951 2.909 1.529 0.699

1952 3.246 1.898 0.750

1953 3.507 2.281 0.831

1954 4.014 2.348 0.748

1955 4.284 2.622 0.743

1956 4.421 3.076 0.695

1957 4.395 3.245 0.650

1958 4.411 3.639 0.329

1959 3.900 3.132 0.310

1960 4.466 3.859 0.315

1961 4.490 3.907 0.389

1962 4.649 4.106 0.512

1963 4.625 4.054 0.449

1964 4.692 4.106 0.588

1965 6.669 5.312 1.114

1966 4.883 3.645 0.614

1967 5.645 4.381 0.420

1968 4.742 3.801 0.491

1969 4.820 4.068 0.375

1970 5.081 4.422 0.332

1971 5.166 3.817 0.432

1972 4.770 3.269 0.338

1973 4.661 2.964 0.273

1974 4.790 2.939 0.324

1975 4.600 2.706 0.324

1976 4.327 2.334 0.245

1977 5.177 3.063 0.216

1978 4.108 1.753 0.227

1979 4.154 1.760 0.211

1980 3.649 1.355 0.212

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Year Gamma 99th % Gamma 95th % Gamma 50th %

1981 3.634 1.544 0.196

1982 4.172 2.005 0.196

1983 4.313 2.706 0.180

1984 3.899 2.300 0.196

1985 4.075 2.589 0.180

1986 3.991 2.780 0.180

1987 3.165 1.467 0.201

1988 0.456 0.259 0.180

1989 0.712 0.283 0.180

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TABLE OF CONTENTS

SECTION TITLE PAGE

C1. General Information .............................................................................................................114

C2. Procedure ............................................................................................................................115

LIST OF TABLES

C-1 Examples of skin dose assignments for Hanford badge readings in 1980 ............................ 117

C-2 Examples of skin dose assignments for Hanford badge readings in 1970 ............................ 117

The guidance in this attachment is currently contained in Appendix C of ORAUT-OTIB-0017, 

Interpretation of Dosimetry Data for Assignment of Shallow Dose (ORAUT 2005c), which will be 

withdrawn at an appropriate time.

C1. GENERAL INFORMATION

A. In the film badge era, the OW reading exhibits a significant over-response to low-energy photons; 

however, starting in April 1957, an additional dosimeter element was included in the badge design 

to facilitate an accurate measurement of X-ray dose. Therefore, prior to April 1957, measured 

doses assigned as <30-keV photons should be multiplied by 0.6 only if evidence exists indicating 

that the recorded doses were not adjusted downward by the site to account for the over-response.

B. Missed doses should be calculated based on the following LODs:

• 1944–1971: 50 mrem for nonpenetrating (OW), 40 mrem for penetrating (S)

• 1972–1994: 30 mrem for nonpenetrating, 20 mrem for penetrating

• 1995–present: 50 mrem for nonpenetrating, 10 mrem for penetrating

C. Hanford used a variety of dosimetry types and reporting schemes during its history. The dose 

reconstructor must ensure that the nonpenetrating and penetrating doses have been adequately 

interpreted from the data reported. For example, when beta and gamma doses are reported by 

the site, these typically represent the nonpenetrating and penetrating doses, respectively, and 

collectively represent the total skin dose. However, when the data are reported as open-window 

and shielded, the open-window measurement represents the total skin dose and the shielded 

measurement represents only the penetrating component.

D. Hanford used a variety of measurement techniques and reporting schemes for neutron dose. 

These doses might or might not have been included in the reported skin (or shallow) or WB (or 

deep) doses. As is the case for reconstructing doses for organs not impacted by nonpenetrating 

radiation, the calculation of dose to the skin requires that any neutron doses have been separated 

from the reported dose quantities and treated separately in IREP.

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E. As described in the Hanford Occupational Environmental Dose TBD (ORAUT 2007d), workers 

from the mid-1940s to the mid-1950s might have been exposed to radioactive particles emitted 

from facility stacks.

C2. PROCEDURE

Measured Dose

1944–March 1957

1. Determine the nonpenetrating dose by subtracting the reported S reading from the reported 

OW reading.

2. Assign the nonpenetrating dose as either electrons >15 keV (corrected for attenuation, if 

applicable), or photons <30 keV if the employee worked primarily with or near plutonium, such 

as in PFP. In the latter case, a correction factor of 0.6 should be applied to account for film 

over-response, if a correction by the site is not evident in the claim records as described above

and in TBD Section 6.4.

3. Assign the penetrating photon dose as photons, partitioned by energy according to the 

Hanford TBD.

4. Assign the reported neutron dose (if applicable) partitioned by energy and corrected for 

neutron quality according to the TBD (using an organ DCF of 1).

April 1957–1971

5. Assign the nonpenetrating dose as the reported beta dose (assigned as >15-keV electrons, 

which should be corrected for attenuation, if applicable) and 65% of the reported X-ray dose 

(assigned as <30-keV photons). Note: If the employee worked primarily with or near 

plutonium, such as in PFP, the reported beta dose should normally be zero during this era 

because the nonpenetrating component should have been identified as X-rays by the 

algorithm; however, in instances in which a positive beta dose was reported, as a favorable-toclaimant measure the dose should be considered <30-keV photons.

6. Assign the penetrating dose as the reported gamma dose (assigned as photons, partitioned by 

energy according to the Hanford TBD) and 35% of the reported X-ray dose (assigned as 30- to 

250-keV photons).

7. Assign the reported neutron dose (if applicable) partitioned by energy and corrected for 

neutron quality according to the TBD (using an organ DCF of 1).

1972–1994

8. Determine the nonpenetrating dose by subtracting the reported penetrating reading (typically 

reported as deep or whole body) from the reported nonpenetrating reading (typically reported 

as shallow or skin).

9. Assign the nonpenetrating dose as either electrons >15 keV (corrected for attenuation, if 

applicable), or photons <30 keV if the employee worked primarily with or near plutonium, such 

as in PFP.

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10. Assign the penetrating photon dose as photons, partitioned by energy according to the 

Hanford TBD.

11. Assign the reported neutron dose (if applicable) partitioned by energy and corrected for 

neutron quality according to the TBD (using an organ DCF of 1).

1995–Present

12. Determine the nonpenetrating dose by subtracting the reported deep photon reading from the 

reported shallow reading.

13. Assign the nonpenetrating dose as either electrons >15 keV (corrected for attenuation, if 

applicable), or photons <30 keV if the employee worked primarily with or near plutonium, such 

as in PFP.

14. Assign the penetrating photon dose as photons, partitioned by energy according to the 

Hanford TBD.

15. Assign the reported neutron dose (if applicable) partitioned by energy and corrected for 

neutron quality according to the TBD (using an organ DCF of 1).

Missed Dose

16. For any badge cycle with a zero result in any of the element readings, assign a single missed 

dose.

17. If only the OW (or beta, or nonpenetrating) reading was reported as zero, the missed dose 

assigned should be the appropriate nonpenetrating LOD for that era (divided by 2, treated as 

lognormal) and considered electrons (corrected for attenuation, if applicable) or low-energy 

photons (multiplied by 0.6 prior to 1957). For the period 1957 to 1971, when X-ray doses were 

reported separately, a nonzero value reported for X-rays indicates that the missed dose should 

be considered electrons, and a zero value reported for X-rays indicates that the missed dose 

should be considered 30- to 250-keV photons.

18. If only the S (or gamma, or penetrating) reading was reported as zero, the missed dose 

assigned should be the appropriate penetrating LOD for that era (divided by 2, treated as 

lognormal) and considered 30- to 250-keV photons.

19. If both the OW and S readings were reported as zero, the missed dose assigned should be the 

appropriate nonpenetrating LOD for that era (divided by 2, treated as lognormal) and 

considered 30- to 250-keV photons.

20. During the film-badge era, for a person potentially exposed to neutrons, assign unmonitored 

neutron dose based on neutron-gamma ratios per the TBD (using an organ DCF of 1).

21. During the TLD era, for a person potentially exposed to neutrons, if a zero neutron result was 

recorded, assign missed dose per the TBD (using an organ DCF of 1).

Tables C-1 and C-2 provide examples of skin dose assignments for Hanford badge readings in 

1980 and 1970, respectively, assuming no clothing correction.

ATTACHMENT C

SKIN DOSE ASSIGNMENT FOR HANFORD CASES 

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Table C-1. Examples of skin dose assignments for Hanford badge readings in 1980 (assuming no 

clothing correction) (mrem).5

Shallow 

reading

Deep 

reading Measured dose assigned Missed dose assigned

50 0 50 (electrons or <30-keV photons) 20/2 = 10

(30- to 250-keV photons)

0 0 None 30/2 =15

(30- to 250-keV photons)

100 60 40 (electrons or <30-keV photons) AND

60 (photon energy per TBD)

None

100 100 100 (photon energy per TBD) None

0 40 40 (photon energy per TBD) 30/2 = 15 (electrons or low-energy photons)

Table C-2. Examples of skin dose assignments for Hanford badge readings in 1970 (assuming no 

clothing correction) (mrem).5

Beta 

reading

X-ray 

reading 

Gamma 

reading Measured dose assigned Missed dose assigned 

50 0 0 50 (electrons or <30-keV photons) 40/2 = 20

(30- to 250-keV photons)

0 0 0 None 50/2 =25

(30- to 250-keV photons)

100 20 60 100 (electrons or <30-keV photons) AND 20 × 

0.65 = 13 (<30-keV photons) AND 20 × 0.35 = 

7 (30-250-keV photons) AND 60 (photon 

energy per TBD)

None

100 0 100 100 (electrons or <30-keV photons) AND 100 

(photon energy per TBD)

50/2 = 25 (30- to 250-keV 

photons)

ATTACHMENT C

SKIN DOSE ASSIGNMENT FOR HANFORD CASES 

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TABLE OF CONTENTS

SECTION TITLE PAGE

D1. Radiation Protection.............................................................................................................118

D2. Historical Timeline................................................................................................................122

LIST OF TABLES

D-1 Chronology of radiation standards: occupational external whole body 

dose equivalent limits........................................................................................................... 121

D-2 Abbreviated timeline of significant Hanford radiation exposure associated 

events .................................................................................................................................. 123

LIST OF FIGURES

D-1 HEW Special Work Permit Form .......................................................................................... 120

This attachment contains a summary of Hanford Radiation Protection practices and an abbreviated 

historical timeline used in the preparation of the analyses of 100, 200, and 300 Area radiation 

protection practices and workplace measurements and controls. 

D1. RADIATION PROTECTION

The basic elements of Hanford radiation protection were generally well defined at the beginning of 

Hanford operations. The early history of the MED included formation of a medical occupational safety 

program and its implementation at Hanford is described by Wilson (1987). Basic elements of the 

Hanford Engineer Works (HEW) radiation protection program included:

• Clear designation of operations management as responsible for worker safety and formation of 

the “Health Instrument” organization’s role to be responsible to management for radiation 

safety. This organization was responsible for development of radiation protection instruments 

and implementing site-wide dosimetry capabilities. 

• A dedicated radiation protection organization of Health Physicists to measure radiation levels 

in the facilities and to control worker exposures in collaboration with operations management.

• Incorporation of a site training program to inform workers of radiation risks in a series of 

“Special Hazards Bulletins.” 

• Adoption of a system of preplanning work tasks to minimize worker exposure using Special 

Work Permits (SWPs) that required approval by Radiation Protection and Operating Divisions 

responsible for the planned work. 

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• Incorporation of operational limits for Hanford worker exposures that were less than the official 

limits to provide an additional measure of safety.

Special Hazards Committee

A Special Hazards Committee (a subcommittee to the Hanford Central Safety Committee) was 

designated in November 1944 to review various phases of radiation hazards. This committee issued 

a series of Special Hazard Bulletins beginning during 1945 to serve as guidance as follows:

• Procedures for Work in Danger Zones

• Procedures for Suspected or Known Overexposures or Contamination

• Contaminated Waste Disposal

• Procedures for Injuries in a Product Work Zone

• Procedure for Inter-Area and Off-Plant Transfer of Special Process Materials

• Investigation and Reporting of Unsafe Practices or Incidents Arising from Special Hazards

• Procedure for Releasing Equipment from Areas Wherein Contamination is Possible.

• Procedure for Fire Fighting in Radiation Danger Zones.

In the years that followed, many additional Hazards Bulletins were issued describing specific hazards 

and procedures to be followed. These were used in site training programs. 

Special Work Permit

The SWP was implemented to ensure against doing work in “Radiation Danger Zones” until each job 

has been properly analyzed from a personnel safety standpoint and approved by responsible 

representatives of the Health Instrument Organization, the Operational Division, “P” or “S” Division, 

and the division doing the work (GE 1949, Special Hazards Bulletin #1). The SWP form in 1949 is 

shown in Figure D-1.

Radiation Protection Standards

The basic elements of Hanford radiation protection practices were defined in the earliest years of 

operating Hanford 100, 200 and 300 Area facilities. In the earliest years of Hanford operations, the 

MED and AEC used radiation protection guidance provided by national and international 

organizations. Generally, Hanford had operational limits that were less than the allowed national 

guidance. Pertinent Hanford Standards or Manuals of Radiation Protection include:

• HW-7-2602, Tolerance Limits, contains a table which identifies tolerance values to be used in 

the control of special hazards at Hanford (Cantril 1945).

• HW-25457, Manual of Radiation Protection Standards, December 15, 1954 (GE 1954). This 

manual contains policies for control of radioactive materials and radiation hazards at Hanford. 

These Hanford standards were formulated from national policies on radiation protection, AEC 

requirements for control of radioactive materials, and working limits that were adopted over a 

period of years. 

• HW-25457, Rev. 2, Manual of Radiation Protection Standards, March 1, 1960 (GE 1960). This 

manual contains Hanford policies relevant to control of work with ionizing radiation and 

radioactive material.

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Figure D-1. HEW Special Work Permit Form (HEW 1949).

• AEC Manual, Chapter 0524, “Standards for Radiation Protection,” (AEC 1963). Prior to the 

issue of Chapter 0524, Hanford worker occupational radiation exposures were limited based 

on guidance from the NCRP. Several facets of radiation protection are addressed in this 

document. About January 1, 1965, Hanford operations were divided among several 

contractors. Each of the Hanford contractors was expected to formalize company-specific 

requirements that complied with the AEC/ERDA/DOE guidance.

The limits and chronology are shown in Table D-1.

There are also several radiation protection program procedures documents that provide detailed 

descriptions of the conduct of the programs. These are described in the following:

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Table D-1. Chronology of radiation standards: occupational external WB dose equivalent limits.

Year

ICRP NCRP AEC/ERDA/DOE

Hanford Radiation 

Protection Guidance

Criteria Ref. Criteria Ref. Criteria Ref. Criteria Ref.

1945 γ–0.1 R/d

β–0.1 rep/d

FN–0.02 rep/d

SN–0.025 rep/d

Cantril 1945

1947 0.2 rad/d

1.0 rad/wk

0.1 rad/d

0.5 rad/wk

NBS 

Handbook 18 

(NCRP 1934)

0.1 rad/day NBS Handbook 

18 (NCRP 1934)

1949 0.2 rad/d

1.0 rad/wk

0.3 rad/wk NBS 

Handbook 42 

(NBS 1949)

0.1 rad/day (as above) GE 1949

1950 0.3 rad/wk 0.3 rad/wk 0.3 rad/wk

3.9 rad/13 wk

NBS Handbook 

47 (NBS 1950)

1954 0.3 rad/wk 3.0 rad/13 wk

0.3 rad/wk 

15 rem/yr

NBS 

Handbook 59 

(NBS 1954

3.0 rad/13 wk

0.3 rad/wk 

max, 15 rem/yr

NBS Handbook 

59 (NBS 1954)

γ–3 R/yr 

Nt–3 rem/yr

GE 1954

1957 0.3 rad/wk 5 rem/yr avg

12 rem/yr 

Max

Addendum to 

NBS 

Handbook 59 

(NBS 1958)

3.0 rad/13 wk 

0.3 rad/wk max

15 rem/yr

1958 0.1 rem/wk, 

3.0 rem/13 

wk, 5 (N-18) 

rem*

ICRP 

Publication 

1 (ICRP 

1959)

0.3 rem/wk 

3 rem/13 wk, 

12 rem/yr 

max, 

5 (N-18) 

rem*

Addendum to 

NBS 

Handbook 59 

(NBS 1958

0.3 rem/wk, 3.0 

rem/13 wk

12 rem/yr 

5 (N-18) rem*

NBS Handbook 

59 (NBS 1954)

1960 0.1 rem/wk, 

3.0 rem/13 

wk, 

5 (N-18) 

rem*

0.3 rem/wk 

3 rem/13 wk, 

12 rem/yr

5 (N-18) 

rem*

3 rem/13 wk, 5 

rem/yr avg 

5 (N-18) rem*

Federal 

Radiation 

Council Report 1 

(FRC 1960)

Total–5 rem/yr, 

γ–3 R/yr

GE 1960

1963 Prospective:

Qtr–3 rem

Year–5 rem

Retrospective 

Accumulated 

Dose: 5(N-18)

AEC Manual, 

Chapter 0524 

(AEC 1963)

Prospective:

Qtr–3 rem

Year–5 rem

Retrospective 

Accumulated 

Dose: 5(N-18)

1965 3 rem/13 wk

5 rem/yr

ICRP 

Publication 

9 (ICRP 

1966)

0.3 rem/wk 

3 rem/13 wk

12 rem/yr 

5 (N-18) 

rem*

3 rem/13 wk

5 rem/yr avg

5 (N-18) rem*

1971 3 rem/13 wk

5 rem/yr 

3 rem/13 wk

5 rem/yr

NCRP 

Report 38 

(NCRP 1971)

3 rem/13 wk

5 rem/yr avg

5 (N-18) rem*

1974 3 rem/13 wk

5 rem/yr 

3 rem/13 wk

5 rem/yr

3 rem/13 wk

5 rem/yr

NCRP Report 38 

(NCRP 1971)

1977 5 rem/yr 

acceptable 

risk

ICRP 

Publication 

26 (ICRP 

1977)

3 rem/13 ws

5 rem/yr

3 rem/13 wk

5 rem/yr

• HW-7-4282, Medical Department, Health Instrument Section, Manual of Standard Procedures, 

Personnel Meters, May 1, 1946 (HEW 1946). The procedures in this manual primarily pertain 

to administration of the Hanford pencil meter and beta/photon film dosimeter programs. Many 

routine Hanford activities are described such as the “weekly restricted report” that was used to 

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summarize personnel with higher recorded doses. The issue of monitoring doses for rover 

(working at more than one area routinely) is described in this document.

• HW-46104, Manual of Standard Procedures for 100, 200, and 300 Area Survey Work, 

December 1, 1949 (GE 1949). This is an extensive document that describes Hanford portable 

radiation detection instrumentation, calibration, survey methods, radiation protection limits, the 

first eight Hazards Bulletins, and general radiation protection considerations for each of the 

primary controlled 100, 200 and 300 Areas. The use and purpose of the SWP is described. 

This document also includes an index.

• External Dosimetry Operation, Operation Procedures Manual, March 23, 1963 (GE 1963a). 

This is the dosimeter section from a formal procedures manual describing dosimeter 

assignment, processing, calibration and dose determination. Section I concerns the 

beta-gamma film dosimeter and Section II concerns the neutron film dosimeter. Procedure 

2.7, Section 3.c., states that “in essentially all facilities other than 200-W Area a positive fast 

neutron dose almost never occurs without an accompanying gamma dose of at least 100 mr 

(Watson 1959).”

Levels of beta, photon and neutron radiation have been monitored by health physics staff using 

personnel dosimeters, pocket ionization chambers, and portable radiation detection instruments. 

Personnel dosimeters represent the usual method to measure and record the official dose for a 

worker. However personnel dosimeters are assigned to workers typically for a specified period (i.e., 

weekly, monthly or quarterly depending on potential for radiation exposure), and exchanged for new 

dosimeters according to an established monthly or quarterly schedule. Dosimeters on return are 

typically processed and doses assigned as part of the Hanford site-wide group of dosimeters. 

Typically the official dose based on the dosimeter is not received by the worker or their supervision 

until many days after a dosimeter has been routinely exchanged and certainly well after radiation 

exposure to the worker has occurred. Administrative control of worker exposures is based on results 

of PICs or portable instruments and timekeeping. These are the real methods used day-to-day to limit 

worker radiation exposures. Basically, a cumulative administrative radiation exposure record is 

maintained for each worker for use in tracking and, as necessary, limiting exposures. Dose results 

from the personnel dosimeters for each exchange cycle are used to update the administrative 

exposure record. The dosimeter exchange cycle is selected based on the exposure potential for each 

worker and, in case of an incident, personnel dosimeters can be special-processed at any time. This 

process requires close attention by supervision and radiation safety personnel to the total exposure 

accumulated by each worker.

D2. HISTORICAL TIMELINE

Because of the number of relevant references, Table D-2 contains a timeline of historical radiation 

associated events at Hanford. This was prepared as an aid in examining the issues and practices. 

As feasible, pertinent information has been transcribed from the references that are contained in the 

NIOSH Project Site Research DataBase (SRDB). The document number, as applicable, and the 

SRDB reference identification are also provided. These references do not necessarily appear in the 

main reference list for this document.

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Table D-2. Abbreviated timeline of significant Hanford radiation exposure associated events.

Reference Description

1944

PNL-6125

SRDB 262

First use of dosimeters (PICs and film) described in Wilson (1987). The first pencil 

dosimeter program was started in January 1944 in the 100 area. Film badges were used 

at the 100-B reactor beginning September 1944.

WHC-MR-0440

SRDB 34730

DUN-6888

SRDB 333

Hanford 305 Test reactor begins operation during March 1944 as described in Multiple 

Missions: The 300 Area in Hanford Site History (September 1993). This reactor was 

constructed to provide testing of each lot of graphite, uranium, aluminum tubes, etc., to 

be used in the Single-Pass Production reactors and in the fabrication of fuel for these

reactors. The 305 Test Reactor was located above ground and operated at very low 

power level usually less than 50 W. The 305 Test Reactor was operated nearly 

continuously when necessary to support construction of Hanford plutonium production 

reactors because of the magnitude of components to be tested. Test reactor operations 

were stopped during 1972.

HW-3-39

SRDB 38385

Letter, G. L. Veil to G. H. Sanford, entitled “Radiation Leakage Through Overlapping 

Joints in Charging Face Shield of 305 Test Pile,” concerning calculation of potential 

radiation doses at a point directly in front of one of the cracks through the front shield for 

the case of continuous operation at 10 W. Tolerance fluxes corresponding to a dose of 

0.01 R in 8 hours were established as:

Radiation Tolerancea

Fast neutrons 20/cm2 × sec

Slow neutrons 1,300/cm2 × sec

Gamma–quanta 300/cm2 × sec

a. Dose of 0.01 R in 8 hours.

Estimated fraction of tolerance (in 8 hours)

Radiation Fraction of tolerance in 8 

hours

Fast neutrons 0.001

Slow neutrons 0.00002

Gamma–quanta 0.00002

HW-7-103

SRDB 5025

Hanford Engineer Works April 1944 monthly report. Routine reports continue throughout 

the years by numerous organizations. Report series “Health Instruments Report on the 

200 Areas and Associated Laboratories for the week Ending MM/.DD/YY” contains in 

particular PFP-associated information regarding T or B Plant concentration (224 Bldg) 

and isolation building (231) issues.

HW-7-189

SRDB 5026

Hanford Engineer Works June 1944 monthly report. Routine report of status for the 

variety of facility construction and testing underway. 305 Test pile operations continued 

to test graphite and other materials for construction and operations use.

HW-3-356

SRDB 49244

“Chambers for Health Monitoring to be used with Beckman Locations” (July 16). This 

memorandum states objections to the wall thickness and use of steel in the design of a 

portable ionization chamber instrument because of its inability to measure low-energy 

photons. The proposed solution is to redesign the instrument using aluminum or plastic 

and to provide prototypes for testing.

PNNL-13524

SRDB 12856

DUN-6888

SRDB 333

First of Hanford single-pass cooling reactors, B Reactor, begins operation (September 

27). 

HW-7-819

SRDB 60625

Letter, R. S. Stone, MD, to Dr. D. W. Norwood, MD, Kadlec Hospital, “Exposures 

Exceeding Tolerance,” dated October 25, 1951. This letter describes possible worker 

assignments in the event of a radiation exposure exceeding tolerance limits.

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Reference Description

HW-3-1120

SRDB 31615

Fast Neutron Survey Meter (November 20). A portable fast neutron survey meter was 

developed that measures the current in a methane-filled chamber due to the reaction of 

fast neutrons on the methane. Two chambers are employed, one filled with argon and 

the other with methane. The two chambers are operated in a differential manner, and if 

the pressures are properly adjusted in the two chambers the currents due to photon 

radiation is balanced leaving only the current due to neutrons.

HW-7-703, Parts I 

and II

SRDB 38394

HEW Operating Standards–100, 200, and 300 Areas, 1943–1946. The Hanford Engineer 

Works Operating Standards Manual, which was issued in 1944, consists of standards 

that outline the limits and broadly define certain important criteria by which it was decided 

that the operation of the 100, 200, and 300 Areas should be guided, based on the best 

available knowledge at the time. Each standard was approved by the representatives of 

the Metallurgical Project, the HEW Technical and Process Groups, and HEW 

Management. Level 300 procedures in Part II pertain to 300 Area activities to prepare 

and test reactor fuel and various reactor components.

HW-7-750

SRDB 5039

Hanford Engineer Works September 1944 monthly report (October 10). Routine report 

regarding overall plant status. 100-B Pile achieved initial operation at 11:50 p.m. on 

September 26. Report states that PICs had been provided to the 100-B area since the 

start of operations. The use of PICs was restricted to people who had access to the 105 

Restricted Area. Report also states that film badges were in use for all people eligible to 

enter the 100 Areas.

HW-7-863

SRDB 38394

Summary of HI Surveys Obtained at Power Level of 38 MW–100-B Area (October 12). 

Report describes the extent and findings of Health Instruments (HI) group startup surveys 

of the 100-B facility. This was anticipated to be one of several power ascension surveys 

conducted at specified power levels. Neutron and photon radiation exposures were 

detected at specific reactor locations.

HW-7-870

SRDB 5041

Hanford Engineer Works October 1944 monthly report (November 10). Routine report 

regarding overall plant status. Report describes collaboration among Industrial Medical, 

HI, and Production Superintendent appointed committee to develop a work permit 

procedure for work to be done in hazardous zones. This procedure is outlined in “Special 

Hazards Bulletin No. 1,” which was expected to greatly increase safety in that 

responsibilities and procedures were now formalized.

DUN-6888

SRDB 333

Startup of D Reactor (December 17).

PNNL-13524

SRDB 12856

T-Plant begins (December 26) chemical separation of B Reactor irradiated fuel

1945

HW-7-3090

SRDB 439

Comparison of Badge Film Readings at the Metallurgical Laboratories, Clinton 

Laboratories and the Hanford Engineering Works. This report describes quality review of 

Hanford beta/photon film dosimetry and densitometer systems in comparison with 

systems used at what are now Argonne National Laboratory and ORNL, respectively.

DOE/RL-97-1047

SRDB 27666

Receipt of plutonium nitrate in 231-Z Building to begin efforts to prepare plutonium nitrate 

to be delivered to Los Alamos (January 16, 1945). 

HW-3-1774

SRDB 37871

Portable Beckman Survey Meter, Final Report, IDS-29 (February 24). The Beckman 

Portable Survey Meter is a portable battery-powered instrument capable of measuring 

gamma or beta radiation. The instrument was developed by Chicago and the National 

Technical Laboratories of South Pasadena, California, which manufactured the meters. It 

consisted of a d.c. amplifier and an ion chamber with a thin window to permit soft 

radiation measurements; this window could be covered with a thicker slide when 

measurement of gamma radiation was desired.

PNNL-13524

SRDB 12856

First shipment (February 5) of Hanford-produced plutonium nitrate (PuNO3) to Los 

Alamos for final processing.

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Reference Description

DUN-6888

SRDB 333

F Reactor startup (February 25)

PNNL-13524

SRDB 12856

B-Plant begins (April 13) chemical separation of irradiated fuel.

PNNL-13524

SRDB 12856

Hanford-produced plutonium used (August 9) in Fat Man bomb exploded over Nagasaki.

HW-7-2602

SRDB 13428

Correspondence from S. T. Cantril dated October 18, 1945, entitled “Tolerance Limits,” 

that contains a table that identifies tolerance values to be used in the control of special 

hazards at HEW. In particular, the following values are identified:

Tolerance limits for prolonged exposures

Hazard Tolerance Reference

External gamma and X-radiation 0.1 R/d (a)

External beta radiation 0.1 rep/d (a)

Fast neutron radiation 0.02 rep/d (a)

Slow neutron radiation 0.025 rep/d conversion 

gamma rays

CH-2808

a. “The Tolerance Dose”, CH-2812, S. T. Cantril and H. M. Parker, January 1945.

HW-7-1635

SRDB 31345 pg 2

#1 H. I. Report on the 100 Areas and 300 Area for Week Ending May 6, 1945

HW-3-2420 SRDB 

31345 pg 9

#2 H. I. Report on the 100 Areas and 300 Area for Week Ending May 16, 1945

HW-3-2464

SRDB 31345 pg 13

#3 H. I. Report on the 100 Areas and 300 Area for Week Ending May 19, 1945

HW-7-1709

SRDB 31345 pg 16

#4 H. I. Report on the 100 Areas and 300 Area for Week Ending May 26, 1945

HW-7-4193-DEL

SRDB 36779

Hanford Works Monthly Report May 1946

HW-7-1748 SRDB 

31345 pg 20

#5 H. I. Report on the 100 Areas and 300 Area for Week Ending June 2, 1945

HW-7-1783 SRDB 

31345 pg 23

#6 H. I. Report on the 100 Areas and 300 Area for Week Ending June 9, 1945

HW-7-1826 SRDB 

31345 pg 26

#7 H. I. Report on the 100 Areas and 300 Area for Week Ending June 16, 1945

HW-7-1856 SRDB 

31345 pg 30

#8 H. I. Report on the 100 Areas and 300 Area for Week Ending June 23, 1945

HW-7-1934 SRDB 

31345 pg 36

#9 H. I. Report on the 100 Areas and 300 Area for Week Ending June 30, 1945

HW-7-1993 SRDB 

31345 pg 41

#10 H. I. Report on the 100 Areas and 300 Area for Week Ending July 7, 1945

HW-7-2016 SRDB 

31345 pg 48

#11 H. I. Report on the 100 Areas and 300 Area for Week Ending July 13, 1945

HW-7-2064 SRDB 

31345 pg 54

#12 H. I. Report on the 100 Areas and 300 Area for Week Ending July 20, 1945

HW-7-2097 SRDB 

31345 pg 60

#13 H. I. Report on the 100 Areas and 300 Area for Week Ending July 27, 1945

HW-3-2988 SRDB 

31345 pg 67

#14 H. I. Report on the 100 Areas and 300 Area for Week Ending August 3, 1945

HW-3-3017 SRDB 

31345 pg 69

Supplement to Report #14 H. I. Report on the 100 Areas and 300 Area for Week Ending 

August 3, 1945 

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Reference Description

HW-3-3018 SRDB 

31345 pg 71

#15 H. I. Report on the 100 Areas and 300 Area for Week Ending August 10, 1945 

HW-3-3054 SRDB 

31345 pg 74

#16 H. I. Report on the 100 Areas and 300 Area for Week Ending August 17, 1945

HW-7-2326 SRDB 

31345 pg 77

#17 H. I. Report on the 100 Areas and 300 Area for Week Ending August 25, 1945

HW-7-2330 SRDB 

31345 pg 79

#18 H. I. Report on the 100 Areas and 300 Area for Week Ending September 1, 1945 

HW-7-2405 SRDB 

31345 pg 83

#19 H. I. Report on the 100 Areas and 300 Area for Week Ending September 8, 1945

HW-7-2434 SRDB 

31345 pg 89

#20 H. I. Report on the 100 Areas and 300 Area for Week Ending September 15, 1945

HW-7-2442 SRDB 

31345 pg 95

#21 H. I. Report on the 100 Areas and 300 Area for Week Ending September 22, 1945

HW-7-2497 SRDB 

31345 pg 100

#22 H. I. Report on the 100 Areas and 300 Area for Week Ending October 1, 1945

HW-7-2516 SRDB 

31345 pg 102

#23 H. I. Report on the 100 Areas and 300 Area for Week Ending October 8, 1945

HW-7-2548

SRDB 27349

Hanford Engineer Works, Monthly Report, September 1945 (Oct 17). Report mentions 

the use of special neutron sensitive films (i.e., NTA) to be worn by personnel working in 

the vicinity of the piles has been steadily increased, and should become stabilized as the 

regular film procedure from now on. No high reading has been noted during the 

development stages. This is of interest because formal use of NTA film to assign neutron 

dose has not been observed until 1950. 

HW-7-2577 SRDB 

31345 pg 106

#24 H. I. Report on the 100 Areas and 300 Area for Week Ending October 15, 1945

HW-7-2633 SRDB 

31345 pg 110

#25 H. I. Report on the 100 Areas and 300 Area for Week Ending October 22, 1945 

HW-7-2682 SRDB 

31345 pg 113

#26 H. I. Report on the 100 Areas and 300 Area for Week Ending October 29, 1945

HW-7-2721 SRDB 

31345 pg 117

#27 H. I. Report on the 100 Areas and 300 Area for Week Ending November 5, 1945

HW-7-2758 SRDB 

31345 pg 121

#28 H. I. Report on the 100 Areas and 300 Area for Week Ending November 12, 1945 

HW-7-2852 SRDB 

31345 pg 125

#29 H. I. Report on the 100 Areas and 300 Area for Week Ending November 19, 1945

HW-7-2897 SRDB 

31345 pg 129

#30 H. I. Report on the 100 Areas and 300 Area for Week Ending November 26, 1945 

HW-7-2982 SRDB 

31345 pg 133

#31 H. I. Report on the 100 Areas and 300 Area for Week Ending December 3, 1945

HW-7-3017 SRDB 

31345 pg 137

#32 H. I. Report on the 100 Areas and 300 Area for Week Ending December 10, 1945 

HW-7-3076 SRDB 

31345 pg 143

#33 H. I. Report on the 100 Areas and 300 Area for Week Ending December 17, 1945

HW-7-3076 SRDB 

31345 pg 148

#34 H. I. Report on the 100 Areas and 300 Area for Week Ending December 24, 1945 

HW-7-3144 SRDB 

31345 pg 153

#35 H. I. Report on the 100 Areas and 300 Area for Week Ending December 31, 1945 

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Reference Description

HW-7-3171

SRDB 5098

Hanford Engineer Works, Monthly Report, December 1945 (Jan 6, 1946). Site wide 

pencil and film badge processing results for December follow:

Description 100-B 100-D 100-F 200E&N 200-W 300 Total

Total pencils read 10,435 9,633 10,049 25,767 30,064 8,470 94,327

No. of single readings 

(100 to 200 mr)

30 48 71 131 220 36 536

No. of paired readings 

(100 to 200 mr)

1 1 1 6 10 0 19

No. of single readings: 

200 mr

35 72 49 165 224 63 608

No. of paired readings: 

200 mr

0 0 1 1 2 0 4

Badge results by areas

Total badges 

processed

3,386 3,303 3,477 4,568 4,430 2,935 22,099

No. of readings (100 

to 300 mrep)

3 0 5a 14 9b 64 95

No. of readings (300 

to 600 mrep)

0 0 5a 0 0 0 5

No. of readings (600 

mrep)

2 0 2a 0 0 0 4

No. of film packets lost 

in processing

4 2 8 12 4 2 32

a. All fogged

b. One fogged

1946

HW-3-3358

SRDB 76791 ]

Report from W. H. Durum to C. M. Patterson, dated Jan 1, 1946, entitled “Badge and 

Contact Exposure in Bldgs. 313-314 Operations. Report describes results of studies 

involving the placement of extra film badge on all Bldg. 313-314 personnel for a period of 

about two-days (Bldg 314 done and then 313). Time studies were made using stop 

watches for those operations known to involve considerable metal contact. Only 

operations with actual or near-actual contact were considered. A maximum of 65 mrep 

per day was determined for the various work activities. The dose received on the skin 

through the gloves from the bare metal handling was determined by placing finger rings 

in the fingers of a right and left glove, which were then laid over the pieces such that they 

approximated operating conditions. Exposures of 3.5 and 7 hours were then made and 

doses determined from standard T-metal calibrations. A 7 day weighted average 

exposure of 776 mrep to the skin of the finger was determined. The maximum hand 

exposure was determined to be 234 mrep/day for the finish machining task which is a 

continuous operation.

HW-7-3194

SRDB 31554

#53 H.I. Report on the 200 Areas and Environs for the Week Ending January 9, 1946 

(Jan 11).

ATTACHMENT D

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Reference Description

HW-7-3686

SRDB 37868

Brief Review of Health Instruments for Fast and Slow Neutrons (Mar 21). This document 

concerns Neutron Measurements and Instruments in Health Physics. Organized 

measurements of neutron doses received by personnel were virtually nonexistent before 

the potential demands of the Project developed. The design and construction of good 

neutron meters for Health Physics therefore lagged behind other aspects of Health 

Instrumentation. In addition, early operating experience in the production branches of the 

Project indicated this need for limited neutron monitoring instruments such that emphasis 

on this feature was not required. Many of the provisional neutron instruments used were 

identical with instruments for pure physics. These are briefly mentioned in this document 

to indicate the compromises required in the absence of true “health physics” or tissue 

absorption systems. This document describes 1) Chang and Eng, 2) Hydrogen Pressure 

Chambers, 3) Boron Lined Lauritsen Electroscope, 4) Spherical Ion Chamber and 5) 

Proton Recoil Chamber.

DUN-6888

SRDB 333

B Reactor shutdown from March 19, 1946 to July 2, 1948.

HW-7-3748

SRDB 37823

Experimental Justification of the Two-Pencil Policy (Apr 1). The policy of wearing pencil 

meters in pairs was developed in the early days of the project when individual pencils 

gave unreliable results, and the number of lost records was naturally reduced by the 

lower probability of the failure of both members of a pair. Three years of operating 

experience have shown slow but steady gains in the reliability of pencils. It was therefore 

becoming pertinent to inquire into the following two points:

1. Is it still desirable to operate pencils in pairs?

2. The principle that the lower reading of a pair is the valid record has been 

assumed throughout. To what degree is this approximation valid?

This document addresses these issues.

HW-7-5078

SRDB 31561

#89 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

9/25/46 (Sept 26).

HW-7-4211

SRDB 15201

Document entitled “Review of Personnel Monitoring at Hanford Engineering Works” 

prepared by HM Parker sometime during 1946 describing pertinent aspects of the 

assignment, collection and processing of pocket ionization chambers and film badge 

dosimeters, as well as many other aspects of workplace radiological controls.

HW-7-4425

SRDB 31493

#64 H. I. Report for the 100 Areas and 300 Area for Week Ending July 22, 1946. Report 

states there was no high pencil reading in the 300 Area confirmed by a badge reading. 

There were 29 badges for 300 Area people who do not wear pencils, which had readings 

between 100 and 260 mrem. Seventeen 300 Area badges were not marked, but none of 

these readings were high. Two badge readings were lost, one because it was exposed 

to X-ray and one was light struck.

HW-7-5009

SRDB 31494

#71 H. I. Report for the 100 Areas and 300 Area for Week Ending September 9, 1946. 

Report states there was no high pencil readings confirmed by a badge reading. There 

were 11 badge readings for 300 Area personnel who are not required to wear pencils 

with readings between 100 and 200 mrep.

HW-7-5113

SRDB 31495

#74 H. I. Report for the 100 Areas and 300 Area for Week Ending September 30, 1946. 

Report states there was no high pencil readings confirmed by a badge reading and there 

was no high badge reading. There were 12 badge readings for 300 Area personnel not 

required to wear pencils, between 100 and 200 mrep.

ATTACHMENT D

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Reference Description

HW-7-5184

SRDB 31496

#76 H. I. Report for the 100 Areas and 300 Area for Week Ending October 14, 1946. 

Report states there was no high pencil readings confirmed by a badge reading and there 

was no high badge reading. There were 13 badge readings for 300 Area personnel not 

required to wear pencils, between 100 and 200 mrep.

300 Area–October

Description No.

Special work permits processed 10

Air monitoring samples 9

HW-7-5276

SRDB 31497

#78 H. I. Report for the 100 Areas and 300 Area for Week Ending October 28, 1946

HW-7-5289

SRDB 31566

#94 H. I. Report for the 200 Areas and Associated Laboratories for Week Ending October 

30, 1946.

HW-7-5302

SRDB 37166

#79 H. I. Report for the 100 Areas and 300 Area for Week Ending November 4, 1946

HW-7-5343

SRDB 31498

#80 H. I. Report for the 100 Areas and 300 Area for Week Ending November 11, 1946

HW-7-5351

SRDB 31567

#97 H. I. Report for the 200 Areas and Associated Laboratories for Week Ending 

November 13, 1946.

300 Area Facilities

Description No.

Special work permits processed 9

Air monitoring samples 3

Routine and special surveys 11

Smear samples for alpha counts 200

Smear samples for beta counts 155

HW-7-5368

SRDB 31499

#81 H. I. Report for the 100 Areas and 300 Area for Week Ending November 18, 1946.

300 Area Facilities

Description No.

Special work permits processed 8

Air monitoring samples 12

Routine and special surveys 11

Smear samples for alpha counts 35

Smear samples for beta counts 35

HW-7-5397

SRDB 31500

#82 H. I. Report for the 100 Areas and 300 Area for Week Ending November 25, 1946

HW-7-5488

SRDB 31501

#84 H. I. Report for the 100 Areas and 300 Area for Week Ending December 9, 1946

ATTACHMENT D

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Reference Description

HW-7-5545

SRDB 31502

#86 H. I. Report for the 100 Areas and 300 Area for Week Ending December 23, 1946. 

Report states there was no high pencil readings confirmed by a badge reading and there 

was no high badge reading. There were 11 badge readings for 300 Area personnel not 

required to wear pencils, between 100 and 400 mrep.

300 Area–December

Description No.

Special work permits processed 5

Routine and special surveys 4

Air monitoring samples 9

HW-7-3933

SRDB 7786

H. I. Section Report for April 1946

HW-7-4699

SRDB 31603

H. I. Section Report for August 1946

HW-7-3517

SRDB 36868

H. I. Section Report for February 1946

HW-7-3322

SRDB 36865

H. I. Section Report for January 1946

HW-7-4312

SRDB 31604

H. I. Section Report for June 1946

HW-7-5428

SRDB 37387

H. I. Section Report for November 1946

HW-7-5301

SRDB 52812

H. I. Section Report for October 1946

HW-7-5145

SRDB 37496

H. I. Section Report for September 1946

SRDB 15199 Manual of Standard Procedures: Personnel Meters, Part 16, Film Calibration and Batch 

Assignments

HW-7-4262

SRDB 38352

Manual of Standard Procedures, Laundry Monitoring (May 1). The stated purpose of this 

standard procedure is to outline the approved method of monitoring laundry and to 

standardize the methods and procedures required. 

HW-7-4282

SRDB 15199

Medical Department, Health Instrument Section, Manual of Standard Procedures–

Personnel Meters (May 1). The procedures in this manual primarily pertain to 

administration of the Hanford pencil meter and beta/photon film dosimeter programs. 

Many routine Hanford activities are described such as the weekly restricted report that is 

used to summarize personnel with higher recorded doses. The issue of monitoring doses 

for rover (working at more than one area routinely) is described. 

HW-7-5289

SRDB 31566

#94 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

10/30/46 (Nov 1).

HW-7-5351

SRDB 31567

#97 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

11/13/46 (Nov 14).

HW-7-5409

SRDB 31569

#99 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

11/27/46 (Nov 29).

HW-7-5465

SRDB 31570

#100 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

12/4/46 (Dec 5).

HW-7-5531

SRDB 31571

#102 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

12/18/46(Dec 18).

HW-7-5553

SRDB 31573

#103 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

12/25/46(Dec 27).

ATTACHMENT D

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Reference Description

1947

HM-11

(Sent)

An Introduction to Plutonium provided in internal General Electric Memorandum (Aug 29). 

The oxalate precipitate as formed in purification is a flocculent precipitate somewhat 

similar to aluminum hydroxide. It settles quite rapidly and forms a rather dense cake. It 

is a rich green color and can be readily transferred as a slurry. This oxalate after drying 

and oxidizing has a light brown color and after fluorination to the tetrafluoride, it is a light 

pink, having the color and consistency of face powder. 

Plutonium is far more dangerous internally than it is externally due to the fact that 

plutonium is not easily eliminated from the body but concentrates in the bone marrow 

where its alpha radiation stops the production of the white cells in blood. One microgram 

of plutonium in a human body is considered the life time tolerance. The quickest way of 

obtaining this tolerance is by allowing plutonium to enter the body through a break in the 

skin. The other paths of entry, the mouth and nose make necessary the careful 

monitoring of air, and hands, as well as general checks for surface contaminations....It is 

desired to run all operations wherever possible without the spread of any plutonium, 

preventing the contamination of personnel.

HW-7-5595

SRDB 31503

#88 H. I. Report for the 100 Areas and 300 Area for Week Ending January 6, 1947

HW-7-5633

SRDB 31574

#105 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

1/8/47(Jan 10).

HW-7-5680

SRDB 31504

#90 H. I. Report for the 100 Areas and 300 Area for Week Ending January 20, 1947

HW-7-5688

SRDB 31575

#107 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

1/22/47(Jan 23).

HW-7-5706

SRDB 31521

#91 H. I. Report for the 100 Areas and 300 Area for Week Ending January 27, 1947

HW-7-5760

SRDB 37499

H. I. Section Report for January 1947

HW-7-5757

SRDB 31522

#92 H. I. Report for the 100 Areas and 300 Area for Week Ending February 3, 1947

HW-7-5882

SRDB 50787

H. I. Section Report for February 1947.

HW-7-6025

SRDB 31523

#100 H. I. Report for the 100 Areas and 300 Area for Week Ending March 31, 1947

HW-7-6140

SRDB 31524

#104 H. I. Report for the 100 Areas and 300 Area for Week Ending April 28, 1947

HW-7-6284

SRDB 31525

#108 H. I. Report for the 100 Areas and 300 Area for Week Ending May 26, 1947

HW-7-6409

SRDB 31526

#111 H. I. Report for the 100 Areas and 300 Area for Week Ending June 16, 1947

HW-7-6450

SRDB 31527

#112 H. I. Report for the 100 Areas and 300 Area for Week Ending June 23, 1947

HW-7184-PT2

SRDB 24119

H.I. Lecture Series -- Part 11 -- Introductory Lecture Series in Health Instrumentation 

(Lectures 16-21) (Jul 1). Lectures used as part of the regular technical training for 

personnel assigned to radiation protection duties. This reference describes the Hanford 

operating facilities and processes, and the hazards. 

HW-7795-DEL

SRDB 37568

Hanford Works Monthly Report September 1947

HW-7997-DEL

SRDB 37569

Hanford Works Monthly Report October 1947

ATTACHMENT D

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Reference Description

HW-8267-DEL

SRDB 37571

Hanford Works Monthly Report November, 1947

HW-7-5633

SRDB 31574

#105 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

1/8/47(Jan 10).

HW-7-5688

SRDB 31575

#107 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

1/22/47(Jan 23).

HW-7-5734

SRDB 31581

#108 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

1/29/47(Jan 30).

HW-7-5784

SRDB 31583

#109 H.I. Report on the 200 Areas and Associated Laboratories for the Week Ending 

2/5/47(Feb 7).

HW-8438-DEL

SRDB 37580

Hanford Works Monthly Report December, 1947

Personnel Meters Monthly Report December 1947.

Description 100-B/D 100-F 200E&N 200-W 300 Total

Total pencils read 11,918 13,514 32,143 34,964 31,098 123,637

No. of single 

readings (100 to 

280 mr)

53 64 86 65 83 351

No. of Paired 

readings (100 to 

280 mr)

0 0 0 1 0 1

No. of single 

readings: >280 mr

166 148 272 71 201 858

No. of paired 

readings: 280 mr

0 1 4 2 3 10

Badge results by areas

Total badges 

processed

7,166 4,829 4,986 6,072 5,469 28,522

No. of readings 

(100 to 500 mrep)

2 1 14 0 80 98

No. of readings (> 

500 mrep)

0 0 0 1 0 1

No. of film packets 

lost in processing

2 1 16 2 1 22

1948

HW-8931-DEL

SRDB 37582

Hanford Works Monthly Report January 1948

HW-9191-DEL, 

HAN-13586

SRDB 36762

Hanford Works Monthly Report February 1948

HW-9595-DEL

SRDB 37587

Hanford Works Monthly Report March 1948

HW-8547

SRDB 38397

Slow Neutron Survey Method (Jan 5). A comparison of surveys made with slow neutron 

pencils and the BF3 Counter at the 100-F instrument cubicles in the -9’ Level and the “B” 

Test Hole Assembly show fairly close correlation for fluxes below 10 mrem/hr. 

Accordingly it is concluded that pencils should be quite satisfactory for direct survey and 

personnel monitoring.

ATTACHMENT D

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Reference Description

Bldg 234-5 construction begun (June) originally to build the Remote Mechanical (RM) 

design but changed to the Rubber Glove (RG) design because of time constraints. The 

RG design was a simpler method whereby operators would operate the process manually 

through rubber gloves. 

HW-9922-DEL

SRDB 37591

Hanford Works Monthly Report April 1948

HW-8973

SRDB 34747

Proposed Revisions of H.I. Procedures: Routine Film Badge Program (Feb 25). This 

report describes elements of the existing administration of the Hanford personnel 

dosimetry program and potential changes. The report describes that all workers (site and 

contractor) are issued dosimeters upon entry into a radiological controlled area (i.e., 100, 

200 and 300 Areas).

HW-9585

SRDB 37891

A Portable Fast Neutron Survey Meter–Preliminary Report (Apr 20). A portable fast 

neutron survey meter called “Neut” with a useful neutron survey range from 0.5 mrem/hr 

to 10 rem/hr, approximately, has been developed. It uses argon and methane chambers 

separately with a modified Zeuto measuring circuit. Gamma ionization current is 

cancelled with a slide-back arrangement. Preliminary reports from the Survey Group 

indicate satisfactory performance.

HW-10166-DEL

SRDB 37256

Hanford Works Monthly Report May 1948

HW-10378-DEL

SRDB 37261

Hanford Works Monthly Report June 1948

HW-10714-DEL

SRDB 37265

Hanford Works Monthly Report July 1948

DUN-6888

SRDB 333

B Reactor returns to operation

HW-10993-DEL, 

HAN-18766-DEL

SRDB 37270

Hanford Works Monthly Report August 1948

HW-11226-DEL

SRDB 37271

Hanford Works Monthly Report September 1948

HW-11499, HAN20213

SRDB 37274

Hanford Works Monthly Report October 1948

HW-11835-DEL, 

HAN-20858

SRDB 33265

Hanford Works Monthly Report November 1948

HM-206

SRDB 37866

Instrument Requirements for Health Monitoring in the 234-5 Building (June 14). Portable 

alpha, photon and neutron (BF3) instrument needs are identified for the 234-5 Building 

work areas.

HW-10522

SRDB 4909

Bioassay at Hanford (July 20). Document describes methods of analysis for plutonium 

and states that tolerance at Hanford is 0.5 microgram. Bioassay is conducted for three 

groups of identified workers as every three, six and 12 months depending on the potential 

for exposure.

HW-12107

SRDB 37112

#179 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of December 1948 (Dec 31).

HW-12086-DEL

SRDB 37280

Hanford Works Monthly Report December 1948

ATTACHMENT D

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Reference Description

SRDB

File 5/26/09 06114

Personnel Meters Monthly Reports December 1948

Description

December 1948 1948

100-B 100-D 100-F 200E&N 200-W 300 Total

Total pencils 

read

12,788 12,897 14,646 32,002 47,395 42,897 1,692,224

No. of single 

readings (100 

to 200 mr)

25 33 20 45 79 73 4,894

No. of paired 

readings (100 

to 200 mr)

0 0 0 0 1 2 38

No. of single 

readings: 200 

mr

20 28 34 55 98 105 9,761

No. of paired 

readings: 200 

mr

0 0 0 0 2 4 142

Badge results by areas

Total badges 

processed

2,793 2,160 2,068 2,955 3.570 8,435 268,112

No. of 

readings (100 

to 500 mrep)

1 0 0 10 9 215 3,277

No. of 

readings 

(>500 mrep)

0 1 0 1 3 0 49

No. of film 

packets lost in 

processing

0 0 0 14 1 15 230

1949

HW-12390

SRDB 37200

#180 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of January 1949 (Jan 31).

HW-12733

SRDB 37207

#181 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of February 1949 (Feb 28).

HW-12391-DEL

SRDB 37281

Hanford Works Monthly Report January 1949

HW-12666-DEL

SRDB 37282

Hanford Works Monthly Report February 1949

ATTACHMENT D

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Reference Description

HW-12710

SRDB 7756

General (Hanford) Operating Tolerances (Mar 11). The permissible tolerances used at 

Hanford Works are as follows:

External Radiation Limits

Whole Body– 0.3 rem per week or whatever the National Committee on Radiation 

Protection recommends.

Hands Only– 1.0 rem per week or whatever the National Committee on Radiation 

Protection recommend.

Internal Emitter Limits

0.3 rem per week to the significant organ or whatever the National Committee on 

Radiation Protection recommends.

Drinking Water

Uranium–100 μg/liter–believe this is high.

Plutonium**–0.01 μg/liter–intend to revise to not more than 0.001 μg/liter.

Mixed fission products–0.1 μg/liter–to be changed when new figure provided by 

K. Z. Morgan’s Subcommittee

(more limits in reference)

HW-12937-DEL

SRDB 37297

Hanford Works Monthly Report March 1949

HW-13190-DEL

SRDB 37306

Hanford Works Monthly Report April 1949

HW-12959

SRDB 37209

#182 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of March 1949 (Mar 31).

HW-13329

SRDB 37219

#183 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of April 1949 (Apr 29).

DOE/RL-97-1047 

SRDB 27666

234-5 RG line began “hot” processing (i.e., using plutonium feed) (Jul 5). 

ATTACHMENT D

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Reference Description

HW-35745

SRDB 32559

Three Memos: Neutron Measurements in the 234-5 Process (Aug 8). The first memo 

concerns fast neutron measurements at Hood 9 in the 234-5 process with a hydrogen 

recoil proton counter and also with BF3 counters. Monitoring results are presented in the 

report as fast neutron flux densities in n/sec/cm2

. Comparison between the recoil counter 

and the BF3 counter showed 14.3 ± 8.7 counts per minute with the moderated BF3

counter to one neutron per second per cm2 as measured with the recoil counter.

The second memo concerned similar measurements at Hood 8. The recoil counter was 

calibrated with a Po-Be neutron source and the moderated BF3 counter with a Ra-Be 

source. The factor used to convert flux density to dose rate was 0.16 mrem/hr per 1 

neutron/sec/cm2

. The evolution of this factor is described in the memo. The results for 

three positions follows:

Position

n/sec/cm2

Dose rate limits 

(mrem/hr)

Recoil 

counter

Mod.

BF3 Flux limits

A 8±4 16±2 8–16 1.3–2.6

B 15±5 12±2 10–20 1.6–3.2

C 123±18 55±3 50–150 8.0–24

The third memo concerned source specific differences in the response of the 234-5 

standard BF3 counter. Interchanging various components of two calibrated BF3 counters 

introduced only small errors in the counting rate, less than 4%. Allowance was made for 

the sensitivity of the tubes and the correct operating voltage.

Source

Average neutron 

energy (MeV)

Ratio

C/M/n/cm2/sec

PoBe 4.6 10.5±0.2

RaBe >4.6 10.3±0.3

PoB 2.3 13.0±0.4

HW-14403

SRDB 34823

432 Project–Needed Modification of the RM Line (Sep 7). This document summarizes 

several requested design modifications to the RM line and the basic reasons for these 

changes. 

HW-13190-DEL

SRDB 37306

Hanford Works Monthly Report April 1949

HW-13561-DEL

SRDB 40705

Hanford Works Monthly Report May 1949

HW-13793-DEL

SRDB 37311

Hanford Works Monthly Report June 1949

HW-14043-DEL

SRDB 37323

Hanford Works Monthly Report, July 1949

HW-14440

SRDB 355

Fast Neutron Measurements–234-5 Building (Sep 15)

Measurements performed 5 days during Jul-Sep using: 1) proton recoil proportional 

counter to measure PoBe equivalent neutron flux and 2) BF3 with moderator to measure 

counts per minute. Results shown on drawings for selected hoods. 

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Reference Description

HW-14579

SRDB 34824

A Screening Review and Classification of Modifications needed on the RM Line (Sep 21). 

This is a reply to HW-14403 regarding 24 design modifications. Items were assigned to 

one of three classifications as follows:

1. Essential items requiring a cost estimate to determine magnitude of change or 

addition before final request.

2. Needed items on which a cost estimate is required to determine if the expense is 

tolerable.

3. Items in the Schenectady design in which operating difficulties are anticipated 

based on current experience in the RG line and on present design for the RM 

Line.

SRDB 26049 Memorandum dated October 27, 1949 to L.W. Finch, P.C. Jerman, P. R. McMurray and 

J. G. Myers, entitled “Intermediate Neutrons.” Letter stated that with present 

instrumentation, they were unable to determine the flux for neutrons in the intermediate 

energy range. Proposed the following procedure for determining intermediate neutron 

dosage rates.

1. Using a moderated BF3 tube, determine the count and convert to N/cm2/second 

on the basis of the slow neutron calibration.

2. Convert this flux to mrem/hour assuming that 300 N/cm2/second is equivalent to 

6.25 mrem/hour.

HW-15011

SRDB 37223

#189 H.I. Divisions Report on the 200 Areas and Associated Laboratories for the Month 

for October 1949 (Nov 8).

HW-14338-DEL

SRDB 37229

Hanford Works Monthly Report August 1949

HW-14596-DEL 

SRDB 37234

Hanford Works Monthly Report September 1949

HW-14916-DEL, 

HAN-28917

SRDB 33220

Hanford Works Monthly Report October 1949

DUN-6888

SSRDB 333

H Reactor startup (October 29, 1949)

HW-15267-DEL

SRDB 37334

Hanford Works Monthly Report November 1949

HW-46104

SRDB 68858

Manual of Standard Procedures for 100, 200 and 300 Area Survey Work dated 

December 1, 1949. This is a comparatively large manual containing radiation exposure 

limits, contamination limits, Special Work Permits, protective clothing, Special Hazards 

Bulletins, descriptions of the monitoring equipment and general monitoring information 

regarding radiation types, selections of instruments, etc.

HW-15658

SRDB 37230

#191 H.I. Divisions Report on the 200 Areas and Associated Laboratories for the Month 

for December 1949 (Jan 11, 1950).

ATTACHMENT D

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Reference Description

HW-15550-DEL

SRDB 37341

Hanford Works Monthly Report December 1949. Report provides the annual status of 

several monitoring activities as follows

Description

100 

Areas

200 

Areas

300 

Areas Total

Special Work Permits (SWPs) 25,762 10,169 2,344 38,275

Routine and special surveys 19,511 17,953 2,146 39,610

107 Effluent surveys 3,656 3,656

Air monitoring samples 4,952 28,706 1,774 28,706

Thyroid checks 2,599 2,599

Pocket ionization chambers 1,708,976

Construction, beta/photon 

badges 63,388

Routine, beta/photon badges 240,805

Bioassays 15,746

1950

DOE/RL-97-1047 

SRDB 27666

“Skull Recovery Project.” Skulls are thin shells of metallic plutonium that cling to the 

molds when plutonium is cast into specific weapons pieces. Project begun to recover 

plutonium from contaminated scrap. Laboratory work directed at developing recovery 

methods for various other types of Pu-bearing scrap such as powders, sludges, shavings, 

metallic chips, fines, etc.

HW-15843-DEL

SRDB 37346

Hanford Works Monthly Report January 1950

HW-15937

SRDB 72210

Technical Report entitled “Comparative Neutron Absorption of Asphalt and Paraffin,” 

dated January 20, 1950, “describing a study conducted to determine the relative neutron 

absorption of asphalt and paraffin for use as moderators of intermediate and fast 

neutrons emitted from the “T” seams on No. 1 Experimental level of the 100-H pile.” 

HW-17056-DEL

SRDB 37239

Hanford Works Monthly Report February 1950

HW-17410-DEL

SRDB 37244

Hanford Works Monthly Report March 1950

HW-17660-DEL

SRDB 37246

Hanford Works Monthly Report April 1950

HW-15871

SRDB 37232

#192 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of January 1950 (Feb 2).

HW-16038

SRDB 34804

Americium Separation from Plant Solutions (Feb 15). Report describes analysis and 

tests to separate americium from aged plutonium solutions. The first reported 

separations of americium from plutonium was accomplished by successive LaF3

precipitations from oxidized plutonium (VI) solutions. The report evaluates methods that 

could be used in 231 or 234 facilities. 

HW-17191

SRDB 37236

#193 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of February 1950 (Mar 13).

HW-17472

SRDB 37238

#194 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of March 1950 (Apr 11).

HW-17766

SRDB 37241

#195 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of April 1950 (May 10).

HW-17971-DEL

SRDB 36754

Hanford Works Monthly Report May 1950

HW-18221-DEL

SRDB 36757

Hanford Works Monthly Report June 1950

ATTACHMENT D

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Reference Description

HW-18473-DEL

SRDB 36794

Hanford Works Monthly Report July 1950

HW-18740-DEL

SRDB 33271

Hanford Works Monthly Report August 1950

DDTS-Generated426

SRDB 50783

Information concerning radiation exposure of personnel was requested by AEC 

representatives and this letter provides some information for Hanford workers as follows:

Table I.

Description 1947 1948 1949

Total pencils used 1,236,686 1,692,224 1,708,976

Pencils reading between 100 and 280 mr 1 in 7,700 1 in 22,000 1 in 39,000

Pencils reading over 280 mr 1 in 5,900 1 in 6,000 1 in 26,000

Pencils lost 1 in 10,300 1 in 11,500 1 in 13,500

Table II. Number in which both pencils read

Reading between (mr) 1947 1948 1949

0–30 585,535 829,411 836,685

35–60 855 697 238

65–120 88 68 13

125–280 12 15 6

Off scale 84 134 31

HW-18043

SRDB 37243

#195 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of April 1950 (May 10).

HW-18561

SRDB 37091

#196 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of May 1950 (Jun 9).

SRDB 31743 Letter (Oct 19) Keene to Money, Film Badge Readings 234-5 Building, concerning 

maintaining accurate list of 234-5 workers to allow appropriate film badge dose 

interpretation.

HW-19690

SRDB 37141

#202 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of November 1950 (Dec 12).

HW-19910

SRDB 37143

#203 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of December 1950 (Jan 10, 1951).

SRDB 67675 Health Instrument Operational Division, Manual of Standard Procedures, Personnel 

Meters (Aug 18, 1950). This is a form manual that describes procedures used with the 

radiation instruments and dosimeters.

HW-19021-DEL

SRDB 36802

Hanford Works Monthly Report September 1950

DUN-6888

SRDB 333

DR reactor startup (October 3, 1950)

HW-19325-DEL

SRDB 36804

Hanford Works Monthly Report October 1950

HW-19622-DEL, 

HAN-35248

SRDB 36812

Hanford Works Monthly Report November 1950

ATTACHMENT D

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Reference Description

HW-19842-DEL, 

HAN-35587

SRDB 33226

Hanford Works Monthly Report December 1950. This routine monthly report provides the 

annual status of several monitoring activities as follow:

Description 100 Areas 200 Areas 300 Areas Total

Special Work Permits (SWPs) 33,633 11,387 1,437 46,457

Routine and special surveys 23,403 23,555 2,205 49,163

Retention basin surveys 5,035 5,035

Air monitoring samples 7,268 38,874 1,857 47,999

Thyroid checks 1,705 1,705

Pocket ionization chambers 1,596,323

Construction, beta/photon 

badges 33,322

Routine, beta/photon badges 270,203

Neutron NTA film 3,808

Bioassays 29,515

HW-19910

SRDB 37143

#203 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of December 1950 (Jan 10, 1951).

1951

HW-20249

SRDB 37145

#204 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of January 1951(Feb 12).

HW-20161-DEL

SRDB 36831

Hanford Works Monthly Report January 1951

HW-20438-DEL

SRDB 36834

Hanford Works Monthly Report February 1951

HW-20671-DEL

SRDB 36837

Hanford Works Monthly Report March 1951

HW-20991-DEL, 

HAN-37490

SRDB 36856

Hanford Works Monthly Report April 1951

HW-20511

SRDB 37147

#205 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of February 1951(Mar 9).

HW-20785

SRDB 32556

Radiation Studies 234-5 (I) (Apr 17). Report concluded that chief source of neutron 

radiation in 234-5 Bldg is the alpha-neutron reaction in fluorine. Although some neutron 

radiation is detected along the line, it is of significance only with the fluorination step and 

nearly zero once the plutonium is converted to metal. Chief sources of photon radiation 

are X-rays associated with alpha decay, passage of alpha radiation through material, 

gamma rays from plutonium and in the scattering of alpha radiation by fluorine. 

Predominate photon energies are approximately 17, 40 and 200 or higher keV.

HW-22490

SRDB 37291

Monthly Report–September 1951 Radiation Monitoring Services Unit

HW-22763

SRDB 37292

Monthly Report–October 1951 Radiation Monitoring Services Unit

HW-22939

SRDB 37294

Monthly Report–November 1951 Radiation Monitoring Services Unit

HW-23235

SRDB 37296

Monthly Report–December 1951 Radiation Monitoring Services Unit

HW-21260-DEL

SRDB 36864

Hanford Works Monthly Report May 1951

HW-21506-DEL

SRDB 36871

Hanford Works Monthly Report June 1951

ATTACHMENT D

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Reference Description

HW-21802-DEL

SRDB 36889

Hanford Works Monthly Report July 1951

HW-22075-DEL

SRDB 36895

Hanford Works Monthly Report August 1951

HW-20802

SRDB 37148

#206 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of March 1951(Apr 11).

HW-21040

SRDB 37149

#207 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of April 1951(May 8).

HW-21127

SRDB 73704

RMA Line Nomenclature (May 18). This document was prepared to identify terms, 

locations and processes, that were not classified, to enable preparations for RMA startup. 

The document presents a coding of RMA Line equipment in terms of Task number and 

process operations and the associated Instruction book volume number. 

HW-21328

SRDB 31601

#208 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of May, 1951(Jun 11).

HW-21552

SRDB 31711

Fast Neutron Monitoring of Personnel (Aug 1). This document describes the routine 

Hanford procedures of monitoring personnel for fast neutron radiation using NTA nuclear 

Track Emulsions. Effects of energy, angular response, fading, calibration, training, etc. 

are described. The report describes the Hanford practice of using “control badges” which 

contain two NTA film; one is blank (i.e., no exposure) and the other is exposed to a 

known level of exposure. Hanford control and calibration dosimeters are exposed prior to 

assigning these dosimeters so that the assigned dose is maximized to compensate for 

fading. The document describes the extensive training necessary for technicians to 

effectively read the NTA film and that films are routinely read by more than one 

technician to detect significant differences in evaluation. The is also the practice to 

routinely submit audit dosimeters with known neutron exposures for evaluation.

HW-21508

SRDB 36888 

RMA Startup Plans, 234-5 Bldg. (Jul 2). This report describes a list of actions to be done 

as prepared by the RMA Startup Committee and signed by each of the several 

participating Division representatives.

HW-21699

SRDB 37025

Annual Report of the Health Instrument Divisions (Jul 20). This report describes 

radiological exposure events during 1950 in each all of the major Hanford areas and 

facilities. The report describes changes in radiation exposure guidelines resulting from 

the 1949 TriPartite meeting at Chalk River, Canada. 

HW-21905

SRDB 37153

#210 H.I. Divisions Monthly Report on the 200 Areas and Associated Laboratories for the 

Month of July, 1951(Aug 13).

HW-22020

SRDB 26043

Radiation Studies 234-5 Building (III) Nuclear Track Film (Aug 21). Report describes 

neutron spectra difference between 234-5 workplace and Po-B calibration source and the 

issue of the relative energy sensitivity of NTA film and the signal fading expected to 

occur. Recommended that a factor of 5/3 be used to increase the reported neutron 

doses.

HW-22021

SRDB 32557

Radiation Studies 234-5 (IV) Moderated BF3 Calibration (Aug 23). Report describes 

calibration and dose interpretation using BF3 counters and sources of calibration. Using 

a BF3 whose slow neutron calibration is 8.47 cpm per nv both Ra-Be and Po-B sources 

give 7 c/m per neutron/sec. Since no difference is found for these two sources that differ 

considerable in average energy, it was assumed that the same factor can be used for PuF neutrons. The report also describes the dose per unit flux from Pu-F as a value of 

0.011 mrem/hr per neutron/cm2/sec. 

HW-17398

SRDB 38354

Hanford Works, Separations Section, Operating Standards (Oct 15)

• Part I. Bismuth Phosphate and Isolation

• Part II. REDOX

• Part III. Metal Recovery

ATTACHMENT D

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Reference Description

HW-24327

SRDB 26044

Technical report concerning on November 16, 1951 accidentally achieving prompt critical 

condition for a partially full spherical reactor using plutonium nitrate fuel in the 300 Area 

Hanford Homogenous Reactor. 

HW-22902

SRDB 58612

The 120 Bldg Critical Mass Laboratory reactor, during a critical mass study on November 

16, 1951, suddenly went out of control. The primary and secondary safety systems 

automatically shut down the reactor promptly. However, all six workers in the P-11 area 

at the time were overexposed to gamma and neutron radiation as noted in the following:

Worker Location

Estimated exposure (mrems)

Fast neutron Gamma Total

1 Control Building 400 200 600

2 Control Building 400 200 600

3 Control Building 400 200 600

4 Control Building 400 140 540

5 Gate House 225 85 310

6 Gate House 225 75 300

HW-22304-DEL

SRDB 36926

Hanford Works Monthly Report September 1951

HW-22610-DEL, 

HAN-41950

SRDB 36935

Hanford Works Monthly Report October 1951

HW-22875-DEL, 

HAN-42327

SRDB 36943

Hanford Works Monthly Report November 1951

HW-22976

SRDB 36971

Radiation Studies 234-5 Building (V) (Dec 11). This report describes examination of the 

“blackening” of the film badge open window and the derivation of a correction factor 

(0.19) to estimate the X-ray dose from a radium calibration. An example is shown in the 

report in which an interpreted 7500 mR of radium “open window” dose based on the film 

response actually corresponds to 1400 mR of X-ray dose (i.e., 7500 * 0.19). 

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

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Reference Description

HW-23140-DEL

SRDB 35862

Radiological Sciences Report December 1951. This project wide report contains a 

summary of annual activities as shown in the following: 

Description Year-to-date

Special Work Permits 6,643

Routine and special surveys 11,998

Air samples 6,995

Skin contamination 372

Dosimeter Annual summaries as follows:

Description Year-to-date

Pencils 1,954,787

Film badges 319,530

Construction film badges 104,601

Slow neutron pencils 4,472

NTA neutron film 3,895

For the year there were 12 lost pencil readings and 19 lost badge readings which were 

investigated to assign a dose.

Radiological Calibrations as follows:

Description Year-to-date

Fixed instruments (gamma) 2,958

Portable instruments

Alpha 3,285

Beta 6,782

Gamma (radium) 13,297

X-ray scanning 67

Special X-Ray 8

Neutron 47

Personal meters

Beta 9,803

Gamma (radium) 77,181

X-ray 58,492

Neutron 1,583

1952

HW-23437-DEL

SRDB 37353

Hanford Works Monthly Report January 1952

PNNL-13524

SRDB 12856

REDOX Plant begins (January 9) operation

HW-23698-DEL

SRDB 36737

Hanford Works Monthly Report for February 1952

HW-23982-DEL

SRDB 36740

Hanford Works Monthly Report for March 1952

HW-24337-DEL

SRDB 36744

Hanford Works Monthly Report for April 1952

SRDB 74153 R. S. Bell, Manager, Separations Section to R. B. Richards, Manager, Separations 

Technology, entitled “Critical Mass Specifications for the 234-5 Building,” dated Feb. 19, 

1952. This letter describes the conduct of a review of the critical mass history of 234-5 

operations and includes a bibliography of documentation. 

ATTACHMENT D

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Reference Description

DOE/RL-97-1047

SRDB 27666

Hanford’s RMA (Remote Mechanical A) line begins hot processing (March 18)

HW-23862

SRDB 38334

Preliminary investigation of DuPont Film Types (Apr 21). Document describes results of 

tests of DuPont 508 and 560 films in comparison with the DuPont 502 film used at 

Hanford since 1944. The 508 and 560 films are more sensitive than the 502 but do not 

exhibit the 502 film linear response to 1000 mR.

HW-24605-DEL, 

HAN-45180-DEL

SRDB 33232

Hanford Works Monthly Report for May 1952

HW-24697-DEL

SRDB 73707

Proposed Procedures in 234-5 Processes (Jun 6). This document describes a critical 

mass review and provides mass specifications for 234-5 processes.

HW-24928, HAN45659

SRDB 37364

Hanford Works Monthly Report June 1952

HW-25227-DEL

SRDB 36746

Hanford Works Monthly Report for July 1952

HW-25533-DEL

SRDB 36749

Hanford Works Monthly Report for August 1952

HW-23472

SRDB 37299

Monthly Report–January 1952 Radiation Monitoring Services Unit

HW-23655

SRDB 37302

Monthly Report–February 1952 Radiation Monitoring Services Unit

HW-23933

SRDB 37303

Monthly Report–March 1952 Radiation Monitoring Services Unit

HW-24595

SRDB 37308

Monthly Report–May 1952 Radiation Monitoring Services Unit

HW-24859

SRDB 37313

Monthly Report–June 1952 Radiation Monitoring Services Unit

HW-25185

SRDB 37314

Monthly Report–July 1952 Radiation Monitoring Services Unit

HW-25483

SRDB 37316

Monthly Report–August 1952 Radiation Monitoring Services Unit

HW-25728

SRDB 73678

Remote Mechanical Operation Methods Vs. Rubber Glove Operating Methods for the 

234-5 Process (Sept 23, 1952). Analysis of RMA Line operation in comparison with RG 

Line operation. Some historical information concerning RG line operation.

HW-25763

SRDB 37320

Monthly Report–September 1952 Radiation Monitoring Services Unit

HW-26086

SRDB 37321

Monthly Report–October 1952 Radiation Monitoring Services Unit

HW-26396

SRDB 37324

Monthly Report–November 1952 Radiation Monitoring Services Unit

DUN-6888

SRDB 333

C Reactor begins operation (November 18, 1952)

ATTACHMENT D

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Reference Description

HW-23180

SRDB 36891

Neutron Measurements in the 234-5 Process (draft). On July 7, fast neutron 

measurements were made on the product in the 234 process with both a recoil proton 

counter and a moderated boron trifluoride counter. Measurements were made in three 

situations as follows:

1. Two boats in a scow lying in furnace No. 1; top half of the furnace open, product 

had been fluorinated and was cooling at the time. Counters were placed on the 

Hood No. 8 window as close to the oven as possible.

2. Same as above, except that counters were placed in the glove port in line with 

the oven axis. The counter end was about 12 inches from the near end of the 

oven.

3. Two boats in a scow on the transport belt, parallel to the front face of the hood. 

Counters placed in a glove port directly opposite the side of one boat. End of the 

recoil counter and of the moderator about 2 inches from the near side of the 

scow.

The recoil proton counter was calibrated with a PoBe neutron source, and the moderated 

BF3 counter with a RaBe neutron source. The factor used to convert flux density to dose 

rate is 0.16 mrem/hr per 1 neutron/sec/cm2

. The evolution of this factor is described in 

the report (Note: This study appears to be included in HW-35745 that appears to 

summarize three studies done during 1949).

HW-23535

SRDB 73705

Additional Shielding in Hood 8 (Feb 13). Shielding of three waste jars in RG line hood 8 

with six inches paraffin lined with cadmium is proposed to reduce the exposure rate. The 

shielding is planned to fit the curve surface of the jars and the jar bottom. A factor of 10 

reduction in exposure rate is expected. From the perspective of criticality hazards, the 

configuration with 640 grams of sweepings in each jar is considered to be safe. 

HW-23639

SRDB 73706

Reduction of Neutron Flux, Hood 8–RG Line (Feb 26). A study was initiated at the 

request of operating personnel to examine options to reduce the neutron flux at Hood 8. 

In normal practice the total radiation intensity at the face of Hood 8 opposite the weighing 

station is not infrequently in the range of 20 to 30 mrem/hr and at times even higher. 

Customary practice is for the radiation monitor to inform the operator when the measured 

exposure rate exceeds 25 mrem/hr. The operator can move waste jars that contain 

sweepings further back from the face of the hood or to pass the contents of the jars to 

Hood 9 for recovery processing. It is convenient to have the waste jars near the weighing 

station. Some options for installing shielding for these jars was also examined. 

PNNL-13524

SRDB 12856

RMB construction was begun (May)

HW-25709

SRDB 34255

Annual Report of the Radiological Sciences Department, 1951 (Sep 22). The Health 

Instrument Divisions was reorganized under the Radiological Sciences Department. This 

report provides highlights of Hanford Site radiological activities during 1951 for all 

operating areas. 

HW-24915

SRDB 73708

Calibration Procedure for the Victoreen Integron (Jun 30). The integron consists of two 

main parts:

1. A cylindrical unit, the inner side of which is coated with aquadag, is used as the 

outer wall of an ionization chamber. ho

HW-25781-DEL

SRDB 37248

Hanford Works Monthly Report September 1952

HW-26047-DEL

SRDB 36751

Hanford Works Monthly Report for October 1952

ATTACHMENT D

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Reference Description

HW-26376-DEL, 

HAN-48244-DEL

SRDB 34267

Hanford Works Monthly Report for November 1952

HW-26720-DEL, 

HAN-48706,

SRDB 35863

Radiological Sciences Report December 1952. This project wide report contains a 

summary of annual activities as shown in the following: 

Description Year-to-date

Special Work Permits 8,279

Routine and special surveys 14,267

Air samples 20,225

Skin contamination cases 690

Dosimeter Annual summaries as follows:

Description Year-to-date

Pencils 2,630,386

Film badges 524,469

Construction film badges

Slow neutron pencils 11,942

NTA neutron film 5,241

For the year there were a total of 459 lost readings which were investigated to assign a 

dose.

Radiological calibrations as follows:

Description Year-to-date

Fixed instruments (gamma) 2,338

Portable instruments: 24,794

Personal meters: 157,083

1953

PNNL-13524

SRDB 12856

Explosion (Sep) in RMA Line Task III hood requiring 2 week switch to RG Line

HW-26958

SRDB 37326

Monthly Report–January 1953 Radiation Monitoring Services Unit

HW-26946-DEL,

SRDB 52681

Hanford Works Monthly Report for January 1953

HW-27236

SRDB 37327

Monthly Report–February 1953 Radiation Monitoring Services Unit

HW-27288-DEL

SRDB 35864

Hanford Works Monthly Report for February 1953

HW-27564

SRDB 37328

Monthly Report–March 1953 Radiation Monitoring Services Unit

HW-27889

SRDB 37348

Monthly Report–April 1953 Radiation Monitoring Services Unit

HW-28190

SRDB 37350

Monthly Report–May 1953 Radiation Monitoring Services Unit

ATTACHMENT D

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Reference Description

HW-28532

SRDB 51479

Document entitled “Exposure Study of the Calibration Unit Operations,” describing an 

analysis of calibration staff radiation exposures. Radium gamma and neutron source 

dose rates are provided to allow calculation of dose based on the time involved in making 

the irradiation. On facet of this study involved evaluation of personnel film badge data for 

the first fifteen weeks of 1953 with the following observations:

1. A maximum exposure of 165 mr/week occurred on swing shift.

2. A maximum exposure of 100 mr/week occurred on day shift.

3. The average exposure for straight day employees was 12 mr/week.

4. The average exposure for shift employees on day shift was 40 mr/week.

5. The average exposure for shift employees on swing shift was 60 mr/week.

This study identified expected exposures from each of several identified radiation 

calibration tasks.

HW-28545

SRDB 37352

Monthly Report–June 1953 Radiation Monitoring Services Unit

HW-28875

SRDB 37355

Monthly Report–July 1953 Radiation Monitoring Services Unit

HW-29150

SRDB 37358

Monthly Report–August 1953 Radiation Monitoring Services Unit

HW-29471

SRDB 37360

Monthly Report–September 1953 Radiation Monitoring Services Unit

HW-29781

SRDB 37362

Monthly Report–October 1953 Radiation Monitoring Services Unit

HW-30107

SRDB 37366

Monthly Report–November 1953 Radiation Monitoring Services Unit

HW-30409

SRDB 37368

Monthly Report–December 1953 Radiation Monitoring Services Unit

HW-27194

SRDB 36973

Radiation Studies 234-5 Building (VI) Plutonium Surface Dose Rate (Jan 20). Report 

describes review of surface dose rate of 200 mrep/hr from plutonium metal based on 

unpublished measurement by Whipple and Jacobs in 1949. The 1949 measurement was 

apparently made on a coated piece. The dose rate for uncoated pieces would be 

significantly greater. This reports conclusions are: 

Table I. Plutonium surface dose rates.

Absorber

Dose rate (mrep/hr)

Coated Uncoated

Skin (7 mg/cm2) 246 (2,700)

Polyethylene glove (7 + 38 mg/cm2) 185 916

Rubber glove (7 + 113 mg/cm2) 173 795

HW-27754

SRDB 36976

Radiation Survey of Task II & III–RMA (Mar 30). This report describes a need for surveys 

of the levels of radiation encountered in Task II and III of the RMA Line and the 

contemplated reduction of allowable body dosage rates. The report specifies 

measurements to assess:

1. Requirements and shielding properties of hood walls.

2. Shielding requirements of the vessels and containers handling the product, and

3. Location of equipment which requires routine manual operation in the Zone III.

HW-27486

SRDB 367

Gamma Dose Measurement with Hanford Film Badges (Mar 23). This report describes 

using the film response characteristic response curves for the open window and shielded 

areas of the film to evaluate the dose received.

ATTACHMENT D

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Reference Description

HW-27554

SRDB 36976

Radiation Survey of Task II & III–RMA Line (Mar 30). This report identifies a need for 

using measurements of the existing RMA Line processes to establish a design bases for 

shielding new Task III RM Line equipment. Information concerning (1) the 

characteristics, level, and the rate of build-up of radiation due to contaminated materials 

collecting on the hood interiors; (2) nature and level of radiation due to the Plutonium 

Charge itself; (3) how both of the above are affected by batch size; and, (4) the 

effectiveness as a radiation shield of typical materials used in hood construction. 

HW-27570

SRDB 37810

Radiation Exposure Rates in the 222-S Process Control Laboratory (Apr 1). The 222-S 

laboratory prime role is to conduct radiochemical analysis of samples. This report 

provides a review and tabulation of potential worker exposures from handling the types of 

samples. 

HW-27814

SRDB 34259

Annual Report of the Radiological Sciences Department, 1952 (Apr 23). This report 

provides a site-wide annual radiological status report as well as for each major operating 

facility.

HW-28116

SRDB 36982

Approximation of Energy of Radiation from 240-S-151 Diversion Box (May 13). This 

report describes an investigation into the reasons for high film dosimeter measured beta 

dose not confirmed with portable instrument measurements. The reason appears to be 

associated with a lower energy photon component in association with typically significant 

beta radiation fields. Measurements were made with a so-called Trent (modified 

Tracerlab CP using a T.P. probe as the ionization chamber) instrument.

HW-28655

SRDB 73709

The Evaluation of the RMA Line Reduction Yield Basis and the Reduction Process 

(Jul 2). This document describes a study of Task III reduction efficiency in the 234-5 

Bldg. 

HW-28918

SRDB 36984

Radiation Studies for Task III Design (Aug 26). This report describes BF3 proportional 

counter measurements of PuF4 powder neutron doses using selected thicknesses of 

water, Plexiglas and masonite shielding. The work is apparently focused on Task III (i.e., 

fluorination hood) design options. 

ATTACHMENT D

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ATTACHMENT D

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Reference Description

HW-29378

SRDB 36986

Radiation Measurements for Task I Design (Sep 18). This report describes actual 

measurements of a PR Can from 231-Z with 336 grams of plutonium for comparison with 

Operations personnel photon dosage rate measurements of 150 mr/hr on the side and 

250 mr/hr on the bottom. The Trent (modified Tracerlab CP using a T.P. probe as the 

ionization chamber)

All measurements made with Trent

Center of probe distance (in.) to: Dosage rate

Edge of can Center (mr/hr)

1 10.25 101.9

2 11.25 76.5

3 12.25 54.8

3.94 13.19 45.0

5.38 14.63 33.5

9.25 18.50 18.7

14.44 23.81 10.0

18.63 27.88 6.5

HW-29443

SRDB 32558

Radiation Studies 234-5 Building (VII) Sensitivity of Nuclear Track Film to PoB and Pu-F 

Neutron sources (Sep 24). This report describes results of measurements of NTA 

sensitivity and fading to evaluate the theoretical conclusions of HW-22020. The NTA 

emulsion exhibits a sensitivity for Pu-F neutrons of 2.9 ± 0.5 tracks per 104 neutrons in 

good agreement with HW-22020. The extent of the fading for Pu-F amounts to 40% in 

one week and 60% in two weeks. Fading for Po-B amounts to about 10-15% in two 

weeks. The sensitivity and the fading are affected by the age of the film. The neutron 

fluence was determined using a BF3 long counter in a Hanson Moderator which is stated 

to have a uniform sensitivity to neutrons from Pu-F. 

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Reference Description

1954

HW-25457

SRDB 34200

“Manual of Radiation Protection Standards,” December 15, 1954 (HW 1954). This 

manual contains the latest policies for control of radioactive materials and radiation 

hazards at HAPO. These Hanford standards have been formulated from national policies 

on radiation protection, AEC requirements for control of radioactive materials, and 

working limits which have been adopted over a period of years. A series of safety factors 

were introduced as summarized in the following table. 

Class of exposure Recommended 

safety factora Source of radiation Body region

External penetrating radiation Whole body 5

Hands and forearms ~2

Feet and ankles ~2

External beta radiation Whole body 2

Hands and forearms ~2

Feet and ankles ~2

Head and neck ~2

eyes 5

Mixed radiation any Not less than 5

a. *Factors relative to the appropriate maximum permissible limit.

The application of these safety factors were used to define recommended annual dose 

working limits as follows:

Type of radiation Dose

X-Rays and gamma rays 3 R/year

Neutrons 3 rem/year

Beta particle emitters 15 rad/year

Any ionizing radiation to hands & forearms, feet 

and ankles, or head and neck (except eyes)

37.5 rem/year

Eyes 3 rem/year

HW-29047

SRDB 36988

Surface Dosage Rate Studies of Task III Feed Material (Jan 15). This report describes 

results of an investigation to evaluate the accuracy of estimates of the surface hand 

exposure from handling Task III plutonium fluoride powder concerning photon and 

neutron radiation. The report concludes that the best estimate for the surface dosage 

from 450 grams of pink colored plutonium fluoride powder contained in a Plexiglas jar 

with one-fourth inch thick walls is 4.5 rem/hr, of which 3.0 rem/hr is due to fast neutrons 

from the 19F(alpha,neutron)22Na interaction with an average energy of 0.75 MeV. Surface 

dose rates with the blue colored Pu-F powder are 3.5 rem/hr (2.0 rem/hr due to fast 

neutrons). The 1.5 R/hr photon radiation was determined to have effective energies of: 

a) 680 keV–50%, b) 50 keV–8%, and c) 17 keV–42%.

HW-30685

SRDB 37370

Monthly Report–January 1954 Radiation Monitoring Services Unit

HW-30942

SRDB 37377

Monthly Report–February 1954 Radiation Monitoring Services Unit

HW-31255

SRDB 37429

Monthly Report–March 1954 Radiological Sciences Department Radiation Monitoring 

Unit

HW-31669

SRDB 37430

Monthly Report–April 1954 Radiation Monitoring Unit Radiological Sciences Department

HW-31976

SRDB 37432

Monthly Report–May 1954 Radiation Monitoring Unit Radiological Sciences Department

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Reference Description

HW-32238

SRDB 37379

Monthly Report–June 1954 Radiation Monitoring Unit Radiological Sciences Department

HW-32571

SRDB 34314

Monthly Report–July 1954, Radiation Monitoring Unit, Radiological Sciences Department

HW-32955

SRDB 37434

Monthly Report–August 1954 Radiation Monitoring Unit Radiological Sciences 

Department

HW-33241

SRDB 37436

Monthly Report–September 30, 1954 Radiation Monitoring Unit Radiological Sciences 

Department

HW-33562

SRDB 37437

Monthly Report–October 1954 Radiation Monitoring Unit Radiological Sciences 

Department

HW-33936

SRDB 37442

Monthly Report–November 1954 Radiation Monitoring Unit Radiological Sciences 

Department

HW-34262

SRDB 37445

Monthly Report–December 1954 Radiation Monitoring Unit Radiological Sciences 

Department

HW-30464

SRDB 34271

Annual Report of the Radiological Sciences Department, 1953 (Jan 7, 1954). This report 

provides a site-wide annual radiological status report as well as for each major operating 

facility.

HW-30185

SRDB 73711

A Mathematical Approach to Surface Dosage Rate Problems (Jan 13). This document 

describes an approach to estimating the exposure rate for handling radioactive sources in 

intimate contact with the hands or other portions of the body. Often it is difficult to 

determine the exposure rates involved due to geometrical considerations of the source 

and receptor. 

HW-31522

SRDB 36996

Surface Dosage Rate Studies of Task III Feed Material (Apr 20). In an early study, the 

dosage rate from plutonium fluoride powder was questioned as being too low. This 

document reports on a follow-up evaluation. The best value for the surface dosage rate 

from 450 grams of pink colored plutonium fluoride powder contained in a Plexiglas jar 

with one-fourth inch thick walls is 4.5 rem/hr, of which 3.0 rem/hr is due to fast neutrons 

from the reaction 19F(alpha, neuron)22Na with an average energy of 0.75 MeV. The 

surface dosage rate from 450 grams of blue colored plutonium fluoride powder contained 

in a Plexiglas jar with one-fourth inch thick walls appears to be 3.5 rem/hr of which 2.0 

rem/hr is due to fast neutrons from the above reaction.

HW-32476

SRDB 26045

Neutron Measurements (I) (Jul 26). This report clarifies the primary Hanford calibration 

sources and emission rate. Dose rates are specified as follows:

RaBe: 1.6 × 10-2 mrad/hr per n/cm2-sec

PoB: 1.3 × 10-2 mrad/hr per n/cm2-sec

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Reference Description

HW-32571

SRDB 34314

Radiation Monitoring Unit, Radiological Sciences Department, Monthly Report, July 1954 

(Jul 30). Neutron film badge for the week ending 6-20-1954 indicated a definite high 

neutron exposure for an individual working in room 24. A total exposure of 405 was 

estimated which included 270 mrem of fast and intermediate neutrons, 45 mrem of slow 

neutrons and 90 mR of gamma radiation. High slow neutron pencil readings were 

detected during the week in question and recommendations were made that no other 

radiation work should be done for the rest of the week. This incident was formally 

investigated (Class II, No. 77)

300 Area General Statistics

Description June July 1954 to date

Special Work Permits 218 224 1,553

Routine and special surveys 569 455 3,602

Air samples 366 256 2,140

Skin contamination 5 5 25

July Statistics–300 Area

Description SWPs Surveys Air sampling

304, 314, 3730, 3732 Bldgs., fuel tech 7 9 1

321 Bldg., Cold Semiworks 0 10 7

325 Bldg., Radiochemistry 19 98 8

326 and 3741 Bldgs., Pile Tech. 35 83 0

327 Bldg., Radiometallurgy 117 102 147

329 Bldg., Biophysics 6 53 91

3745, 3745-A, 3745-B Bldgs., calibrations 0 1 2

Miscellaneous bldgs., 300 Area 4 68 0

Construction 26 30 0

HW-35282

SRDB 36990

Some Notes on the Surface Dosage Rate of Plutonium Metal (Apr 13). This report 

summarizes studies made on the surface dosage rate on plutonium metal during the 

previous year. It states that the assumption is made that a dosage rate of 800 mr/hr is 

assumed for buttons and for uncoated pieces.

PNNL-13524

SRDB 12856

Violent chemical reaction and fire in PFP Metallurgical Laboratory (May)

PNNL-13524

SRDB 12856

Metal turnings fire stopped Tasks IV and V for three weeks (July).

HW-32516

SRDB 378

Gamma Dose Measurement with Hanford Film Badges (Jul 21). This document 

describes dose algorithms used to determine nonpenetrating and penetrating dose with 

the Hanford film dosimeter.

HW-32492

SRDB 36999

Gamma Surface Dosage Rates From Task II Feed Material (Aug 2). This report 

describes results of an investigation to evaluate the surface dosage rate involving Task II 

feed material. A best estimate of the gamma surface dosage rate from a full boat of 

plutonium oxalate is 732 ± 54* mr/hr. The best estimate for an empty filter boat is 459 ±

133* mr/hr. For routine exposure calculations a dosage rate of 800 mr/hr is 

recommended in the report for both materials.

* one standard deviation.

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Reference Description

HW-32493

SRDB 37005

Hand Exposures During Routine Operation of the RMA Line (Aug 3). This report 

describes a summary of potential exposure to workers involved with manual manipulation 

of plutonium in several chemical states along the RMA Line. All primary jobs on the RMA 

Line are stated to have been evaluated and the upper limit (90% confidence level) of 

potential exposure for each job is tabulated.

Task II Dose (mrem)

1. Process one boat through the line 32

Task III

1. Weigh chemicals and prepare can pack

a. with no addition of turnings ~0

b. with addition of turnings 60

2. Charge the furnace 26

3. Break out the button and mark 40

4. Pickling 40

5. Stripping (chemical)

Task IV

1. Charge the furnace 16

2. Break out casting and skull disposal (note) 16

Note: If crucible fragments adhere to the casting and filing is 

required involving hand exposure, calculate exposure based on 

a surface dosage rate of 800 mrem/hr (13.3 mrem per minute)

Task V

1. Machining (does not include turning 

cleanup) 125

2. Turning recovery (cleanup)

a. with turnings going to storage 55

b. with turnings going to briquetting 45

3. Briquetting 35

Task VII

1. Coating hood operation (when using 

remote tool) ~0

2. Cleaning and polishing, testing (room 242)

a. excellent quality 30

b. good quality 55

c. poor quality ~200

3. Mating 35

4. Final polish 10

Miscellaneous Operations

1. Canning normal buttons for off-plant 

shipment 60

2. Sealing out plutonium fluoride powder 

(including hood sweepings from TASKS II 

and III)

a. **to be determined at time of job

a

HW-32494

SRDB 37002

RMA Hand Exposure (Aug 3). This is a supplement to HW-32493 with the measurement 

data provided in a series of appendices.

HW-32526 

SRDB 378

Gamma Dose Measurement with Hanford Film Badges

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Reference Description

PNNL-13524

SRDB 12856

Hydrogen explosion in RMA Line Task II Hood.

WHC-MR-0512

SRDB 474

RMA Line expansion and improvements (especially Tasks I–oxalate precipitation, II–

fluorination, and III–reduction)

HW-33533

SRDB 32278

Achievements in HAPO Radiation Monitoring, 1944 to 1954 (Sep 15). This is a review of 

radiation monitoring challenges and successes during the period of 1944-54.

HW-34365

SRDB 393

Radiation Protection in the Atomic Energy Industry–A Ten Year Review (Nov 26). This is 

a general review of personnel exposure and monitoring.

HW-25457

SRDB 27679

Manual of Radiation Protection Standards, Compiled by Radiological Sciences 

Department (Dec 15). This manual contains updates to some previously issued and 

some new procedures (see revision log at the bottom of each procedure). 

HW-34147-E

SRDB 34312

Radiological Sciences Department Report for Month of December, 1954. This routine 

monthly report provides the annual status of several monitoring activities as follow:

Description Total

Special Work Permits (SWPs) 6,425

Routine and special surveys 19,342

Air samples 18,357

Skin contamination 182

Gamma PIC 2,766,976

Slow neutron PIC 15,526

Beta/photon film badges 461,600

Neutron NTA badges 6,349

Bioassays:

Plutonium 9,063

Fission product 9,754

Uranium 3,811 22,628

1955

DUN-6888

SRDB 333

KW initial startup (January 4, 1955)

WHC-MR-0521 

SRDB 474

RG Line shuts down during January and February while Task I equipment is installed

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Reference Description

HW-35905

SRDB 34301

Annual Report of the Radiological Sciences Department, 1954 (Feb 4). This report 

provided summary statistics as follows:

Table I. Radiation incidents reported.

Year Informal Class I Class II Total

1944 5 0 3 8

1945 88 35 6 129

1946 85 39 4 128

1947 99 27 2 128

1948 126 38 2 166

1949 121 36 0 157

1950 124 20 5 149

1951 77 25 13 115

1952 130 71 12 213

1953 239 69 26 334

1954 287 76 20 383

Table II. Whole body gamma exposure summary.

Year >1 r >2 r >3 r >4 r >5 r

1944 0 0 0 0 0

1945 8 1 0 0 0

1946 8 2 0 0 0

1947 13 2 1 1 1 (6.4 r)

1948 10 2 0 0 0

1949 4 0 0 0 0

1950 3 0 0 0 0

1951 23 0 0 0 0

1952 179 22 1 0 0

1953 323 42 4 0 0

1954 372 68 16 3 1 (14.4 r)

PNNL-13524

SRDB 12856

RECUPLEX begins operation (July 1)

HW-34810

SRDB 34359

Monthly Report–January 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-35499

SRDB 37447

Monthly Report–February 1955 Radiation Monitoring Unit Radiological Sciences 

Department

HW-35979

SRDB 34283

Monthly Report–March 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-36424

SRDB 37448

Monthly Report–April 1955 Radiation Monitoring Unit Radiological Sciences Department

DUN-6888

SRDB 333

KE initial startup (April 17, 1955)

HW-36929

SRDB 37450

Monthly Report–May 1955 Radiation Monitoring Unit Radiological Sciences Department

HW-37651

SRDB 34280

Monthly Report–June 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-38333

SRDB 34364

Monthly Report–July 1955, Radiation Monitoring Unit, Radiological Sciences Department

HW-38846

SRDB 34354

Monthly Report–August 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

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Reference Description

HW-39674

SRDB 37453

Monthly Report–October 1955 Radiation Monitoring Unit Radiological Sciences 

Department

HW-40185

SRDB 34288

Monthly Report–November 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-40696

SRDB 34356

Monthly Report–December 1955, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-39558

SRDB 37079

Annual Report of the Radiological Sciences Department, Fiscal Year 1955 (Sep 23, 

1955). This report provides a site-wide annual radiological status report as well as for 

each major operating facility.

HW-40448

SRDB 34825

Dosimetry of 234-5 Manufacturing Processes–A summary of current problems (Nov 21). 

The purpose of this document is stated to be a summary of day-to-day operating 

problems of the Z Plant Radiation Monitoring Subsection. Apparently, with the new 

equipment, the HW-32493 dosage rates need to be updated. Several monitoring “rules 

of thumb” are provided as follows:

Full filter boats

CP reading on carrier Exposure rate in boat (mrem/hr)

<40 mr/hr 800

>40 mr/hr but <120 m/hr 1,500

>120 mr/hr but <200 mr/hr 3,000

>200 mr/hr To be determined

Fluoride powder

<3 inches of powder 4,500

<12 in. but >3 in 800

<3 inches of a full can pack 1,500

Uncoated metal

CP meter reading

(window closed)

Exposure rate on metal (mrem/hr)

<3 in. 3–12 in

<100 mr/hr 800 200

>100 mr/hr, <250 mr/hr 1,500 ?

>250 mr/hr, <350 mr/hr 3,000 800

>350 mr/hr To be determined

Coated metal

<12 in. 250

HW-39774

SRDB 34248

Radiological Sciences Department, Monthly Section Reports, October 1955 (Nov 4)

HW-40188

SRDB 37082

Radiological Sciences Department, Monthly Section Reports, November 1955 (Dec 5)

HW-40468

SRDB 34826

Preliminary Notes on Dosimetry Problems, Room 242, 234-5 (Dec 15).

The report describes hand and extremity exposure evaluations of an activity involving 

soot removal and rough polishing. Based on 4 studies on uncoated metal, the surface 

dosage rate on coated metal was estimated to be 400 ± 40 mr/hr based on the 

assumption the high energy photon emission will penetrate the nickel coat and the low 

energy photon components (17 keV) will not. Concern was expressed that these doses 

are about a factor of 2 higher than noted in HW-27194.

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Reference Description

1956

HW-40977

SRDB 51503

Comparison of Estimated Radiation Exposure and Film Badge Results (Jan 10). This 

document describes Hanford penetrating and beta dose limits and the practice of 

estimating the exposure to workers while waiting for the official film dosimeter result. A 

nine month study from January 1 through September 30, 1955 was conducted to 

compare estimated and recorded film badge doses for several maintenance (e.g., 

millwrights and pipefitters) and radiation monitoring staff. For all groups of workers the 

film badge measured dose was less than the estimated exposure based on workplace 

survey measurements and time-keeping.

PNNL-13524

SRDB 12856

Startup (January 12) of PUREX high product output drives production at PFP to higher 

levels 

HW-41167

SRDB 73748

N-1 Tank Neutron Studies, 231 Building (Jan 27). This report concerns data collected 

with a enriched BF3 tube enclosed in a standard moderator mounted as close as 

practicable to the bottom of the N-1 Tank, cell 4, 231 Bldg. This was done because of a 

suspicion of buildup of plutonium on a filter in the tank. Meaningful measurements for 

this purpose were collected when the tank was empty because otherwise the tank 

contents tended to shield the neutrons.

HW-41209

SRDB 34296

Monthly Report–January 1956, Radiation Monitoring Unit, Radiological Sciences 

Department

HW-41704

SRDB 37455

Monthly Report–February 1956 Radiation Monitoring Unit Radiological Sciences 

Department

HW-42297

SRDB 37457

Monthly Report–March 1956 Radiation Monitoring Unit Radiological Sciences 

Department

HW-42710

SRDB 58383

Monthly Report–April 1956 Radiation Monitoring Unit Radiological Sciences Department

HW-43438

SRDB 37459

Monthly Report–May 1956 Radiation Monitoring Unit Radiological Sciences Department

HW-44009

SRDB 37461

Monthly Report–June 1956 Radiation Monitoring Unit Radiological Sciences Department

HW-44588

SRDB 37463

Monthly Report–July 1956 Radiation Monitoring Unit Radiological Sciences Department

HW-45153

SRDB 37465

Monthly Report–August 1956 Radiation Monitoring Unit Radiological Sciences 

Department

HW-45736

SRDB 37382

Monthly Report–September 1956 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-46368

SRDB 37385

Monthly Report–October 1956 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-47107

SRDB 37388

Monthly Report–November 1956 Radiation Monitoring Operation Hanford Laboratories 

Operation

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Reference Description

05-26-09

File 006001-1

SRDB 67521

Exposure Evaluation and Records Monthly Report, November 1956. Routine report 

regarding site-side status. A summary of 18 incidents is provided. The effort to replace 

the two-element personnel dosimeter with the multielement badge was apparently 

underway. The report identifies an unresolved issue concerning the interpretation of 

dose for 234-5 staff compared with the Chemical Processing Department staff. This is 

anticipated to involve issues associated with primarily a primarily low and higher energy 

photon radiation field (234-5) with issues of mixed beta and photon fields (processing 

facilities). There is a reference to a new program to remove PICs from workers who do 

not normally work or enter radiation zones. The number of pencils assigned during 

November 1956 was about 18% less than assigned during October 1956 and 8% less 

than the 1956 monthly average to date. This report also describes an effort to prepare 

computer input cards that contain the total beta and gamma exposure from 1944 through 

the first nine months of 1956 for all operational with current active clearance and 

construction employees for input to the new IBM database. This effort was being made 

so that the IBM database system could maintain a total accumulated dose for each 

Hanford worker on a current basis.

05-26-09

File 006001-2

SRDB 67522

Exposure Evaluation and Records Monthly Report, December 1956. Routine report 

regarding site-side status. This report provides a summary of year-end 1956 dosimetry 

processing totals as follows:

Pencils

1956 total 100-280 mr >280 mr Lost readings

3,615,432 233 231 164

Beta/gamma filma

1956 total 100-300 mr 300-500 mr >500 mr Lost readings

668,863 10,532 330 172 634

Slow neutron pencils

1956 total 4-12 mrem >12 mrem Lost readings

12,586 460 63 30

Fast neutron film (NTA) badges

1956 total >12 mrem Lost readings

10,025 11 25

a. It was also noted that for 1956 total films (668,863) that the average open 

window dose was 3.39 mrad while the average shielded dose was 3.29 mr. 

(This implies are comparatively penetrating photon energy on average).

HW-47657

SRDB 37389

Monthly Report–December 1956 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-41233

SRDB 37090

Radiological Sciences Department Section Reports for January 1956 

HW-41702

SRDB 53072

Radiological Sciences Department Report for Month of February 1956 (Mar 5)

HW-42219

SRDB 53073

Radiological Sciences Department Report for Month of March 1956 (Apr 6)

HW-41369

SRDB 34828

Further Notes on the Surface Dosage Rate of Plutonium Metal (Feb 20). This report 

describes the history of Hanford surface dosage rate measurements on plutonium metal 

and the range in measurement results. The author describes an estimate of the average 

dosage rate of uncoated plutonium metal as between 1066 and 1322 mr/hr based on 400 

CP readings that show wide variations in the measured dosage rate. This dosage rate is 

through 110 mg/cm2 of tissue equivalent absorber.

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Reference Description

HW-41439

SRDB 34830

Surface Dosimetry and Effective Energy Calculations, (Sep 8). This report provides a 

more detailed examination of the surface dosage rate from plutonium metal with several 

attenuation curves provided in the report, estimation of workplace energy spectra and 

account in the dosage rate for instrument energy response. The estimated “true’ dosage 

rate is 817 mr/hr. Tables of reference data are provided at the end of the report to be 

used in examining 4 typical workplace exposure scenarios.

HW-42195

SRDB 58385

Technical Document entitled “Beta and Gamma radiations from PUREX Produced 

Plutonium,” identifying the presence of significant beta emitting nuclides in plutonium 

product. (May 28, 1956)

PNNL-13524

SRDB 12856

Uncontrolled chemical reaction occurred (May) in RMA TASK I.

HW-42626

SRDB 34290

Radiological Sciences Department Report for Month of April 1956 (May 4)

HW-43345

SRDB 34831

Exposures in 234-5, Room 242 (May 23). Report provides brief summary of radiation 

exposures received by personnel performing normal operations in room 242, 234-5 

building as follows: 

Operations

Exposure per 

piece (mrem)a

1. Spot removal, whisker removal, cleaning and 

preliminary testing.

24

2. Polishing, cutting to weight, gauging and marking 13

3. Electrolytic testing 8

4. Final polishing. 8

a. Value is the upper 95% level in that 95% of the time the long-term average 

exposure will be this value or less.

HW-43448

SRDB 37006

Surface Dose Rates from plutonium Metal (Jun 1). This report is one of a series 

concerning surface dosage rate studies on fabricated and unfabricated plutonium metal. 

Values are valid for REDOX produced plutonium (and might not be appropriate for 

PUREX, please see HW-42195) as follows:

Metal from 

Task III

Probability is that the surface dosage rate from this form of metal 

is between 1,246 and 2,154 mr/hr with a most likely value of 

1,638 mr/hr. In addition, the probability is 95% that 90% or more 

of the time the surface dosage rate on an individual item will be 

below 4,923 mr/hr.

Metal from 

Tasks IV and V

Probability is 95% that the surface dosage rate from this form of 

metal lies between 1,027 mr/hr and 1,224 mr/hr with a most likely 

value of 1,121 mr/hr. In addition, the probability is 95% that 90% 

or more of the time the surface dosage rate on an individual item 

will be below 1,540 mr/hr.

Metal from 

Task VII

Probability is 95% that the surface dosage rate from this form of 

metal lies between 311 mr/hr and 405 mr/hr with a most likely 

value of 355 mr/hr. In addition, the probability is 95% that 90% or 

more of the time the surface dosage rate on an individual item will 

be below 622 mr/hr.

HW-43137

SRDB 34309

Radiological Sciences Department Report for Month of May–1956 (Jun 4)

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Reference Description

HW-43784

SRDB 37009

Past Exposure Problems in 234-5 Room 242 (Jun 20). Report one of a series to 

complete the record of exposure problems in room 242, 234-5 Building. The studies in 

this report were made during production. This report is a supplement to HW-32493, HW32494, HW-40468 and HW-43345. Exposures per operation are presented in report for 

each operation in this room. It was noted that substantially less exposure is received by 

an experienced technician as compared to an inexperienced technician. All exposures in 

report were based on the latest best estimate of a surface dosage rate from coated 

plutonium, 355 mr/hr (see HW-43448).

HW-43938

SRDB 34305

Radiological Sciences Department Report for Month of June–1956 (Jul 6). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc.

HW-43979

SRDB 34307

Radiological Sciences Department Section Reports for June–1956 (Jul 6). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc.

HW-43811

SRDB 37013

Effective Energies of Radiations from Pu Metal (Jun 22). Report provides a brief 

summary of the effective energies from fabricated and unfabricated plutonium metal. 

Energies are valid for REDOX produced plutonium but at the time of the report could not 

be interpreted as valid for PUREX produced plutonium (Report is a supplement to HW41369 and HW-43448).

Unfabricated Metal

Effective energy Surface dosage rate

Average 95% confidence limits

Task

Average 95% confidence limits

keV Upper Lower mr/hr Upper Lower

18.1 18.6 17.6 III 745 786 708

IV 745 786 708

59.2 63.1 55.3 III 152 297 78

IV 119 168 84

616 658 575 III 568 769 336

IV 259 317 211

Fabricated Metal (from Task VII)

Effective energy Surface dosage rate

Average 95% confidence limits Average 95% confidence limits

kev Upper Lower mr/hr Upper Lower

62 65 59 83 108 63

500 540 460 243 254 232

PNNL-13524

SRDB 12856

T-Plant separation operation terminated (Aug)

HW-44580

SRDB 34303

Radiological Sciences Department Report for Month of July–1956 (Aug 6). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc.

HW-44706

SRDB 34304

Radiological Sciences Department Section Reports for July–1956 (Aug 6). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc.

HW-44836

SRDB 34833

234-5 Exposures in Task V, Hoods 200A&B (Aug 9). Report provides a summary of 

radiation exposures received by personnel performing machining operation at Hoods 200 

A & B. Using standard 30 gauge neoprene hood gloves with an average density 

thickness of 110 mg/cm2

, an exposure of 60 mrem per piece should be used for routine 

exposure accountability purposes. Note: This exposure does not include the sanding 

operation. Exposure received for the sanding operation is received at an average rate of 

20 mrem/minute, and should be determined by clock or stop watch each time this occurs. 

Using lead impregnated gloves reduces the exposures.

ATTACHMENT D

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Page 43 of 82
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Reference Description

HW-44934

SRDB 37016

Exposures in Task V, Part II (Aug 17). Report provides a summary of radiation 

exposures received by personnel performing cleanup and briquetting operation at Hoods 

200 A & B and the briquetting hood, 234-5 Building. Using standard 30 gauge neoprene 

hood gloves with an average density thickness of 110 mg/cm2

, an exposure of 35 mrem 

per operation should be used for routine exposure accountability purposes for the 

cleanup and briquetting operation. Note: This exposure does not included exposure 

received while placing burned turnings into a bottle. Exposure for this step is received at 

an average of 20 mrem/minute, and should be determined by clock or stop watch each 

time this occurs. When Edmont Glove Company lead impregnated plastic gloves are 

installed in all glove ports the exposure rate is reduced to 12 mrem per operation.

HW-45142

SRDB 34788

Exposures in Task IV 234-5 Building, Part I (Aug 31). Dosimetry of Plutonium 

Fabrication–Interim Report (Oct 2). Report provides a summary of radiation exposures 

received by personnel performing 1) the Task IV furnace loading and 2) the Task IV 

furnace unloading. Using standard 30 gauge neoprene hood gloves with an average 

density thickness of 110 mg/cm2

, an exposure of 35 mrem per operation should be used 

for routine exposure accountability purposes for the Task IV furnace loading operation 

when crucibles are double stacked. An exposure of 35 mrem per operation should be 

used for routine exposure accountability purposes for the Task IV furnace unloading each 

casting. This does not include sealing out skulls.

HW-45114

SRDB 34293

Radiological Sciences Department Section Reports for August 1956 (Sep 7). 

HW-45115

SRDB 34292

Radiological Sciences Department Report for Month of August–1956 (Sep 7). This is 

stated to be the last routine monthly report by the Radiological Sciences Department. 

These responsibilities are apparently assumed by the Radiation Protection Operation 

under the Hanford Laboratory.

HW-45472

SRDB 37879

The Feasibility of Processing Pocket Ionization Chambers on a Weekly Basis (Sep 10). 

This report describes a study involving 83 pairs of pencils issued in three groups as 

follows: 1) 55 pairs to 303 area workers, 2) 13 pairs to 3705 Bldg workers and 3) 15 

pairs set aside as controls. Pencils were charged and issued for weekly periods and 

read about 7.5 days later. More than 50% of the paired readings were zero while the 

highest was 35 mr. Only 4 pencils read more than 100 mr and three of these were off 

scale. The program of weekly processing is concluded to be feasible. 

HW-45674

SRDB 36496

Hanford Irradiation Processing Department issued “Radiation Control Standards and 

Procedures” manual dated December 14, 1956. This manual describes numerous 

routine radiation safety functions pertaining to workplace controls, measuring and 

recording exposures to workers, and applicable exposure limits.

ATTACHMENT D

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Page 44 of 82
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Reference Description

HW-45600

SRDB 34789 

Dosimetry of Plutonium Fabrication–An Interim Report (Oct 2). Report provides a 

summary of radiation exposures authorized for routine exposure accountability on 

portions of the RMA Line.

Location and operation Exposure (mrem)

Room 242

1. Soot removal, whisker removal cleaning and 

preliminary testing 27 142

2. Polishing, cutting to weight, gauging, and 

marking 14 —

3. Electrolytic testing 8 10

4. Mating — 43

5. Final polishing 8 27

Task V

1. Machining, without leaded gloves 63

Machining, with leaded gloves 43

2. Sanding 20 mrem per minute

3. Cleanup and briquetting 35

Task IV

1. Loading furnaces 35

2. Unloading furnaces 35 mrem per casting

HW-46522

SRDB 34366

Radiological Protection Operation Report for Month of October 1956 (Nov 9). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc. 

HW-46023

SRDB 34790

Exposures in Task VII, 234-5 Building (Oct 12). Report provides a summary of radiation 

exposures received by personnel performing 1) the Task VII coating hood loading, and 2) 

the Task VII coating hood unloading operations. Using standard 30 gauge neoprene 

hood gloves with an average density thickness of 110 mg/cm2

, an exposure of 5 mrem

per piece should be used for routine exposure accountability purposes for loading the 

coating hoods. Using a minimum of surgical gloves with an average density thickness of 

15 mg/cm2

, an exposure of 4 mrem per piece should be used for routine exposure 

accountability purposes for loading the coating hoods.

HW-46068

SRDB 34791

Exposures in Task V, Part III-190 (Oct 15). This report evaluates radiation exposures 

received by personnel performing machining operation. Using standard 30 gauge 

neoprene hood gloves with an average density thickness of 110 mg/cm2

, an exposure of 

77 mrem per operation should be used for routine exposure accountability purposes. 

Please note this exposure does not include the sanding and cavity cleaning operation. 

Exposures for sanding and cleaning cavities are received at a rate of 20 mrem/minute 

and should be determined by clock or stop watch each time this occurs. When lead 

impregnated plastic gloves equivalent to those manufactured by the Edmont Glove 

Company are used at the glove ports for planar surface machining, exposure of 50 

mrem/piece should be used. 

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

Page 45 of 82
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Reference Description

HW-46383

SRDB 34792

Exposures in Task III, Part I (Oct 31). Report provides a summary of radiation exposures 

received by personnel performing the button knockout and pickling operation, Task III. 

Using standard 30 gauge neoprene hood gloves with an average density thickness of 

110 mg/cm2

, an exposure of 16 mrem per button should be used for routine exposure 

accountability purposes for knocking out and pickling one button. Please Note: This 

does not include removal of the button from the pickling solution, inspection, weighing 

and storage. This data will be included in a second report to be issued as soon as the 

data are compiled.

For purposes of definition, the steps involved in knocking out and pickling one button are:

1. Remove crucible and button from hopper

2. Hold button and remove fragments with hammer

3. Pick up fragments and put into hopper.

4. Transfer button to pickling hood.

HW-46401 

SRDB 34793

Surface Dosage Rate Problems From Task III and Task IV Wastes (Nov 1).

Report describes the most recent Surface Dosage Rate (SDR) problems from Task III 

and IV crucible fragment cans with the goal to prepare for RECUPLEX Operations. The 

report provides a description of estimating the gamma and neutron dose rates from single 

CP or BF3 measurements, respectively. The gamma dosage rate in mr/hr on cans of 

waste materials from Tasks III and IV can be estimated from the equation

Gamma SDR = 8 (CPR),

Where the CP reading is the window open dial reading. The neutron surface dosage rate 

in mrem/hr on cans of waste material from Tasks III and IV can be estimated from the 

equation

Neutron SDR = (16) (mrem/hr at contact)

There apparently is no correlation with the CP reading. The gamma activity on Task IV 

fragments appears to have a half-life of approximately 157 days.

HW-46449

SRDB 34794

Exposure Studies, 234-5 Building, Book II (Nov 5). Document contains many pages of 

original measurement data that is difficult to interpret.

HW-46507

SRDB 34795

Exposure in Task II (Nov 9). This report describes measurements of exposures received 

by personnel performing all phases of routine Task II operations. Using standard 30 

gauge neoprene hood gloves with an average density thickness of 110 mg/cm2

, an 

exposure of 35 mrem per boat should be used for routine exposure accountability 

purposes for all routine operations in Task II. Details were provided as follows:

Exposure per boat per job step, Task II

Step

Mean

(mrem)

95% C.I., interval 

(mrem) Variance 

Upper Lower (log)

1. Stir fluoride powder 1.2 1.9 0.8 0.10173

2. Stir oxalate 8.4 13.5 5.2 0.11970

3. Put empty boat in 

bathtub

5.0 7.4 3.3 0.08043

4. Place boat on door 5.2 7.3 3.8 0.06270

5. Change o-ring or inspect 

as required

9.6 27.0 3.5 0.33564

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

Page 46 of 82
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Reference Description

HW-46508

SRDB 34796

Exposure in Task III, Part II, Exposures in Task IV, Part II, Waste Material (Nov 12). This 

report describes measurements of exposures received by personnel performing the sealout operations for Task III and Task IV crucible fragments. Using standard 30 gauge 

neoprene hood gloves with an average density thickness of 100 mg/cm2

, an exposure of 

7 mrem per can should be used for routine exposure accountability purposes for sealing 

one can of crucible fragments in Tasks III or IV. For purposes of definition, the steps 

involved in sealing out one can of crucible fragments are:

1. Place lid on can and tape

2. Place can in plastic bag

3. Seal out and number

4. Survey

5. Transfer to storage box.

HW-46688

SRDB 49315

A New Neutron Dosimeter–Its Calibration and Use in Shield Evaluation (Dec 18). This 

report describes a neutron dosimeter consisting of a paraffin-moderated enriched BF3

proportional counter that has been developed by the Hanford Physics and Instruments 

Operation. Calibration has been made for all available neutron energies and 

approximates the dose response quite well except for intermediate energy neutrons. 

Modifications for field use are described as well as the program for shield evaluation tests 

using this instrument. The instrument appears to be satisfactory for neutron dose 

measurements of all types except for small beams.

HW-46697

SRDB 5156

Penetration of Gamma Ray Secondaries (Sep 28). Technical report of radiation 

penetration in media used to examine response of X-ray film response to photons of 

different energies.

HW-46774

SRDB 34797

Exposure in Task III, Part III (Nov 20). This report describes radiation exposures 

received by personnel performing the last part of the pickling operation, Task III. Using 

standard 30 gauge neoprene hood gloves with an average density thickness of 110 

mg/cm2

, an exposure of 12 mrem per button should be used for routine exposure 

accountability purposes for completing the pickling operation and transfer to storage, 

Tasks III.

HW-46775

SRDB 37018

Exposures in Task IV, Part III (Nov 20). This report provides a summary of radiation 

exposures received by personnel while removing buttons from cans and preparing the 

metal for firing, Task IV. Using standard 30 gauge neoprene hood gloves with an 

average density thickness of 110 mg/cm2

, the following exposures should be used for 

routine exposure accountability purposes.

1. Place cans in hood 9 mrem per operation, regardless 

of the number of cans

2. Open can, remove button from 

plastic

10 mrem per button

3. Transfer to train, pick up 

briquettes, transfer and weigh

7 mrem per weighing, regardless 

of the number of buttons weighed 

at one time.

HW-46776

SRDB 34798

Summary for HW-48000, Dosimetry of Plutonium Fabrication (Nov 20). This report 

contains only the table shown under HW-48000.

HW-47230

SRDB 34310

Radiological Protection Operation Report for Month of November 1956 (Dec 11). This 

report provides site wide radiation monitoring statistics, incident descriptions, etc. 

Weekly assignment of pencil dosimeters was initiated. 

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

Page 47 of 82
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 165 of 265

Reference Description

HW-48000 

SRDB 34799

The Dosimetry of Plutonium Fabrication–Terminal Report (Nov 27). This report reviews 

the history of plutonium surface dosage rates from the earliest available information 

through the present. The method for the determination of the surface dosage rate on 

plutonium is given, as well as tests to detect significant changes in exposure rates. The 

tests are based on simple measurements with the CP radiation monitoring instrument. 

The exposure received for performing a given operation is presented for every operation 

which involves significant radiation. The following Table presents the recommended 

values for routine exposure calculations.

Activity Description Dose

Task I

1. All operations Based on total time and 

average background.

Task II

1. Complete processing for one boat 35 mrem per boat

Task III

1. Charge furnace No significant exposure

2. .... 16 mrem per button

3. ..., Monitor, inspect, store 12 mrem per button

Task IV

1. Charge double stacked furnace 35 mrem per furnace

2. Unload double stacked furnace 35 mrem per casting

3. Unload triple stacked furnace 57 mrem per furnace

4. Remove overflow plutonium (use stopwatch) 20 mrem per minute

5. Uncan. buttons charging to furnace

a. Place cans in hood 9 mrem per operation

b. Open can, remove button from plastic 10 mrem per button

c. Transfer to train, ..., weigh 7 mrem per weighing

Tasks III and IV

1. Seal out.....fragments 7 mrem per can

Task V

1. Machining, no leaded gloves 60 mrem per piece

2. Machining, leaded gloves only 40 mrem per piece

3. Machining, ... no leaded gloves 77 mrem per piece

4. Sanding (use stop watch) 20 mrem per minute

5. Cleanup and briquetting 35 mrem per briquette

a. Cleanup only 16 mrem per operation

b. Briquetting only 20 mrem per briquette

Task VII

1. Charging a coating hood... 5 mrem per piece

2. Unloading a coating hood, transport to 

Room 242

4 mrem per piece

3. All other hood work not involving plutonium 

metal

No significant exposure

Room 242

1. Soot removal, experienced operator 12 mrem per piece

2. Soot removal, average, inexperienced 

operator

24 mrem per piece

3. Polishing, experienced operator 11 mrem per piece

4. Polishing, experienced operator 14 mrem per piece

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

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Reference Description

Activity Description Dose

5. Polishing, inexperienced operator 14 mrem per piece

6. Lapping 2 mrem per piece

7. Electrolytic testing 8 mrem per piece

8. Final polishing 8 mrem per piece

Room 192, final Inspection (See HW-46443 and HW-46449)

1. Preliminary screening 15 mrem per piece

2. Initial and final alpha count.. 0.6 mrem per piece per 

operation

3. Electrolytic testing 9 mrem per piece

4. Gauging 12 mrem per piece

5. Magna gauging 3 mrem per piece

6. Radioaudiography 5 mrem per piece

7. Neutron counting 0.9 mrem per piece

8. Final numbering 10 mrem per piece

9. Final packaging 0.5 mrem per piece

10. Radiography 0.7 mrem per piece

RECUPLEX

1. Remove material from storage and charge 

dissolver (HW-4650 F)

19 mrem per charge

HW-64716 RD

SRDB 

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

September 1956 Through June 1957.

1957

PNNL-13524

SRDB 12856

231-Z Building ends it original “isolation” plutonium processing mission (Jan)

HW-47655

SRDB 73750

RMC Line Flowsheet–Tasks I, II and III (Jan 2). This report provides a flowsheet to be 

used in scoping Tasks I, II, and III of the new RMC Line. For Tasks I and II, the flow 

rates and concentrations are the same as specified for the continuous Tasks I and II. For 

Task III, the flowsheet is essentially the same as the one now in use on the RMA Line 

and reflects only minor changes in chemical additions and waste losses.

WHC-MR-0521 

SRDB 474

Project GC-691 Continuous Tasks I-II equipment installed in RMA Line achieving a 

continuous calcination/hydrofluorination process that essentially combined the flow of 

Tasks I and II.

HW-48045

SRDB 37391

Monthly Report–January 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-48817

SRDB 37393

Monthly Report–February 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

SRDB 15396 Letter “Exposure Problem 234-5 Building,” (Feb 12). History of using factor of 20% of the 

open window to increase assigned deep dose from low-energy photon fields 

characteristic of plutonium. Letter from AR Keene to GE Backman. 

HW-49437

SRDB 37394

Monthly Report–March 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-50586

SRDB 37395

Monthly Report–May 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-51753

SRDB 37397

Monthly Report–July 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-52849

SRDB 37398

Monthly Report–September 1957 Radiation Monitoring Operation Hanford Laboratories 

Operation

ATTACHMENT D

HISTORICAL TIMELINE OF RADIATION EXPOSURE ASSOCIATED EVENTS AT HANFORD

Page 49 of 82
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 167 of 265

Reference Description

HW-48741

SRDB 34604

Radiological Protection Operation Report for Month of February 1957 (Mar 8). This 

report provides site wide radiation monitoring statistics, incident descriptions, etc. Report 

describes process of converting film badge data to electronic data processing and the 

practice of checking master records for any errors. The report also states that a program 

of placing multiple dosimeters at selected locations on the body was started with a group 

of Radiation Monitoring Operation staff to evaluate the distribution of exposure over the 

body.

HW-48751

SRDB 15402

Weekly Processing of Pencil Dosimeters (Apr 15). This report provides results of a study 

of 450 workers who wore pocket ionization chambers (pencils) on a weekly basis. The 

study was conducted in the 300 Area. Pencil results are compared with results of daily 

processed pencils from another group of randomly selected employees. Comparisons 

with both daily pencil results and corresponding badge films showed that weekly 

processing of pencil results in a program of near equal reliability with a better dose 

measurement than does daily processing. 

HW-49854

SRDB 34607

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–April 

1957 (Apr 30). This report provides site wide radiation monitoring statistics, etc.

HW-50298

SRDB 73751

Design Scope of the RMC Button Line (May 24). The purpose of this document is to 

detail the design scope of the RMC Button Line. The proposed installation consists of 

installing Task I, II and III equipment in the RG area of the 234-5 Building. The process 

equipment is planned to be installed behind an operational barrier constructed of 

Plexiglas and steel. Equipment is planned to generally be operated remotely from the 

Zone I area.

HW-50339

SRDB 34368

Radiation Protection Operation Report for Month of May 1957 (Jun 10). This report 

provides site wide radiation monitoring statistics, incident descriptions, etc. 

HW-51189

SRDB 34608

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–June 

1957 (Jun 28). This report provides site wide radiation monitoring statistics, etc.

HW-51317

SRDB 26046

Surface Dose From Plutonium (Jul 10). The technical report describes an examination of 

the surface dose rate from plutonium metal for variations in reactor exposure and 

provides a technical basis for estimating the dose for any relative isotopic composition.

HW-51783

SRDB 37881

A Scintillation Fast Neutron Exposure Rate Meter (Jan 8). A scintillation fast neutron 

exposure rate meter has been developed to give a flat response from 1.0 MeV to at least 

5.2 MeV fast neutrons with a reading error over this range of ± 10 per cent. 

HW-51934 

SRDB 15409

Reproducibility of Personnel Monitoring Film Densities (Jul 25). This document reports 

on an examination of personnel and calibration film processed during the previous 13 

years (beginning in 1944). No indications of any immediate problems in film density 

fading were apparently observed. Variations between the original and reread optical 

densities were considered reasonable for all calibration levels. Generally fluctuations 

were 10% or less with occasional differences of 30 to 40%. More variation was noted in 

readings for personnel film with some errors detected as a result of misreads of the film 

density originally or in posting results; however, all obvious errors detected occurred prior 

to 1950. 

HW-52325

SRDB 5166

Energy Discrimination in Gamma Dose Evaluation (Nov 18). This report describes a 

study of dose evaluation for film packets given controlled doses of X- and Gamma-ray 

exposures from 16.1 to 170 keV, and 1,000 keV, respectively. 

HW-53465

SRDB 34610

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

October 1957 (Oct 31). This report provides site wide radiation monitoring statistics, etc.

ATTACHMENT D

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Reference Description

HW-53515

SRDB 61205

A Study of Zinc Impregnated Rubber Overlay Hood Gloves for Shielding Effectiveness 

(Nov 7). A study was done which showed an approximate 50% reduction in the surface 

dose rate using a hood glove with a 10 ml zinc impregnated rubber overlay compared to 

the standard 30 gauge neoprene hood gloves with an average density thickness of 

110 mg/cm2. 

HW-54027 

SRDB 34614

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

November 1957 (Nov 27). This report provides site wide radiation monitoring statistics, 

etc.

HW-54242

SRDB 53752

Shielding Requirements for the RMC Button Line Process Technology Study Report 

(Dec 3). Shielding in the RMC Button Line to be constructed has a design requirement of 

< 1 mrem/hr in the Zone 1 Operating Gallery, and from 8 to 10 mrem/hr in Zone 3. 

Shielding requirements for the RMC Button Line were evaluated using improved radiation 

measuring instruments on existing comparable process hoods in 234-5. These 

measurements showed that neutron exposure is approximately equal to that of gamma 

exposure. The radiation levels from process hoods under maximum operating conditions 

which result in some build up of radioactive materials within the hoods will require 

additional shielding to achieve a radiation exposure level of < 1 mrem/hr in Zone 1. The 

measured dose data are shown in the following table.

RMC hood

Equivalent 

RMA hood

Doses at hood walls from RMA 

and 691 hood readings (mrem/hr)

Neutron Gamma Total

HC 6 H-5 1 5 6

HC 7 H-5 3 10 13

HC 9 (top)

HC-9B

15 50 65

HC 9 (center) 25 40 65

HC 9 (bottom) 20 25 45

HC 10 H-9W 50 10 60

HC 11 16 CS 60 15 75

HC 12 S H-11 15 8 23

HC 13 MD H-13 MD 20 8 28

HC 15 (A, B C) H-13 10 8 18

HC 16 CC 14 CC 10* 10 20

HC 17 DC 14 DC 40* 10 50

HC 17 P 14 P 25* 10 35

HC 17 B 15 B 10* 5 15

HC 18 BS 16 BS 25* 10 35

HC 42 H-41 0 2 2

Maint hood Rm 170 hood 0.3 3 3.3

* Higher than would exist on RMC hoods if movement of powder 

into these hoods is prohibited.

HW-54408

SRDB 34617

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

December 1957 (Dec 31). This report provides site wide radiation monitoring statistics, 

etc.

HW-55384

SRDB 34801

Z-Plant Radiation Study Interim Report on

Special Process Sampling Program (Mar 20)

HW-55463

SRDB 34802

Z-Plant Radiation Study Special Sampling

Program Interim Report #2 (Mar 27)

HW-56102

SRDB 34803

Z-Plant Radiation Study Special Sampling Program Interim Report #3 (May 21).

ATTACHMENT D

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HW-57358

SRDB 34805

Z-Plant Radiation Study Special Sampling

Program Interim Report #4 (Sep 5)

Reference Description

PNNL-13524

SRDB 12856

RMA Hood 9B placed into operation (Aug)

HW-64718-RD

SRDB 64561

Radiological Engineering Management Report, December 13, 1957. Report contains 

information stating “Effective January 1, 1958, IPD’s method for issuing pocket 

dosimeters (pencils) will change. Pencil meter post boxes will be set up at strategic 

locations in the 105 buildings and personnel will only be required to wear pencils while in 

radiation zones. Pencils will continue to be read on a daily basis, thus retaining the 

purpose they serve of flagging a high daily dose which is not otherwise known. The 

number of dosimeters issued and processed will be appreciably reduced.”

HW-54408

SRDB 34617

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

December 1957 (Dec 31). This report provides site wide radiation monitoring statistics, 

etc. The removal of contaminated equipment from the main floor of the Plutonium 

Metallurgy Facility Expansion was completed and installation of new equipment is 

underway. Year to date statistics provided as follows:

Description Year-to-date

Special Work Permits 31,191

Routine and special surveys 26,231

Air samples 27,933

Skin contamination 207

Year to date exposure investigations were summarized as follows:

Description Year-to-date

Radiation occurrences 132

Potential overexposures 12

Technical overexposures 2

PNNL-13524

SRDB 12856

Near criticality in RMA Hood 9B (Nov)

1958

HW-51783

SRDB 37881

A Scintillation Fast Neutron Exposure-Rate Meter (Jan 8)

HW-54844

SRDB 34618

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

January 1958 (Jan 31).

HW-55169

SRDB 34619

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

February 1958 (Feb 28). 

HW-55537

SRDB 34620

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–March 

1958 (Mar 31). 

HW-55907

SRDB 34621

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–April 

1958 (Apr 30).

ATTACHMENT D

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Reference Description

HW-54997

SRDB 50842

Preliminary Project Proposal, Reduction of Radiation Exposure, RMA Line 234-5 

Building. (May 15). This document contains an analysis of current exposure conditions 

associated with proposal to improve shielding between Zone I and III process areas 

along Tasks I through IV hoods. The current combined neutron and gamma exposure 

levels of 1 to 5 mrem per hour along Tasks I through IV in the RMA Zone 1 (lowest level 

radiation area) operating aisle makes it possible for personnel to exceed the exposure 

limit of 5 rem per year without leaving the Zone I area, so corrective action is necessary. 

At that time, essentially all the neutron radiation is due to alpha-neutron reaction of the 

plutonium compound contained in the Task II and III operation. A second source of 

neutrons is from spontaneous fission of the several isotopes of plutonium which will 

become a more troublesome neutron contributor with the highly exposed power reactor 

fuels. Higher fuel exposures will also increase the quantity of gamma contributors in the 

plutonium product. Radiation exposures will increase with higher plutonium throughput 

as a result of increases in reactor power level.

HW-56205

SRDB 34622

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–May 

1958 (May 29).

HW-56550

SRDB 34623

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–June 

1958 (Jun 30). This report describes routine radiation monitoring statistics and includes 

results of a neutron survey of 231.

HW-56211

SRDB 52241

Hood 9B Nitrate Feed Tank Monitoring Studies (Jun 2). This document describes 

gamma measurements of unusual feed material with abnormally high fission product 

zirconium and ruthenium contamination.

HW-58054

SRDB 37401

Monthly Report–October 1958 Radiation Monitoring Operation Hanford Laboratories 

Operation

PNNL-13524

SRDB 12856

RMA Hood 9A placed into operation (Jul)

HW-57293

SRDB 49324

Double Moderator Neutron Dosimeter (Jul 15). This document describes the 

J. DePangher developed dosimetry method that became widely used. A history of 

previous neutron dosimetry methods is provided. The Double Moderator Neutron 

Dosimeter uses a moderated BF3 detector and used for measuring fast neutron dose, 

flux and average energy. The instrument consists of a “fluxmeter” and a “dosimeter” was 

calibrated with monoenergetic neutrons from accelerator and nuclide sources. The ratio 

of the fluxmeter and dosimeter responses provides a measure of the average energy of 

the neutron spectrum. The system was being used in Hanford workplaces.

HW-56378

SRDB 37885

Slow and Fast Neutron Scintillation Count-Rate and Dose-Rate Meter (Aug 1)

HW-57283

SRDB 69972

Technical report entitled “Revised Fission Product Specification for Z-Plant Feed from 

Purex,” (August 29, 1958) describing a revised fission product specification for plutonium 

nitrate feed received at Z-Plant from PUREX to limit the amount of fission product gamma 

(due mainly to 95Zr and 103-106Ru) exposure to PFP workers.

HW-57716

SRDB 33188 

Shielding Basis for high exposure Pu Button Line–Part I Gamma (Oct 20)

HW-58093

SRDB 32560

Shielding Basis for high exposure Pu Button Line–Part II Neutron (Nov 10)

DOE/RL-97-1047

SRDB 27666

Additional shielding installed around RMA Line to reduce personnel exposures

DOE/RL-97-1047

SRDB 27666

Design of Plutonium Reclamation Facility 232-Z Incinerator construction begun

HW-64714

SRDB 36861

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

October 1958 to June 1959 (Oct 31). This is a collection of several monthly reports from 

Oct 1958 through June 1959.

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Reference Description

1959

PNNL-13524

SRDB 12856

PFP RMC Line construction completed (Jul)

HW-56827

SRDB 26047

Technical document entitled “A Personnel Film Badge Neutron Dosimeter,” issued that 

describes features of the Hanford personnel neutron dosimeter (May 15, 1959). This 

dosimeter has thermal neutron capability using Sn and Cd filters and also a fast neutron 

dose capability using NTA film.

HW-60620

SRDB 73753

Technical document entitled “Gamma Energy Analysis of the RMA Line and 

RECUPLEX,” dated June 15, 1959. Measurement results were consistent with 

theoretical expectations. Gamma energies were measured at 7 levels ranging from 17 

(Pu) keV to 750 (Zr) keV. Energy levels of 17, 60, 100, 200 and 380 keV associated with 

Pu were prevalent at all RMA measurement locations.

HW-60699

SRDB 58403

Technical document entitled “Estimate of Gamma Dose Rates from 1000 MWD/T and 

2000 MWD/T Plutonium,” dated June 22, 1959. 

HW-60905

SRDB 60597

Technical report dated June 30, 1959 concerning accuracy of extremity dose from 

plutonium. Report notes that the dose is being under-estimated and suggest use of a 

correction factor of 5.8. 

DDTSGENERATED-933

SRDB 36552

Monthly Report–June 1959 Radiological Engineering Unit

HW-60225

SRDB 37403

Monthly Report–April 1959 Radiation Monitoring Operation Hanford Laboratories 

Operation

SRDB 31747 Measured NP dose ratios included in attachment to October 19, 1962 letter from P. E. 

Bramson to C. M. Unruh regarding NP ratios for identified specific 234-5 locations 

included in May 13, 1959 letter from V. P. Madsen to L. M. Knights.

HW-61041

SRDB 51252

Neutron Emission Rate Measurements on the Plutonium Compounds Common to 234-5 

Building (Jul 13). Document presents measured neutron emission rate from plutonium 

compounds of nitrate, oxalate, and oxide, and metal present at 234-5.

HW-64713 RD

SRDB 64502

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–July 

1959 Through June 1960 (Jul 1959).

HW-61140

SRDB 51173

Review of Radiation Shielding Requirements and Exposure to Operators, RMC Button 

Line, Project COC-734 ( Jul 15). This report provides an overall analysis of potential PFP 

worker exposure for handling the higher irradiated reactor fuel. There is an analysis of 

measured gamma doses and also the application of NP dose ratios hood by hood.

Total Zone IIII Gamma Exposure (r/yr)

Hood

650 MWD/T 2000 MWD/T

None 1⁄4” X-ray 1” HD None 1⁄4” X-ray 1” HD

HC-6 14 6.3 2.2 18.4 7.0 2.4

HC-7 4 0.8 0.2 7.0 1.4 0.3

HC-9B 32 3.6 0.7 46.2 6.1 1.1

HC-12S/16CC 1 0.1 — 1.8 0.2 —

HC-17DC 6.5 0.5 0.1 11.2 1.1 0.1

HC-17P/18RS 2.5 0.5 0.1 3.7 0.9 0.2

Total 60.0 11.9 3.3 88.3 16.7 4.1

HW-61358

SRDB 51253

Estimated Effects of Variations in Plutonium Isotopic Concentrations on HAPO Personnel 

Exposures as Measured by Film Badges. (Sep 24). This document provides several 

formulas to calculate surface and penetrating dose from plutonium isotopes. The 

document uses this information to forecast future doses to workers from blends of higher 

exposed plutonium fuel in reference to 1958 film measured doses.

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Reference Description

HW-61755, Part I

SRDB 34845

Z-Plant Radiation Study Interim Report #5–

Part I Possibilities for Reducing NPR Gamma Dose Rate, Pt 1 (Oct 22). This document 

contains substantial information concerning neutron and photon dose rates. The report 

states “plutonium fluoride which has a high neutron flux from alpha-neutron reaction was 

found to be by far the most difficult process material in Z-Plant to shield for gamma 

radiation. Measurements of dose rates with routine survey instruments showed twice as 

much lead to be required to reduce gamma radiation from fluorides than was required for 

any other plutonium compounds including the metal. An explanation of this behavior is 

presented in Figure IF. It shows that with fluorides gamma reduction is governed by 

attenuation of 1.27 MeV and the 2.1 MeV components of the fluoride gamma energy 

spectrum. These two high gamma energies were observed in all fluoride, but in no other 

samples.” The 1.27 MeV gamma is produced by Na-22 when it decays to Neon-22. The 

Na-22 is formed from the fluorine atom when it absorbs an alpha particle and produces a 

neutron. The 2.1 MeV gamma is attributable to neutron captures by hydrogen to form 

deuterium.

HW-61755 Part II

SRDB 34846

Z-Plant Radiation Study Interim Report #5–

Part II, Data on Gamma Shielding of Special Plutonium Samples (Oct 22)

HW-62589

SRDB 34669

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

October 1959 (Oct 30). 

HW-62873

SRDB 34670

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

November 1959 (Nov 30). 

HW-63308

SRDB 34671

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

December 1959 (Dec 31). Year to date statistics were provided as follows:

Description Year-to-date

Special Work Permits 23,995

Routine and special surveys 20,546

Air samples 30,069

Skin contamination 106

Year to date 1959 exposure investigations were summarized as follows:

Description Year-to-date

Radiation occurrences 23

Potential overexposures 15

Technical overexposures 4

1960

HW-63710

SRDB 34672

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

January 1960 (Jan 29).

SRDB 26050 Letter report dated June 10, 1960 to file containing results of Intersite Personnel 

Dosimeter Intercomparison Study for workplace plutonium radiation fields (photon only) 

among Hanford, SRS, LANL and RFP. 

HW-64086

SRDB 34673

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

February 1960 (Feb 29). 

HW-64156

SRDB 74648

Design Study Interim Report: RMA Button Line Radiation Reduction (Apr 1)

The purpose of this design study was to develop new design concepts for handling and 

processing high exposure plutonium from the nitrate through the button stage and to 

prepare design criteria to form the basis for design and construction of a new facility. A 

detailed discussion and description of each process function is provided in Appendix I of 

the report.

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Reference Description

HW-65047

SRDB 73755

Technical report entitled “Interim Product Specification for Z Plant Feed from Purex,” May 

9, 1960) regarding Z Plant radiation control consideration for radiation levels near the 

button processing equipment.

HW-66675

SRDB 34848

Technical report entitled “Predicted Z Plant Radiation Exposure Levels vs. Plutonium 

Isotopic Concentration of Products,” regarding relationship between WB exposure levels 

encountered in Z Plant versus the plutonium isotopic concentration of the product.

HW-25457, Rev 2

SRDB 27679

Manual of Radiation Protection Standards, Hanford Atomic Products Operation, General 

Electric Company, March 1, 1960. This manual contains updates to some previously 

issued procedures (see revision log at bottom of procedures) and also some new 

procedures. Appears to be major revision of HW-25457 issued December 15, 1954.

Occupational External Exposure Standard

Occupational exposure as a result of ionizing radiation from a source external to the body 

shall not exceed:

1. 5 rems multiplied by the number of years between the person’s age and age 18, 

including not more than 3 rems in any 13 consecutive weeks, to the whole body, 

head and trunk, blood-forming organs, eyes or gonads due to radiation of 

sufficient penetrating power to affect a significant fraction of the critical organ;

2. 10 rems multiplied by the number of years between the person’s age and age 18, 

including not more than 8 rems in any 13 consecutive weeks, to the skin of a 

major portion of the body, due to radiation of very low penetrating power (half 

value less than 1 mm of soft tissue); 

3. 75 rems per year, including not more than 25 rem in any 13 consecutive weeks,

to the hands, forearms, feet and ankles.

Hanford Operational External Exposure Control

The control of external exposure is primarily achieved at HAPO through the personnel 

meter program. Therefore, the following exposure limitations are to be applied by facility 

management to assure that HAPO Radiation Protection Standards are met:

1. The “whole-body dose”, evaluated through the personnel meter program shall not 

be permitted to exceed 1 rem in any regular four-week badge period, or 5 rems 

including 3 r in any calendar year.

2. The “skin dose”, evaluated through the personnel meter program shall not be 

permitted to exceed 2 rems in any regular four-week badge period, or 10 rems in 

any calendar year.

3. The “extremity dose”, evaluated through the personnel meter program shall not 

be permitted to exceed 8 rems in any regular four-week badge period, or 40 rems 

in any calendar year.

Application of the four-week badge period shall be such that the Occupational External 

Exposure Standard limits above are not exceeded. 

HW-64591

SRDB 34674

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–March 

1960 (Mar 31).

HW-64979

SRDB 34675

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–April 

1960 (Apr 29).

HW-65153

SRDB 34847

Scope Basis–Shielding–Plutonium Reclamation Facility Project CAC-880 (May 9).

HW-65441

SRDB 34676

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–May 

1960 (May 31).

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Reference Description

SRDB 26050 Wilson letter report dated June 10, 1960 regarding Inter-Site comparison to plutonium 

irradiations conducted at Hanford. Hanford, Savannah River, Rocky Flats and Los 

Alamos participated in the study. Each site evaluated their dosimeters which were 

simultaneously exposed at Hanford. 

HW-65946

SRDB 34677

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–June 

1960 (Jun 30).

HW-66675

SRDB 34848

Predicted Z Plant Radiation Exposure Levels versus plutonium isotopic concentration of 

Products (Aug 19)

HW-66280

SRDB 34678

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

December 1960 (Dec 30).

HW-66861

SRDB 34849

Gamma Shielding Calculations for Slag and Crucible Fragment Handling–Plutonium 

Reclamation Facility Project CAC-880 (Sep 27)

HW-71702

SRDB 37787

Technical report entitled “Gamma Calibration and Evaluation Techniques for Hanford 

Beta-Gamma Film Badge Dosimeters.” (Sep 1960). This report describes many of the 

operational techniques and experience in using the Hanford multielement beta/gamma 

dosimeter implemented during 1957. The document was apparently prepared as part of 

a Film Dosimeter Information Exchange held at Hanford during September 20-22, 1960 

with representatives from Argonne, Oak Ridge, Los Alamos, Savannah River, Rocky 

Flats, Idaho Falls, University of California at Berkeley, Hanford AEC and Hanford Atomic 

Products Operations. 

HW-66979

SRDB 34680

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

September 1960 (Sep 30).

RMC Line hot operations begun (Oct)

HW-67248

SRDB 34681

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

October 1960 (Oct 31).

HW-67642

SRDB 34682

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

November 1960 (Nov 30).

HW-SA-1933

SRDB 24381

Analysis of the Distribution of Externally Received Radiation at Hanford, 1944-59 

PNNL-13524

SRDB 12856

PRTR begins (Nov. 21) operation in 300 Area.

HW-67982

SRDB 34683

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

December 1960 (Dec 30). Year to date statistics provided as follows:

Description Year-to-date

Special Work Permits 27,377

Routine and special surveys 19,566

Air samples 35,095

Skin contamination 112

Year to date exposure investigations were summarized as follows:

Description Year-to-date

Type A occurrences 0

Type B occurrences 0

Type C occurrences 33

1961

HW-68352

SRDB 34684

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

January 1961 (Jan 31).

HW-68706

SRDB 34685

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–

February 1961 (Feb 28).

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Reference Description

HW-69039

SRDB 34686

Radiation Monitoring Operation, Hanford Laboratories Operation, Monthly Report–March 

1961 (Mar 31).

HW-SA-2140

SRDB 32561

Reproducible Precision Polyethylene Long Counter For Measuring Fast Neutron Flux 

(Apr 3) 

HW-69817

SRDB 37406

Monthly Report–May 1961 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-69650

SRDB 60071

Technical report entitled “Impurity Levels in Plutonium Nitrate to Yield Acceptable Metal 

By Direct Calcination, Hydrofluorination, and Bomb Reduction,” regarding average fission 

product specification for zirconium and ruthenium to preclude excessive button radiation.

HW-SA-2182

SRDB 52831

Document entitled “Radiological Development Within the Hanford Laboratories Radiation 

Protection Program,” presented at the annual Health Physics Society Meeting during July 

13-16, 1961. Paper describes general characteristics of Hanford dosimetry capabilities 

as follows: “An assessment of personnel dosimeter capabilities indicates that Hanford’s 

personnel dosimeter utilizing a 1 mm sterling silver shield as the primary shield for 

interpretation of gamma dose performs well for gamma energies between 0.200 and 2 

MeV. A given dose between 0.1 and 1 R at any energy or from a mixture of energies in 

this range can be interpreted routinely within ±10% at better than the 95% confidence 

interval. For similar exposure for gamma energies between 0.050 and 0.200 MeV, the 

interpretation is not as satisfactory. Our recent studies have shown that a tantalum shield 

or a tungsten shield of the appropriate thickness and when encased in plastic can give a 

nearly linear film density response for a given gamma dose in the energy range from 

0.050 and 2 MeV. The actual deviation from a linear density response is about ±10%. 

For low energy about 17 to 50-keV X-ray or gamma ray doses in the range from 0.1 to 1 

R, our present dose interpretation capabilities, on a routine bases, might be limited to 

about ±50%, and the presence of a few tenths of a rad of beta radiation further limits the 

accuracy of the low energy dose interpretation. The use of an iron filter and two plastic 

filters of appropriate thicknesses has resulted in more accurate interpretation of these low 

energy gamma doses and has extended the dose evaluation capabilities to low energy 

gamma doses in the presence of beta radiation.

HW-71353

SRDB 49327

An Automated Reader for Personnel Dosimeter Films (Nov 8). This document describes 

the development of the Hanford automated film reader system.

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Reference Description

1962

HW-68023

SRDB 36923

Development of Gamma and Neutron Radiation Data for Three Alternate Design 

Concepts for the Plutonium Reclamation Facility (PRF), Project CAC-880 (Jan 4).

The focus of this document was to evaluate three options for design of the Plutonium 

Reclamation Facility. The RECUPLEX facility was considered to be the most 

representative of conditions anticipated in the recovery of plutonium. Photon spectra 

were analyzed and showed substantial photon contribution from plutonium fission product 

contaminants that contributed substantial photon exposure compared to plutonium 

photon radiation particularly for higher exposed fuel. Measurements at the 234-5 

RECUPLEX Facility are summarized in Table F of the report and were used as a basis in 

the analysis of PRF Design Options. A selection of measurements from Table F are 

shown below.

Distance 

from 

hood (ft)

Dose rate (mr/hr)a

R B hood S E hood S C hood

Gamma Neutron Gammab Neutron Gamma Neutron

At hood 37 0.9 90 0.3 31 3.3

1 27 30 0.2 12 2.0

2 21 19 6

3 17 0.2 4 1.2

4 14 14 3

5 11 2

6 9 2

7 7 2

8 6 2

a. Measurements 3-24-60.

b. Measurements 3-2-60.

PNNL-13524

SRDB 12856

232-Z Incinerator begins operations (Jan 5)

HW-75546

SRDB 29140

Dosimetry Investigation of the RECUPLEX Criticality Incident.

HW-71764

SRDB 37788

Technical report entitled “A Personnel Dosimeter Filter System for Measuring Beta and 

Gamma Doses in Mixed Radiation Fields,” (March 1962). This report describes details of 

dose interpretation using the 1962 Hanford beta/photon film dosimeter system. Based on 

studies of mixed field beta radiation exposures from uranium and low-energy photon 

exposures from plutonium metal, and also k-fluorescent irradiations, interpreted doses 

were within ±10% of the given doses.

HW-70032

SRDB 52282

Evaluation of Fixed Radiation Monitoring Instrumentation for use in IPD (Jun 27). 

Evaluation of instruments used as fixed detectors in Hanford reactors.

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Reference Description

HW-72315

SRDB 74143

Document entitled, “NPR Shield Review,” (Jan 16). This document describes the 

shielding features of the N Reactor under construction according to five protective zones 

as follows:

Zone 1 which is adjacent to the charge face, the discharge face, and the top of the 

reactor. No access is possible to this zone during operation. Monitored access is 

possible during reactor shutdown. This zone is operated at a negative pressure relative 

to Zone 2.

Zone 2 which includes secondary radiation areas such as the inner and outer rod rooms, 

the gas system, the flux and rupture monitor room, the ball system, and the ventilation 

exhaust system from Zone 1. Normally, no access to the restricted areas of zones 2 will 

be required during operation but limited emergency access is possible. Zone 2 is 

operated at a negative pressure relative to Zone 3.

Zone 3 is a normal access or buffer zone which will have free access at all times except 

perhaps for quite abnormal conditions. This zone includes most of the work regions and 

corridors around the reactor in which metal handling and other routine operations will be 

conducted.

Zone 4 is an unlimited access area with essentially no radiation during normal operations.

Zone 5 is defined as a warranted access area in which continuous access is maintained 

at all time including emergencies. Zone 5 is limited to the main control room and the 

main instrument room beneath the main control room. 

HW-73212

SRDB 37425

Monthly Report–March 1962 Radiation Monitoring Operation Hanford Laboratories 

Operation

SRDB 31745 Letter from LM Knights to JJ Courtney entitled “Personnel Exposure to Neutrons–Button 

Line,” dated April 6, 1962. This letter describes use of a neutron to photon dose ratio of 

1:1 (i.e., NP ratio of 2) to control worker dose because of the time lapse involved in 

receiving neutron dose for the processed dosimeters.

HW-74811

SRDB 37426

Monthly Report–August 1962 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-75697

SRDB 37427

Monthly Report–November 1962 Radiation Monitoring Operation Hanford Laboratories 

Operation

HW-76050, HAN84031

SRDB 446

N Reactor Department Monthly Report December 1962

HW-76944

SRDB 5230

Technical Report entitled, “The New Hanford Film Badge Dosimeter” (Mar 1, 1963). This 

report describes the technical features of the improved beta gamma dosimeter 

implemented at Hanford on August 10, 1962. This dosimeter provides for the evaluation 

of radiation dose from beta, gamma and X-ray radiations present independently or 

concurrently. Activation foils provide neutron dosimetry in the event of a criticality or 

similar radiation event. Two small silver phosphate glass rod dosimeters (fluoride) are 

included to provide measurement of high gamma dose. Indium foil is provided for prompt 

sorting of directly-involved personnel following a criticality event. 

HW-81037 

SRDB 54563

Weapon Manufacturing Operation, Radiation Control Report, 1962 and 1963

1963

HW-SA-2904

SRDB 51219

Hanford Plutonium Fuel Development Laboratory (Feb 13). This document describes the 

worker exposure experience of the 308 Plutonium Fabrication Pilot Plant (PFPP) after 4 

years of operation. The document provides an analysis of hazards associated with the 

plutonium isotopes handled at Hanford. 

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Reference Description

HW-77295

SRDB 52814

Radiation Protection Aspects of the RECUPLEX Incident of April 7, 1962 (May)

PNNL-13524

SRDB 12856

RMC Line Fire in Room 227 Glovebox (Nov)

HW-81037

SRDB 54563

Weapon Manufacturing Operation, Radiation Control Report, 1962 and 1963

Date

Instrument measurements

Hoods 

7C-9B 

gamma 

(mR/hr)

Hoods 

7C-9B 

neutron 

(mrem/hr)

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma, 

(mR/hr)

Button 

line 

neutron

(mrem/hr)

Button, 

instr. 

NP ratio

Jan-63 3.6 24.5 6.8 1.5 4.8 3.2

Feb-63 4.6 18.6 4.0 1.9 3.6 1.9

Mar-63 5.1 21.6 4.2 1.0 4.2 4.2

Apr-63 4.8 21.6 4.5 1.5 4.2 2.8

May-63 4.6 NA 1.8 5.1 2.8

Jun-63 4.1 NA 2.0 4.2 2.1

Jul-63 5.7 NA 1.6 6.3 3.9

Aug-63 5.6 NA 1.9 3.0 1.6

Sep-63 5.0 NA 1.5 4.0 2.7

Oct-63 2.4 NA 1.1 2.7 2.5

Nov-63 5.2 NA 2.4 3.6 1.5

Dec-63 6.0 NA 1.3 4.7 3.6

HW-77071

SRDB 52813

Preliminary Engineering Report, Replacement and Improvement of Fixed Radiation 

Monitoring Instrumentation. Discussion of project to upgrade fixed instrumentation in 

Hanford reactor facilities.

HW-77077

SRDB 73757

Document entitled, “Acceptance and Startup Testing of N Reactor Plant.. ( Mar 26) ). 

This document generally describes the anticipated testing of the N Reactor regarding 

physics, operation and power ascension.

HW-77093

SRDB 51210

A Method of Measuring Integrated Thermal Neutron Exposure (Mar 22). Document 

describes a method to measure the integrated thermal neutron exposure in a reactor 

core.

SRDB 4829 Hanford External Dosimetry Operations, Operating Procedures (1963). Document 

contains routine external dosimeter procedures to prepare, issue, process and calibrate 

Hanford dosimeters. Procedures 2.6 and 2.7 describe thermal and fast neutron 

interpretation, respectively. For example, the Hanford Neutron Film Badge Dosimeter 

contains two shield areas. These consist of an opposed pair of cadmium shields 0.040” 

thick and an opposed pair of tin shields of the same thickness. These shields have very 

nearly equal absorption of gamma rays over a wide energy range. However, the tin 

shield is essentially transparent to thermal neutrons, while the cadmium shield has a very 

high thermal neutron cross-section. ...The difference in optical density, between these 

two filtered regions of the film, is directly related to the thermal neutron exposure. 

HW-77335

SRDB 52815

Technical Criteria for Reactor Radiological Monitoring Systems (Apr 22). Document

provides technical basis for the design of the production reactor radiological monitoring 

systems.

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Reference Description

HW-77917 PT1

SRDB 73758

Document entitled, “Startup Test N-1–Procedures, N Reactor Startup Physics Test 

Program, Cold Physics Tests (Nov 22).” This document describes on page 74 an 

evaluation of radiological hazards at several locations known to have some potential. 

Testing is done under conditions to maximize readings. All possible beams must be 

surveyed and the areas properly marked to prevent unnecessary exposure in the vicinity 

of the beams. Recoil reflects must be surveyed at the confinement walls. 

HW-77937

SRDB 73759

RMC Button Line Radiation (Jun 7)

In 1960, the RMC Button Line was equipped with a 1) water wall shield between the front 

and rear side and 2) a one-inch high density (HD) glass shielded gloveboxes. Several 

studies were done to compare worker dose rates particularly with consideration of 

processing higher exposed fuel. This document presents the average personnel 

exposure for the button line from 1959 to 1962. The data clearly shows reduction in the 

photon exposure from the one-inch HD shielded gloveboxes. Measured average doses 

for 33 operators in 1962 are: 1,422 mR/yr photon and 1,657 mrem/yr neutron with a ratio 

of 1.16. For 1961, the corresponding doses are: 1,200 mR/yr photon and 1,243 mrem/yr 

neutron with a ratio of 1.03. These measured values are for fuel exposures of 500 

MWD/ton. The paper presents analyses of extrapolated exposures for handling 

plutonium from 2,000 MWD/ton exposed fuel.

AECM 0524

SRDB 13037

AEC Manual 0524, “Standards for Radiation Protection,“ issued with several 

requirements for radiation monitoring and records. Dose limits specified for external 

radiation follow: 

Radiation Protection Standards for External Exposure

Type of exposure Condition

Dose (rem) or 

dose commitment 

(rem)

(Prospective annual limit) Whole body, 

head and trunk, gonads, lens of the eye, 

red bone marrow, blood forming organs

Year

Calendar quarter

5

3

(Retrospective annual limit) Type of 

exposure same as above

Accumulated dose 5 (N-18)

Unlimited areas of skin (except hands 

and forearms). Other organs, tissues 

and organ systems

Year

Calendar quarter

15

5

Forearms Year

Calendar quarter

30

10

Hands Year

Calendar quarter

75

25

WHC-SP-0297

SRDB 64586

N Reactor begins initial fuel loading on December 16 and achieves initial criticality on 

December 31, 1963.

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Reference Description

1964

HW-78500

SRDB 38343

N Reactor Radiation Protection and Procedures (January 1). This document states the 

Hanford exposure standards dose limits and the operational controls as follows:

HAPO Exposure Standards

Occupational exposure as a result of ionizing radiation from a source external to the 

human body shall not exceed:

1. 5 rem multiplied by the number of years between the person’s age and age 18, 

including not more than 3 rem in any 13 consecutive weeks to the whole body, 

head and trunk, active blood-forming organs, lens of the eyes, or gonads, due to 

radiation of sufficient penetrating power to affect a significant fraction of the 

critical tissue;

2. 10 rem multiplied by the number of years between the person’s age and age 18, 

including not more than 6 rem in any 13 consecutive weeks to the skin of the 

major portion of the body, due to radiation of very low penetrating power (halfvalue less than 1 mm of soft tissue);

3. 75 rem/year, including not more than 25 rem in any 13 consecutive weeks to the 

hands, forearms, feet or ankles.

Operational Controls

The following exposure limitations will normally be applied throughout NRD to assure that 

JAPO Radiation Protection Standards are met:

1. The WB penetrating dose should not be permitted to exceed 1 rem in any regular 

four-week badge period, or 5 rem including 3 r in any calendar year.

2. The WB skin dose should not be permitted to exceed 2 rem in any regular four 

week badge period, or 10 rem in any calendar year.

3. The extremity dose should not be permitted to exceed 8 rem in any regular four 

week badge period, or 40 rem in any calendar year.

4. Application of the four-week badge period shall be such that the basic HAPO 

exposure standards above are not exceeded.

If planned work will cause personnel to exceed an exposure check point(s), the 

responsible supervisor shall, before work begins:

1. Complete all sections of the appropriate “Personnel Exposure Request” form. 

These forms are required for:

• Exposure over 300 mrem, but less than 500 mrem in 7 days (A-5000-832).

• Exposure over 500 mrem in 7 days (A-5000-830).

• Exposure over 3 rems per year (A-5000-830).

2. Submit the completed form to Radiation Monitoring for review (if required on the 

form).

Acquire from Environmental Engineering, the current radiation exposure status for each 

individual listed on the form.

ORAUT-TKBS0006-2234-5Z RMA Line shutdown in 1964. Glovebox reactivated in 1967. Tasks I-III were 

cleaned out and reactivated in 1968. Line placed on standby in 1984.

DOE/RL-97-1047 

SRDB 27666

Pu Reclamation Facility (PRF, 236-Z) hot processing begun (May)

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Reference Description

HW-83246

SRDB 60049

Technical report entitled “Button Line Process Over-All Impurity Decontamination (July 

29, 1964)” use of spectrographic analyses of each hood 6 plutonium nitrate feed batch to 

develop a new specification for button line feed solutions.

HW-79746

SRDB 73762

Document entitled, “N Reactor Start-Up Test N-2, Low Power Testing Program,” (Jan 20). 

This document describes on page 72, radiation survey requirements as stated “The Low 

Power Testing Program includes the first increases in reactor power level above 1 MW. 

To monitor the shielding adequacy and detect any unforeseen radiation beams, a 

complete building radiation survey is included in each test step calling for special data. 

These steps are as follows:

Step Power level (MW)

4 0

11 100

13 200

17 300

19 400

HW-82366

SRDB 57442

Document entitled “Measurement of the Radiation Intensity Streaming Through The NPR 

Steam Vent Shield Penetration and an Analysis of the Proposed Steam Vent Shielding,.” 

(May 24). This document describes significant dose rates of gamma and neutron 

radiation emerging below the steam vent penetrations. The N Reactor steam vent 

penetrations are located in the bottom shield of the reactor and open to the southeast 

and southwest corners of the ball hopper retrieval system. On April 29, Hanford 

Laboratories personnel were called in to instrument these penetrations to determine the 

gamma and neutron radiation intensities. Shielding design changes were evaluated to 

achieve the following:

Radiation

Transmitted dose 

(R/hr)

Gamma rays 9.5

Fast neutrons 0.2

Resonance neutrons 0.5

Thermal neutrons 1.4

HW-82272

SRDB 73762

Document entitled, “Startup Test N-2 Low Power Testing Program, Preliminary Summary 

Report,” (May 26). This document describes status of neutron leakage found (see HW82366) to have a higher than expected neutron level during reactor operation. The cause 

on investigation was neutron streaming down the steam vent piping provided at two 

locations to permit venting of steam from a process tube rupture. Corrective action was 

required for purposes of radiation protection and to reduce the possibility of neutron 

activation of system components in the ball recovery room. The action consisted of 

adding a pipe offset to achieve a labyrinth design and to provide additional shielding. 

HW-82452

SRDB 36920

Critical Mass Control Specification–Recycling of Non-standard Powders–Hoods 9-A and 

HC-9B (Jun 1). This report identifies critical mass specifications for the recycling of 

nonstandard powders through the calciner and fluorinator in hoods 9-A and HC-9B. This 

specification sets forth supplemental conditions to HW-66936 Rev (Hood 9-B) and HW76553 (9-A) under which powder might be recycled. 

HW-81363

SRDB 50800

Radiological Control Experience with Plutonium Fuels (Mar 26). This document 

describes the worker exposure experience of the 308 Plutonium Fabrication Pilot Plant 

(PFPP) after 4 years of operation. The document provides an analysis of hazards 

associated with the plutonium isotopes handled at Hanford (seemingly identical to HWSA-2904, dated 2/13/63). 

ATTACHMENT D

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Reference Description

PL 88-376 Public Law 88-376 passed by Congress on July 14, 1968 giving official recognition to the 

NCRP to provide radiation protection guidance and changed its name slightly to the 

National Council on Radiation Protection and Measurements.

UCRL-12199 

SRDB 6180

Angular Dependence of Eastman Type A (NTA) Personnel Monitoring Film. This 

document recommends using a correction factor of 1.3. 

DDTSGENERATED-988 

SRDB 34775

Monthly record report 01/1964 radiological engineering unit

DDTSGENERATED-989 

SRDB 34776

Monthly record report 02/1964 radiological engineering unit

DDTSGENERATED-990 

SRDB 34777

Monthly record report 03/1964 radiological engineering unit

DDTSGENERATED-991 

SRDB 34778

Monthly record report 04/1964 radiological engineering unit

DDTSGENERATED-992 

SRDB 36444

Monthly record report 05/1964 radiological engineering unit

DDTSGENERATED-993 

SRDB 34779

Monthly record report 06/1964 radiological engineering unit

DDTSGENERATED-994 

SRDB 34780

Monthly record report 07/1964 radiological engineering unit

DDTSGENERATED-995 

SRDB 34781

Monthly record report 08/1964 radiological engineering unit

DDTSGENERATED-996 

SRDB 34782

Monthly record report 09/1964 radiological engineering unit

DDTSGENERATED-997 

SRDB 34783

Monthly record report 10/1964 radiological engineering unit

DDTSGENERATED-998 

SRDB 34784

Monthly record report 11/1964 radiological engineering unit

DDTSGENERATED-999 

SRDB 34785

Monthly record report 12/1964 radiological engineering unit

RL-GEN-1768 

SRDB 74140

Basic hazards information

HW-83681 

SRDB 74142

N reactor status report 50 percent power

HW-NUSAR-81580

SRDB 73768

Startup test N3 N Reactor power ascension program

HW-NUSAR-81580

SRDB 73768 

Startup test N3 N Reactor power ascension program

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DDTSGENERATED-988 

SRDB 34775

Monthly record report 01/1964 radiological engineering unit

DDTSGENERATED-989 

SRDB 34776

Monthly record report 02/1964 radiological engineering unit

DDTSGENERATED-990 

SRDB 34777

Monthly record report 03/1964 radiological engineering unit

DOE/DP-0137

SRDB 12292

PFP produces first reactor-grade plutonium product (see Figure 1).

RL-SEP-376

SRDB 54564

Weapon Manufacturing Operation, Radiation Control Report, 1964

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

Gamma

Button 

line 

Neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-64 4.8 10.5 2.2 1.5 3.4 2.3

Jun-64 5.3 16.6 3.1 1.3 3.1 2.4

Sep-64 5.1 18.2 3.6 1.1 4.1 3.7

Dec-64 5.3 18.6 3.5 0.9 4.4 4.9

Film dosimeter measurements

Mar-64 2.5 5.0 2.0 0.5 2.0 4.0

Jun-64 2.8 6.1 2.2 0.8 1.7 2.1

Sep-64 3.1 6.8 2.2 0.5 2.2 4.4

Dec-64 2.9 6.8 2.3 0.5 1.4 2.8

PFP produces its first nondefense plutonium for EURATOM

USPHS 

Performance 

testing,

SRDB 15021

The National Sanitation Foundation initiates performance testing of “Standards of 

Performance for Film Badge Services” during December 1964. The types and numbers 

of organizations that submitted film badges for this testing included:

Commercial 12

Federal agencies 8

State health departments 4

Private 1

Approximately 2,000 film badges were irradiated with various types and energies of 

radiation. Exposures ranged from 0.002 to 497 Roentgens. The dosimetry services did

not know which badges were exposed to what type, energy, or dose of radiation.

HW-SA-4000

SRDB 50809

The Administration of Radiation Safety at Hanford (Dec 28). Broad discussion of Hanford 

Radiation Protection Program. Annual doses controlled to 5 rem including 3 R photon 

dose. Establishment of workplace Zones 1 to 4. Monitoring conducted for all workers 

and visitors entering radiological controlled areas.

HW-84600

SRDB 36446

Document entitled “Hanford Periodic and Serial Reports 1943-1964, A Book Catalog,” 

issued (December 1964). This 300 page document lists numerous report series by 

general category.

WHC-SP-0297

SRDB 64586

N Reactor achieves 4000 MWt design operating level on December 9, 1964 following 

approximately one year of system testing.

DUN-6888

SRDB 333

DR Reactor was shut down for deactivation (December 30, 1964)

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Reference Description

1965

DOE/RL-97-1047

SRDB 27666

Battelle memorial Institute assumes Pacific Northwest Laboratory contract effective 

1/1/1965 to technically direct Hanford personnel dosimetry services such as WB counter, 

personnel dosimetry, radiological calibrations, etc., in addition to general research and 

development.

HW-82536

SRDB 73765

Document entitled, “Final Report, startup test N-2, Low Power Testing Program Steps 13 

and 18,” (Jan 15). This document presents an example of the extensive tests conducted 

and includes references to numerous test results.

DOE/RL-97-1047

SRDB 27666

US Testing assumes Hanford contract to provide radiochemical analyses and personnel 

dosimeter processing services. 

DOE/RL-97-1047

SRDB 27666

Douglas United Nuclear (DUN), November 1965 to August 1967 assumes responsibility 

for Hanford reactor operations and fuel fabrication.

BNWC-8-1

SRDB 64808

Battelle-Northwest Monthly Activities Report, January 1965 (Feb 15). Report describes 

Battelle-Northwest assumption of Hanford Site personnel dosimetry and environmental 

surveillance responsibilities from General Electric effective January 4, 1965. Report also 

describes role of U.S. Testing Company to conduct personnel dosimetry processing, 

bioassays and environmental radiochemical analyses effective January 1, 1965. 

BNWC-8-2

SRDB 64810

Battelle-Northwest Monthly Activities Report, February 1965 (Mar 15). Report describes 

highlights of Hanford Site dosimetry support. As noted in this report a new 1000 gram 

plutonium fluoride neutron source was obtained. The new source is doubly contained 

with an inner can of monel material and an outer can of aluminum. The monel inner 

container was chosen to provide maximum inertness to fluorine. The air space of 

approximately 1/8 inch is provided between the two containers so that X-ray examination 

can be used to detect any possible source swelling of the inner container. The higher 

density monel metal has significantly reduced the gamma radiation dose rate from this 

source. Also, the recent purification of the plutonium used has resulted in a source with a 

minimum of 241Am. Gamma radiation rates from this source will increase as the 241Am 

increases. 

DUN-6888

SRDB 333

H Reactor was shut down for deactivation (April 21, 1965)

Letter Report

SRDB 73677

Field Evaluation of Badge, Pencil Dosimeter, and CP Response. This report dated April 

1, 1965 compares 3 film dosimeters, 3 Victoreen pencils, 3 Bendix pencils, and 6 

Stephens pencils under three different field conditions. The pencils indicated an average 

exposure about 25% higher than the film dosimeter dose.

PNNL-13524

SRDB 12856

Am-241 recovery begun at 242-Z facility (May)

DUN-6888

SRDB 333

F Reactor was shut down for deactivation (June 25, 1965)

RL-REA-2247

SRDB 73773

Historical report issued entitled, “Historical Events–Reactors and Fuels Fabrication,” 

(July 1, 1965). The stated purpose of this report is to document, in one place, the 

significant historical events pertinent to the operation of the production reactors at 

Hanford. 

BNWC-8-9

SRDB 64813

Battelle-Northwest Monthly Activities Report, September 1965 (Oct). Report describes 

highlights of site-wide dosimetry support. An update to Hanford participation in the AEC 

Health and Mortality Study was provided. “Work on the Mancuso Project is continuing 

both at Hanford and Pittsburgh, Pennsylvania. At Hanford the identification of 

approximately 10,000 payroll numbers used during the early portion of the data 

processing program with the names of employees was initiated. At Pittsburgh the 

independent audit of approximately 20,000 personnel film was initiated. Approximately 

one million calibration films were shipped for use in this project.”

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Reference Description

RL-SEP-820

SRDB 34155

Thorium and N Reactor Technical Record

BNWC-8-10

SRDB 64815

Battelle-Northwest Monthly Activities Report, October 1965 (Nov). Report describes 

highlights of site-wide dosimetry support. There is a description of a study involving 

neutron dosimeters, based on foil activation and film dosimetry principles, placed on field 

tests at the PRTR, at production reactors, and at selected locations in the Weapons 

Fabrications building. Preliminary results indicate that these dosimeters which permit an 

evaluation of fast neutron dose by film density measurements are performing 

satisfactorily in the field. They can provide an intermediate step to provide an improved 

neutron dosimetry over that currently available with the NTA film dosimeters. 

RL-REA-472

SRDB 36698

Routine report entitled “Irradiation Processing Department Monthly Report January, 1965 

(Feb 15).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-475

SRDB 36715

Routine report entitled “Irradiation Processing Department Monthly Report April, 1965 

(May 14).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-476

SRDB 36717

Routine report entitled “Irradiation Processing Department Monthly Report May, 1965 

(Jun 14).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-477

SRDB 36718

Routine report entitled “Irradiation Processing Department Monthly Report June, 1965 

(Jul 15).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-2248

SRDB 52841

Routine report entitled “Irradiation Processing Department Monthly Report July, 1965 

(Aug 15).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-2249

SRDB 52842

Routine report entitled “Irradiation Processing Department Monthly Report August, 1965 

(Sep 15).” Report primarily addresses exposures at the single-pass reactors.

RL-REA-2250

SRDB 52850

Routine report entitled “Irradiation Processing Department Monthly Report September, 

1965 (Oct 15).” Report primarily addresses exposures at the single-pass reactors.

RL-NRD-150-6-

DEL 

SRDB 57679

N reactor dept monthly report 06/1965 


RL-REA-2251

SRDB 36691

Routine report entitled “Irradiation Processing Department Monthly Report October, 1965 

(Nov 15).” Report primarily addresses exposures at the single-pass reactors.

PNNL-13524

SRDB 12856

RMA Weapons fabrication facility shutdown (Dec 31)

RL-SEP-925

SRDB 54565

Weapon Manufacturing Operation, Radiation Control Report, 1965

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. NP 

ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. NP 

ratio

Instrument measurements

Mar-65 3.9 16.1 4.1 1.0 3.9 3.9

Jun-65 5.6 20.2 3.6 1.0 3.6 3.6

Sep-65 5.7 18.7 3.3 1.2 3.5 2.9

Dec-65 3.3 16.4 5.0 1.0 3.7 3.7

Film dosimeter measurements

Mar-65 2.6 3.8 1.5 0.9 1.5 1.7

Jun-65 2.4 5.7 2.4 0.6 1.2 2.0

Sep-65 2.2 3.1 1.4 0.7 0.9 1.3

Dec-65 2.0 3.3 1.7 0.5 0.5 1.0

1966

PNNL-13524

SRDB 12856

NPR fuel processed at REDOX (Mar-Apr)

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Reference Description

RL-NRD-294-11 

SRDB 

57683

N Reactor Trends Report December 1965 (Jan 4). This is one of a report series 

describing many facets of N Reactor Operation. This document provides a summary of 

data for 1965 to include:

1. Dates and causes of all scrams or shutdowns.

2. Fuel failures, etc., along with a summary of monthly radiation dose rates (rad/hr) 

at selected locations.

ORAUT-TKBS0006-2Fabrication of pits removed from 234-5Z RMC Line in 1966. Line shut down in 1976 as a 

result of explosion in 242-Z. RMC Line restarted in 1985, shut down in 1989.

RL-NRD-822

SRDB 38400

Radiological Status of the N Reactor for January and February, 1966 (Mar 24). Routine 

report describing radiological status. Report states that the final Battelle evaluation on 

personnel dosimetry for 1965 at N Reactor indicated that on average all crafts except 

radiation monitors were well below the N Reactor operational control limit for external WB 

dose. This limit is 5 rem including 3 Roentgens per calendar year. 

Calendar Year 1965 Radiation Dose of N Reactor 

Personnel

Critical groups Dose (mR)

Maintenance

Exempt supervision–first line 1,200

Non-exempt electrical 830

Non-exempt instrument techs. 1,470

Non-exempt millwrights 1,330

Non-exempt pipefitters 2,330

Processing

Exempt supervisors 1,470

Non-exempt process operators 1,950

Non-exempt radiation monitors 2,740

All other groups

Exempt 530

Non-exempt 480

BNWL-255

SRDB 68419

Battelle-Northwest Monthly Activities Report, April 1966 (May). Report describes under 

Personnel Dosimetry Section results of an evaluation of NTA measurement of neutron 

radiation dose from a glovebox PuF4 source as follows:

Doses from Plutonium Fluoride Source Exposure

Neutron energy category

PuF4 source, dose, rad

Bare 1⁄2” Lucite shield

> 1.3 MeV 0.302 0.119

1.3 to 0.4 MeV 0.187 0.078

Epithermal (>0.4 eV) 0.008 0.002

Thermal (<0.4 eV) 0.000 0.000

Total dosimeter evaluated dose 0.566 0.199

The one-half inch Lucite shield was used to simulate a typical plutonium hood. The 

measurements show the Lucite reduces the neutron dose for energies above 1.3 MeV by 

about 40%; the total dose is reduced by about 35%. These data indicate that at least 

60% of the PuF4 neutron dose observed through a one-half inch Lucite panel can be 

monitored with the NTA emulsion neutron dosimeter.

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Reference Description

RL-GEN-960-1

SRDB 36880 

Radiological status of the N reactor for March 1966 (April 18, 1966). Routinely prepared 

report that provides monthly status report of survey readings in mR per hour under stated

operating conditions, along with information concerning incidents, contamination levels, 

etc.

BNWL-275

SRDB 64821

Battelle-Northwest Monthly Activities Report, May 1966 (June 1966). Report describes 

under Personnel Dosimetry “The evaluation and correction of approximately 2,500 dose 

results for dosimeters worn during the period ending March 1966, which were reported to 

be questionable, is nearly complete. Approximately 700 dose results for neutron 

dosimeters worn during the periods ending March and April 1966 were reported to be 

questionable. Evaluation and correction of these results is approaching completion. 

Special external exposure evaluations were performed for 45 other Hanford contractor 

employees; however, no exposures over permissible limits were revealed.”

RL-GEN-960-2

SRDB 36885 

Radiological status of the N reactor for April 1966 (May 13, 1966). Routinely prepared 

report that provides monthly status report of survey readings in mR per hour under stated 

operating conditions, along with information concerning incidents, contamination levels, 

etc.

BNWL-302

SRDB 64822

Pacific Northwest Laboratory Monthly Activities Report, July 1966, Division of Production 

and Hanford Plant Assistance Programs (August 1966).

DUN-558

SRDB 57660

Douglas United Nuclear, Inc. Monthly Report 01/1966

DUN-559

SRDB 57660

Douglas United Nuclear, Inc. Monthly Report 02/1966

DUN-560

SRDB 57661

Douglas United Nuclear, Inc. Monthly Report 03/1966

DUN-561

SRDB 57662

Douglas United Nuclear, Inc. Monthly Report 04/1966

DUN-562

SRDB 57666

Douglas United Nuclear, Inc. Monthly Report 05/1966

DUN-563-DEL

SRDB 57667

Douglas United Nuclear, Inc. Monthly Report 06/1966 (Jul 1966). Report covers primarily 

single-pass cooling production reactors operated by DUN. However, on page 14, this 

report describes “The assignment of neutron badges was discontinued within the DUN 

reactor facilities in April, 1966, however, the present practice requires each individual to 

sign a Neutron Exposure Register form prior to entering a radiation zone, where a 

neutron dose rate has been established, and to record an estimated dose.” Radiation 

Practices Engineering has provided signs for each reactor area outlining the procedure to 

be followed for the neutron dose recording program.

DUN-1293-DEL

SRDB 57599

Douglas United Nuclear, Inc., Monthly Report July, 1966.

DUN-1294

SRDB 57601

Douglas United Nuclear, Inc., Monthly Report August, 1966. Report describes settlement 

on August 21, 1966 of a strike by HAMTC which began on July 8, 2006. 

DUN-1295

SRDB 57603

Douglas United Nuclear, Inc., Monthly Report September, 1966

DUN-1638

SRDB 57608

Douglas United Nuclear, Inc., Monthly Report October, 1966

DUN-1639

SRDB 57613

Douglas United Nuclear, Inc., Monthly Report November, 1966

ISO-611

SRDB 61207

Technical report entitled “ZrNb95 Effect on Plutonium Button Gamma Dose Rate” 

regarding measurements of dose rate in plutonium buttons in association with ZrNb95. 

Gamma spectra presented in graphs within the report showing substantial high energy 

(~750 keV) contribution from ZrNb95. 

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Reference Description

ISO-694

SRDB 54566

Plutonium Finishing Section, Radiation Control Report, 1966

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. NP 

ratio

Instrument measurements

Mar-66 3.7 16.1 4.4 1.4 3.6 2.6

Jun-66 3.1 14.5 4.7 1.0 3.0 3.0

Sep-66 2.8 16.6 5.9 2.0 4.3 2.2

Dec-66 4.0 14.2 3.6 1.7 3.9 2.3

Film dosimeter measurements

Mar-66 1.8 4.5 2.5 0.8 1.6 2.0

Jun-66 2.0 4.4 2.2 0.9 2.0 2.2

Sep-66 2.4 3.9 1.6 1.2 1.3 1.1

Dec-66 2.5 3.6 1.4 1.3 1.7 1.3

1967

BNWL-498

SRDB 64823

Pacific Northwest Laboratory Monthly Activities Report, June 1967, Division of Production 

and Hanford Plant Assistance Programs (July 1967). Report states, “A study is being 

made to prepare recommendations on the feasibility of pursuing the activation neutron 

dosimeter concept. Development work on a portable neutron survey instrument 

continued as did studies on the performance and possible uses of thermoluminescent 

and glass materials for dosimetry work.”

DUN-1640

SRDB 57614

Monthly Report December 1966

RL-GEN-1482

SRDB 60602

Document issued entitled “Production Program For Irradiating All Hanford-Produced 

Neptunium.” (March 22, 1967)

DUN-2011

SRDB 57616

Douglas United Nuclear, Inc., Monthly Report January 1967

DUN-2012-DEL

SRDB 57630

Douglas United Nuclear, Inc., Monthly Report February, 1967

DUN-2013-DEL 

SRDB 57631

Douglas United Nuclear, Inc., Monthly Report March 1967

DUN-2424

SRDB 57634

Douglas United Nuclear, Inc., Monthly Report 04/1967

DUN-2425

SRDB 57635

Douglas United Nuclear, Inc., Monthly Report 05/1967

DUN-2426

SRDB 57636

Douglas United Nuclear, Inc., Monthly Report 06/1967

DUN-6888

SRDB 333

D Reactor was shut down for deactivation (June 26, 1967)

DUN 7949

SRDB 72203

Document entitled, “N Reactor Startup and Operation, 1963 to 1970 Working Papers,” 

(May 28, 1972). This document on page 37 includes a letter from W. Devine, Director, 

AEC Production Reactor Division to R.L. Dickeman, General Manager, General Electric 

Company, HAPO describing planned transfer of N Reactor responsibilities to DUN.

ATTACHMENT D

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Reference Description

ARH-393

SRDB 54567

Plutonium Finishing Section, Radiation Control Report, 1967

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP Ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. NP 

ratio

Instrument measurements

Mar-67 7.3 13.4 1.8 1.4 3.7 2.6

Jun-67 6.2 12.2 2.0 1.1 2.7 2.5

Sep-67 5.7 14.6 2.6 1.4 2.6 1.9

Dec-67 5.0 12.6 2.5 1.7 3.6 2.1

Film dosimeter measurements

Mar-67 2.6 3.3 1.3 0.9 1.5 1.7

Jun-67 2.3 3.5 1.5 1.4 1.6 1.1

Sep-67 2.3 4.3 1.9 1.2 2.3 1.9

Dec-67 2.8 3.2 1.1 1.9 1.7 0.9

DUN-2872

SRDB 37637

Douglas United Nuclear, Inc., Monthly Report July 1967 (Aug 17). Operating 

responsibility for the N Reactor and associated fuel and target fabrication facilities was 

assumed by DUN on July 1, 1967. Personnel transfers from General Electric totaled 

592: 219 exempt and 373 nonexempt. 

DUN-2873-DEL

SRDB 57638

Douglas United Nuclear, Inc., Monthly Report 08/1967

DUN-2874

SRDB 57639

Douglas United Nuclear, Inc., Monthly Report 09/1967

BNWL-542

SRDB 14914

Technical report entitled, “The Establishment and Utilization of Film Dosimeter 

Performance Criteria.” (Sep 1967). This report describes the ongoing evolution in the 

effort to define criteria for a national dosimeter performance testing program. Table B-1 

entitled, “Bias and Variance Features for Hanford Film Badge Dosimetry Measurement 

Records,” provides analysis of Hanford quality control dosimeter results for beta, gamma 

and X-ray exposures at various exposure levels.” 

DUN-3179

SRDB 57640

Douglas United Nuclear, Inc., Monthly Report 10/1967

DUN-3180

SRDB 57641

Douglas United Nuclear, Inc., Monthly Report 11/1967

DUN-3181

SRDB 57642

Douglas United Nuclear, Inc., Monthly Report December, 1967. Report includes 

information concerning a HAMTC strike for 103 days that started September 1, 1967 and 

resolved on December 12, 1967. 

File: 1967-10

SRDB 33189

GR Yesberger, Richland Operations Office, Health and Safety Division, prepared 

historical summary of Hanford Radiation Protection Standards, Procedures, Practices, 

and Exposure Records (Oct 1967). This analysis was prepared in association with “On 

September 1, 1967, eight chemical operators employed at the 100-N Reactor were sent 

home by Douglas United Nuclear (DUN) management when the men refused to perform 

work which would increase their weekly radiation exposure above 300 mrem per week. 

The eight men were all members of the Hanford Atomic Metal Trades Council (HAMTC). 

A strike ensued that lasted at least 60 days.

DUN-3385

SRDB 57643

N Reactor Coproduct Demonstration

DUN-3180-RD 

SRDB 57641

Reactor operations month end report 11/30/1967 

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Reference Description

1968

DUN-3595-DEL

SRDB 37644

Douglas United Nuclear, Inc., Monthly Report 01/1968

DUN-3596-DEL

SRDB 37645

Douglas United Nuclear, Inc., Monthly Report 02/1968

DUN-6888

SRDB 333

B Reactor was shut down for deactivation (February 12, 1968)

DUN-3597-DEL

SRDB 57646

Douglas United Nuclear, Inc., Monthly Report 03/1968

SRDB 37796 Letter to DR Elle to file entitled: “Film Badge Dosimetry–Anomalous Results in 

December 1967, January, February and March 1968, Dosimeters. (Apr 23, 1968).” 

Letter describes a meeting involving representatives from AEC-RL, ARCHO, BNW, 

ITT/FSS, J. A. Jones, and U. S. Testing, Company was held to discuss the problem of 

anomalous film badge readings which resulted in a high dose evaluation in December 

1967 and the first quarter of 1968. 

SRDB 38330 Letter from KR Heid to file, dated May 2, 1958 regarding follow-up to April 22, 1968 

meeting to investigate the cause of high dose reports. The estimated high dose bias was 

based on quality control dosimeter results which are described in the letter. 

DUN-4017-DEL

SRDB 57647

Douglas United Nuclear, Inc., Monthly Report 04/1968

DUN-4018-DEL

SRDB 57648

Douglas United Nuclear, Inc., Monthly Report 05/1968

UNI-M-10, p 22

SRDB 59172

Radiation Exposure Usage Accountability System was established by the exposure 

reduction task force. This process consisted of manual recording of the daily PIC data. 

The original manual system was later computerized with capabilities to provide individual 

worker exposure for each day and in addition of the accumulated exposure for the week, 

month, year to date, etc. 

DUN-4019-DEL 

SRDB 57649

Douglas United Nuclear, Inc., Monthly Report 06/1968

DUN-4450-DEL

SRDB 57650

Douglas United Nuclear, Inc., Monthly Report 07/1968

DUN-4451-DEL

SRDB 57651

Douglas United Nuclear, Inc., Monthly Report 08/1968

DUN-4452

SRDB 57652

Douglas United Nuclear, Inc., Monthly Report 09/1968

DUN-4811-DEL

SRDB 57653

Douglas United Nuclear, Inc., Monthly Report 10/1968

DUN-4812

SRDB 57654

Douglas United Nuclear, Inc., Monthly Report 11/1968

DUN-4813-DEL

SRDB 57655

Douglas United Nuclear, Inc., Monthly Report 12/1968

BNWL-CC-1762-1

SRDB 34223

Chemical Processing of Irradiated Targets From Hanford's Plutonium-238 Demonstration 

Program Part 1: N Reactor Neptunium-Aluminum Alloy Elements 

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Reference Description

ARH-1131

SRDB 54568

Plutonium Finishing Section, Radiation Control Report, 1968

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. NP 

ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. NP 

ratio

Instrument measurements

Mar-68 6.0 16.5 2.8 2.2 3.0 1.4

Jun-68 5.6 14.2 2.5 2.4 3.4 1.4

Sep-68 4.5 10.0 2.2 2.7 4.7 1.7

Dec-68 4.6 14.1 3.1 4.8 2.7 0.6

Film dosimeter measurements

Mar-68 2.9 3.8 1.3 1.1 1.3 1.2

Jun-68 3.1 5.6 1.8 1.0 2.9 2.9

Sep-68 3.0 4.4 1.5 1.6 1.9 1.2

Dec-68 3.0 4.6 1.5 1.2 1.7 1.4

1969

BNWL-1030

SRDB 64825

Pacific Northwest Laboratory Monthly Activities Report February 1969, Division of 

Production and Hanford Plant Assistance Programs (March 1969). Some details of 

construction of the new Hanford thermoluminescent dosimeter readers are presented.

PNNL-13524

SRDB 12856

231-Z fabricated devises for Nevada Test Program

BNWL-1340

SRDB 11096

AEC Workshop on Personnel Neutron Dosimetry (Sep 23). This report describes the first 

AEC workshop to discuss neutron dose issues among selected sites with a neutron 

dosimetry program. The report notes the potential serious under-reporting of neutron 

dose to workers for intermediate energy neutrons using NTA film. 

DUN-5254

SRDB 57656

Douglas United Nuclear, Inc., Monthly Report 01/1969

DUN-5255

SRDB 57657

Douglas United Nuclear, Inc., Monthly Report 02/1969

DUN-5256

SRDB 57658

Douglas United Nuclear, Inc., Monthly Report 03/1969

DUN-5610

SRDB 57663

Douglas United Nuclear Monthly Report 04/1969

DUN-6888

SRDB 333

C Reactor was shut down for deactivation (April 25, 1969)

DUN-5611

SRDB 57664

Douglas United Nuclear Monthly Report 05/1969

DUN-5612

SRDB 57665

Douglas United Nuclear Monthly Report 06/1969

DUN-5965 

SRDB 57605

Douglas United Nuclear Monthly Report 07/1969

DUN-5966

SRDB 57620

Douglas United Nuclear Monthly Report 08/1969

DUN-5967

SRDB 57623

Douglas United Nuclear Monthly Report 09/1969

DUN-6270

SRDB 57625

Douglas United Nuclear Monthly Report 10/1969

DUN-6271

SRDB 57626

Douglas United Nuclear Monthly Report 11/1969

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Reference Description

DUN-6272

SRDB 57627

Douglas United Nuclear Monthly Report 12/1969

ARH-1213

SRDB 60062

Plutonium Finishing Section, Radiation Control Report, 1969

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-69 4.0 13.2 3.3 2.5 2.6 1.0

Jun-69 5.1 17.2 3.4 4.5 3.3 0.7

Sep-69 5.2 18.0 3.5 3.2 3.6 1.1

Dec-69 5.7 19.0 3.3 3.1 3.0 1.0

Film dosimeter measurements

Mar-69 2.5 3.6 1.4 1.0 1.8 1.8

Jun-69 3.2 3.2 1.0 2.3 2.1 0.9

Sep-69 2.7 2.6 1.0 2.5 1.4 0.6

Dec-69 4.8 5.6 1.2 2.2 3.5 1.6

1970

DUN-6888

SRDB 333

“Historical Events–Single Pass Reactors and Fuels Fabrication.” (Apr 10). The stated 

intent of this report is to record, in one place, the significant historical events associated 

with the single-pass reactors from initial startup through December 1969. Significant 

events are listed in Section 1 of the report and specific programs are summarized in 

Section 2.

DUN-6888

SRDB 333

KW Reactor was shut down for deactivation (February 1, 1970)

ARH-1213-4

SRDB 54570

Plutonium Finishing Section, Radiation Control Report, 1970

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-70 5.6 13.3 2.4 2.6 2.4 0.9

Jun-70 7.6 11.2 1.5 4.0 1.7 0.4

Sep-70 7.5 11.5 1.5 5.1 1.5 0.3

Dec-70 8.3 32.1 3.9 8.6 3.5 0.4

Film dosimeter measurements

Mar-70 2.5 3.6 1.4 1.0 1.8 1.8

Jun-70 3.2 3.2 1.0 2.3 2.1 0.9

Sep-70 2.7 2.6 1.0 2.5 1.4 0.6

Dec-70 4.8 5.6 1.2 2.2 3.5 1.6

1971

BNWL-CC-2633

SRDB 15395

Basic Hanford thermoluminescent dosimeter (TLD) implemented for nonradiological 

workers.

PNNL-13524

SRDB 12856

Presidential decision to close the last of Hanford single-pass reactors, KE and KW, and 

the Hanford N Reactor effective January 28, 1971.

DUN-6888

SRDB 333

The last single-pass cooling reactor, KE Reactor, was shut down for deactivation 

(January 29, 1971)

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Reference Description

DUN-M-1

SRDB 59064

DUN issues Radiation Protection Manual that establishes occupational and 

nonoccupational exposure limits, and provides administrative check points, methods, and 

safeguards for use in controlling personnel exposure within limits. Section 2.6 requires 

the following:

“If planned work will cause personnel to exceed an exposure check point(s), the 

responsible supervisor shall, before work begins:

1. Complete all sections of the appropriate “Personnel Exposure Request“ form. 

These forms are requests for:

• Exposure over 300 mrem, but less than 500 mrem in 7 days.

• Exposure over 500 mrem in 7 days.

• Exposure over 3 rems per year.

2. Submit the completed form to Radiation monitoring for review.

Acquire from Environmental Engineering, the current radiation exposure status for each 

individual listed on the form.”

BNWL-SA-3955 

SRDB 15397

The Hanford Thermoluminescent Multipurpose Dosimeter (May 28, 1971). This report 

describes the design and performance characteristics of the Hanford Multipurpose 

Thermoluminescent Dosimeter (TLD) implemented on January 1, 1972 for radiological 

workers (note: a basic Hanford one-chip TLD was implemented January 1, 1971 for 

nonradiological workers).

This document describes results of several laboratory studies of the dosimeter response. 

To include results of field testing of the dosimeter in which selected workers wore the 

TLD and the Hanford Neutron Film dosimeter used until December 31, 1971. Results of 

this field testing are summarized below. 

Employee

number

Slow neutrons 

(mrem)

Fast neutrons 

(mrem)

TLD Film TLD Film

1 6 30 0 0

2 9 30 200 0

3 12 40 200 0

4 6 30 0 0

5 3 0 140 0

6 6 30 160 0

7 9 50 180 110

8 36 20 0 110

9 21 0 0 100

10 6 20 180 0

11 3 0 140 0

12 15 0 410 0

13 12 40 260 0

14 15 40 130 0

15 9 30 270 130

According to this report, statistical analysis of the data indicates that the TL neutron 

dosimeter can consistently detect 0.5 mrad of thermal neutrons and 5 mrads of fast 

neutrons within ±50% under ideal conditions. 

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Reference Description

ARH-1903-DEL

SRDB 68500

200 Areas Operational Report for March 1971 (Apr 22). Routine operational monthly 

report that contains information as follows: “The new plutonium storage building, 2736-Z, 

was placed into service by the Plutonium Finishing Section. Initial survey results in the 

vaults indicate the installed shielding will significantly reduce the dose rates to personnel 

working in the vaults.” 

PNNL-13524

SRDB 12856

Decision made to restart the Hanford N Reactor (August 1971).

ARH-2073

SRDB 60065, 

60066, 60068

Plutonium Finishing Section, Radiation Control Report, 1971

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-71 9.2 12.8 1.4 9.1 1.7 0.2

Jun-71 8.3 15.0 1.8 5.3 2.6 0.5

Sep-71 7.1 19.1 2.7 3.0 2.7 0.9

Dec-71 6.8 26.2 3.9 3.6 2.6 0.7

Film dosimeter measurements

Mar-71 4.6 3.3 0.7 3.9 1.2 0.3

Jun-71 5.6 4.8 0.9 3.0 2.8 0.9

Sep-71 4.8 5.4 1.1 2.5 2.3 0.9

Dec-71 4.4 4.8 1.1 1.9 2.2 1.2

1972

BNWL-SA-3955

SRDB 15397

Multipurpose Hanford thermoluminescent dosimeter (TLD) implemented for radiological 

workers.

BNWL-B-127

SRDB 13698

Hanford Multipurpose TL Dosimeter Field Tests and Evaluation (Aug). This report 

describes workplace parallel studies between the TLD nonpenetrating, penetrating and 

neutron dose response and the associated responses of Hanford beta/photon film and 

NTA film neutron dose responses. Studies involved workers wearing both types of 

dosimeters and also carboys placed in selected work areas with both types of dosimeters 

attached. These studies showed a significant under-response of the NTA neutron dose 

in comparison with the TLD neutron dose and resulted in a DOE/HQ technical study of 

Hanford neutron doses led by EJ Vallario.

ARH-2647

SRDB 4774

A Method for Estimating Neutron Exposures Received by Plutonium (draft). This report 

describes development of NP dose ratios to estimate an adjusted neutron dose for 

Hanford plutonium workers for years prior to 1972 when NTA film dosimeters were used 

and prior to 1950 when boron lined pencils were used along with portable instruments.

ARH-2473

SRDB 60070, 

60072, 60074

Plutonium Finishing Section, Radiation Control Report, 1972

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-72 7.9 19.0 2.4 5.6 2.7 0.5

Jun-72 8.2 18.3 2.2 4.7 3.6 0.8

Sep-72 9.8 19.4 2.0 5.6 3.6 0.6

Dec-72 7.7 10.7 1.4 3.5 9.3 2.7

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Reference Description

1973

ARH-2792

SRDB 60017, 

60016

Plutonium Finishing Section, Radiation Control Report, 1973

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-73 6.7 8.8 1.3 4.1 1.6 0.4

Jun-73

Sep-73

Dec-73

1974

ARH-3082 SRDB 

60076, 60077, 

60079

Plutonium Finishing Section, Radiation Control Report, 1974

Date

Hoods 

7C-9B 

gamma

Hoods 

7C-9B 

neutron

Hoods 

7C-9B, 

inst. 

NP ratio

Button 

line 

gamma

Button 

line 

neutron

Button, 

instr. 

NP ratio

Instrument measurements

Mar-74 6.9 9.5 1.4 5.2 1.0 0.2

Jun-74 6.7 10.2 1.5 5.4 1.6 0.3

Sep-74 6.9 9.8 1.4 6.3 1.7 0.3

Dec-74 6.8 10.1 1.5 6.6 1.8 0.3

UNI-174

SRDB 29156

1973 Year-End Exposure Report (May 1974). Dose components described individually to 

include neutron radiation as follows:

Annual dose summary as follows:

Type of exposure

Total exposure 

(mrem)

Whole body gamma

Monthly badged employees 658,830

Quarterly badged employees 100,240

Annually badged employees 26,000

Total WB gamma 785,090

Total neutron exposure 1,330

Internal exposure WB dose 200

Total WB penetrating exposure 786,620

Details of neutron recorded dose as follows:

No. of employees Dose/yr (mrem)

13 Less than 50

3 Between 50 and 100

5 Between 100 and 200

1 210

0 Greater-than 210

Total = 22 Total = 1330 

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1975

UNI-M-10

SRDB 59172

Document issued entitled, “Exposure Reduction Guide,” identifying companywide 

requirements (January 1, 1975)

UNI-372

SRDB 59171

1974 Year-End Exposure Report (June 1975). Dose components described individually 

to include neutron radiation as follows:

Type of exposure

Total exposure 

(mrem)

Whole body gamma

Monthly badged employees 665,890

Quarterly badged employees 108,620

Annually badged employees 43,450

Total WB gamma 817,960

Total neutron exposure 2,700

Internal exposure WB dose 200

Total WB penetrating exposure 820,860

Details of neutron recorded dose as follows:

No. of employees Dose/yr (mrem)

56 Less-than 50

5 Between 50 and 100

2 Between 100 and 200

0 Greater-than 200

Total = 63 Average = 40 mrem 

1976

ORAUT-TKBS0006-2234-5Z RMC Line shut down in 1976 as a result of explosion in 242-Z. RMC Line 

restarted in 1985, shut down in 1989.

1977

UNI-818

SRDB 59170

Document entitled “Criteria for Radiation Control Program” issued for United Nuclear 

Industries (July 5, 1977)

1978

SRDB 

26722

Accidental Irradiated Fuel Discharge from N Reactor Hanford Reservation Richland, 

Washington December 16, 1977

1979

RHO-CD-704

SRDB 67503

The PUREX Plant receives irradiated production reactor fuels, which are processed to 

produce purified plutonium, uranium, and neptunium nitrates, which were shipped as 

liquid solutions to subsequent processing sites at Hanford. The PUREX Oxide 

Conversion Facility was built into the N and M Cell area (202-A Building), which is 

completely surrounded by the PUREX Building to provide for conversion of plutonium 

nitrate to plutonium oxide. The feed to the Oxide Conversion Facility is the normal 

PUREX product plutonium nitrate solution with 250 to 350 grams of plutonium per liter in 

about seven molar nitric acid. The produced plutonium oxide could then be loaded into 

sealed containers for shipment and storage. 

UNI-M-10 Rev

SRDB 59172

UNC Nuclear Industries issues revision to “Radiation Exposure Reduction,” (June 1, 

1979)

1980

PNL-3213

SRDB 13700

Personnel Neutron Dosimetry at Department of Energy Facilities. This document 

describes prevalent dosimetry methods including NTA and TLD.

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Reference Description

WHC-SP-0479

SRDB 67517

PUREX Handing Procedure for UNH Process Material, 202-A, 200-E (Jan 1, 1980). 

Description of some details of plutonium solution rework. Under section 4.11.2.4.1, it is 

stated that “Although a seemingly simple job, loading plutonium nitrate into shipping 

vessels requires ~70 operating steps executed in the proper sequence to minimize the 

potential for nuclear or radiation hazards. “

1981

PNL-3536

SRDB 15355

Hanford Personnel Dosimeter Supporting Studies FY-1980. This document includes 

several studies of Hanford dosimetry system performance and some measurements in 

selected Hanford facilities.

1982

PNL-3736

SRDB 15439

Hanford Personnel Dosimeter Supporting Studies FY-1981. This document includes 

several studies of Hanford dosimetry system performance and some measurements in 

selected Hanford facilities.

UNI-2137

SRDB 58670

Document issued entitled “Characterization of Surface Contamination in UNC Facilities,” 

(August 30, 1982)

UNI-2164

SRDB 58669

Document issued entitled “Characterization of Airborne Radioactive Particles in UNC 

Facilities.” (August 30, 1982)

1983

PNL-3982

SRDB 13345

Response Characteristics of Selected Personnel Neutron Dosimeters (Sep). 

UNI-M-10 Rev 2 

SRDB 58680, 

58681

UNC Nuclear Industries issues “ALARA Program and Radiation Exposure Reduction 

Guide,” (Dec 31, 1983)

1984

1985

1986

RHO-HS-ST-10-

VOL1-ATT

SRDB 60801

Document entitled “Historical Timelines of Hanford Operations (Aug 28, 1986).” Report 

provides detailed charts of Hanford operations to include a historical review of Hanford 

radiation protection guidelines shown below. 

1987

N Reactor operation terminated (January).

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Reference Description

PNL-6125

SRDB 262

Historical document entitled “Historical Review of Personnel Dosimetry Development and 

its Use in Radiation Protection Programs at Hanford, 1944 to the 1980s.” (Feb 1987). 

This document describes many facets of the Hanford Radiation Protection Program. The 

two-element beta/gamma film dosimeter developed at the Metallurgical Laboratory 

(Pardue et al. 1944) and implemented at the Clinton Laboratory was used at Hanford until 

a new multielement beta/photon film dosimeter was implemented during April 1957. The 

NTA film was used in the regular Hanford beta/gamma holder from 1950 until 1957, at 

which time a separate “neutron dosimeter” was implemented. This neutron dosimeter 

consisted of the NTA film and a regular beta/gamma film packet for measurement of 

thermal and slow neutron exposure. Cadmium and tin shields were used to provide 

capabilities for slow neutron dose measurement. This dosimeter was assigned to 

workers with potential exposure to neutron radiation until the introduction of the 

thermoluminescent dosimeter (TLD) on January 1, 1972. A second multielement 

beta/gamma film dosimeter was implemented at Hanford during August 1962 which had 

improved low-energy photon and mixed beta/photon dose capabilities. This dosimeter 

included glass fluorods and an activation foil system to provide high-dose nuclear 

excursion dose capabilities. The multipurpose Hanford TLD system implemented 

January 1, 1972 replaced all of the beta/photon and neutron film dosimeters. 

1988

1989

ORAUT-TKBS0006-2234-5Z RMC Line plutonium metal operations (May) shut down in 1989 with ongoing 

plutonium storage in PFP vault.

TRAC-0672

SRDB 67464

Radiological History of the PUREX Facility 1955 to 1989 (August 1, 1989). Historical 

review of radiological events at PUREX. On page 24, it is stated “Dose rates in the “old” 

N-cell hood room averaged 5 to 15 mR/hr during normal operations, but radiation 

measurements, on occasion, have been detected up to 300 mR/hr on the N-1 tank. 

Neutron radiation averaged from less than 1 to 3 mrem/hr in the N-cell glove box room.” 

A renovated N-Cell area was constructed in 1984. On page 25, in reference to the new 

N-cell, it is stated “Radiation dose rate in the vicinity of the glove boxes will normally 

range from 2 to 20 mR/hr at the hood front while operating. Neutron radiation in the glove 

box rooms average 1 to 5 mrem/hr. Neutron measurements on the final product cans 

seldom exceed 20 mrem/hr.”

PNL-6980

SRDB 27670

Historical document entitled “A Historical Review of Portable Health Physics Instruments 

and Their Use in Radiation Protection Programs at Hanford, 1944-1988 (Sep 1989).” This 

document describes the development of the various portable radiation detection 

instruments used at Hanford, the period of use, and the importance of these instruments 

to workplace radiation safety such as in the preparation of and work performance under 

Special Work Permits, 

PNL-7439

SRDB 285

A Study of Detailed Dosimetry Records for a Selected Group of Workers Included in the 

Hanford Mortality Study. This document describes a review of the hard copy records in 

comparison with computer database records for selected workers included in the Hanford 

Mortality Study. 

PNL-7447 

SRDB 4793

Historical document entitled “Description and Evaluation of the Hanford Personnel 

Dosimeter Program from 1944 Through 1989 (Sep 1990).” This document describes 

details of the various Hanford external dosimetry system designs, algorithms, etc., along 

with laboratory energy response and dose measurements. 

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Reference Description

1990

PNL-7439

SRDB 285

A Study of Detailed Dosimetry Records for a Selected Group of Workers Included in the 

Hanford Mortality Study. This document describes a review of the hard copy records in 

comparison with computer database records for selected workers included in the Hanford 

Mortality Study. 

1991

PNL-7881

SRDB 13703

Response of TLD Albedo and Nuclear Track Dosimeter Exposed to Plutonium Sources 

1992

WHC-MR-0293

SRDB 470

Legend and legacy: Fifty Years of Defense Production at the Hanford Site. 

1993

WHC-MR-0440

SRDB 34730

“Multiple Missions: The 300 Area in Hanford Site History.” (Sep 1993). 

1994

PNL-10066

SRDB 305

An Assessment of Bias and Uncertainty in Recorded Dose from External Sources of 

Radiation for Workers at the Hanford Site. 

1995

1996

PNL-10516

SRDB 309

Response of the Hanford Combination Neutron Dosimeter in Plutonium Environments

1997

PNNL-11196

SRDB 5275

Historical document entitled “Retrospective Assessment of Personnel Neutron Dosimetry 

for Workers at the Hanford Site (Feb 1997).” This document was prepared to examine 

the specific issue of the potential for unrecorded neutron dose for Hanford workers with 

the conclusion that the neutron dose was generally underestimated prior to the 

implementation of the TLD on January 1, 1972. 

DOE/RL-97-1047

SRDB 27666

History of the Plutonium Production Facilities at the Hanford Site Historic District, 1943-

1990

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TABLE OF CONTENTS

SECTION TITLE PAGE

E1. Executive Summary .............................................................................................................201

E2. Introduction ..........................................................................................................................202

E3. Site Profile Neutron Dose Reconstruction Recommendations.............................................. 203

E4. History..................................................................................................................................203

E4.1 Facility Design .......................................................................................................... 204

E4.2 N Reactor Operation................................................................................................. 205

E5. Radiation Protection Practices .............................................................................................206

E6. Methods ...............................................................................................................................207

E6.1 Site Expert Interviews............................................................................................... 207

E6.2 Data Capture............................................................................................................ 207

E6.3 DOE REIRS Data ..................................................................................................... 208

E6.4 U.S. Nuclear Regulatory Commission (NRC) Studies of Commercial 

Nuclear Plants .......................................................................................................... 208

E7. Results.................................................................................................................................208

E7.1 Site Expert Interviews............................................................................................... 208

E7.2 Dosimeter Recorded Photon Dose ........................................................................... 210

E7.3 N Reactor Reports, Policies and Procedures............................................................ 211

E7.4 Query of N Reactor Workers Dosimeter Measured Neutron and 

Photon Dose............................................................................................................. 213

E7.5 DOE REIRS Annual Dose Summaries...................................................................... 217

E7.6 UNC Annual Exposure Summaries........................................................................... 218

E7.7 NRC measured neutron and photon doses in commercial nuclear 

plants........................................................................................................................ 218

E8. Summary .............................................................................................................................219

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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LIST OF TABLES

E-1 Sample of Hanford N-Reactor data collection....................................................................... 212

E-2 List of N Reactor worker measured neutron and photon dose, ≥30 mrem, 

respectively.......................................................................................................................... 216

E-3 Lognormal statistical parameters to measured TLD neutron dose........................................ 216

E-4 Unique REX-ID worker annual dose records with positive neutron dose .............................. 217

E-5 Unique REX-ID worker measured and assigned annual neutron doses for 

1964–86............................................................................................................................... 217

E-6 Hanford reactor category REIRS/REMS reporting................................................................ 218

E-7 UNC annual report identified dose components ................................................................... 218

E-8 Neutron dose distribution for UNC annual reports ................................................................ 218

LIST OF FIGURES

F-1 Timeline of Hanford plutonium plant facilities and operational changes................................ 224

F-2 Hanford plutonium production .............................................................................................. 230

F-3 Variation in measured neutron and photon dose rates with distance, and 

the associated calculated NP ratio ....................................................................................... 238

F-4 1,419 measured NP ratios in Hanford 234-5Z plutonium facility ........................................... 240

F-5 Scatter plot of 1,346 measured neutron and photon doses .................................................. 242

F-6 Lognormal probability plot of 1,419 measured NP values..................................................... 242

F-7 Radiation control report instrument measured monthly neutron dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-8 Radiation control report instrument measured monthly photon dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-9 NP ratios calculated from the data contained in Figures F-5 and F-6 ................................... 245

F-10 Correlation of TLD measured neutron and photon doses ..................................................... 246

F-11 Lognormal probability plot for TLD measured neutron-photon ratios .................................... 246

F-12 Fluorination 7C/9B and 7A/9A hoods instrument and worker TLD NP ratio 

measurements ..................................................................................................................... 247

E1. EXECUTIVE SUMMARY

There is comparably low level neutron dose received by some N Reactor workers on some occasions 

that was not reliably measured prior to the implementation of the thermoluminescent dosimeter on 

January 1, 1972. The photon dose was reasonably accurately measured throughout N Reactor 

Operation from December 1963 through December 1986. A feasible option to reconstruct neutron 

dose to N Reactor workers prior to the use of the TLD is to multiply the measured photon dose by a 

NP dose ratio. The recommended NP lognormal distribution has a GM equal to 0.06, a GSD = 3.1

and a 95th percentile equal to 0.4. As described in this paper, relatively few positive neutron results 

for N Reactor workers have been measured with TLDs used since January 1, 1972. The entire 

annual dose history during the 1963-86 period of N Reactor operation was examined for a selected 

group of 592 workers. These workers were selected as persons employed at the 100-N reactor using 

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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criteria described in this paper. Only 14 of the sample of 592 workers showed a TLD-measured 

neutron and photon dose ≥ 30 mrem, respectively, during the 1972–1986 period. The distribution was 

based on a single worker with the maximum number of positive TLD-measured neutron doses 

consisting of 4 years (NP ratio: 1972–0.027; 1974–0.003; 1977–0.042; 1978–0.027) and for the other 

years had no measured neutron dose (1973, 1975, 1976, 1979, 1980, 1981, 1982, 1983, 1984, 1985 

and 1986). The low-level neutron dose to workers at N Reactor is confirmed by the collective neutron 

dose reported during 1973 and 1974 as a fraction of 0.002 and 0.004, respectively, of the collective 

photon dose. The recommended NP ratio will result in significant assigned neutron dose for the 

period from 1964 through 1971 [i.e., measured neutron dose = 0 mrem. Assigned neutron dose = 806 

mrem (50th-percentile) or = 1,612 mrem (95th percentile)]. The approach is considered to be 

favorable-to-claimants as illustrated in this attachment by comparing the TLD-measured neutron dose 

with the value that would be assigned using this approach for the period of N Reactor operation and 

this person’s employment from 1972 through 1986 [i.e., measured neutron dose = 280 mrem. 

Assigned neutron dose = 934 mrem (50th percentile) or = 1,868 mrem (95th percentile)]. These 

neutron doses must also incorporate the ICRP Publication 60 weighting factor, which for the neutron 

category of 0.1 to 2 MeV is equal to 1.91 (ICRP 1991) and, thus, a further increase in assigned 

neutron dose of nearly a factor of 2 will occur.

E2. INTRODUCTION

The focus of this analysis concerns a technical basis for neutron dose reconstruction for Hanford 100 

Area N Reactor Workers during the period of its operation from December 1963 through January 

1987. A technical basis has been developed for neutron dose reconstruction at the Hanford eight 

single-pass cooling plutonium production reactors (B, C, D, DR, F, H, KE, and KW) constructed during 

the period from 1943 through 1954 that operated from 1944 through 1971 (Taulbee et al. 2008). 

Neutron radiation exposures to reactor workers at the Hanford 100 Area N Reactor were not reliably 

measured using personnel dosimeters prior to implementation of the Hanford TLD on January 1, 

1972. Prior to the use of the TLD, Hanford used NTA personnel neutron film in a dedicated Hanford 

neutron personnel dosimeter implemented during 1958 with thermal and fast neutron dose capabilities 

as well as photon dose.

Hanford Radiation Protection professionals were well aware of limitations in NTA film capabilities to 

reliably measure intermediate energy neutron radiation dose for many years prior to startup of the N 

Reactor. Hanford established operational limits for WB dose in 1954 based on a safety factor of 5 to 

compensate for unknowns in dosimetry and risk (i.e., official guide of 15 rem WB dose per year was 

divided by 5). The operational limit for the photon component of the measured WB dose was 

established as 3 R/yr for photon and neutron radiation, respectively (GE 1954). In 1960, when the 

AEC adopted the NCRP radiation protection guidance for the WB external dose of 5 × (N-18) rem per 

year where N is the age in years, Hanford continued the practice to limit the WB photon dose to less 

than 3 rem/yr (GE 1960) The decision to stop assignment of NTA film personnel neutron dosimeters 

to N Reactor workers, along with workers at the Hanford single-pass cooling production reactors, was 

made effective during April 1966 (DUN 1966). For reasons explained in this attachment, the 

measured photon radiation dose to each worker for all years of N Reactor operation (i.e., shut down 

during January 1987) is considered to have been reasonably accurately measured by Hanford film 

and thermoluminescent dosimeters. The TLD-measured neutron dose is considered to be reasonably 

accurate with a significant potential to overestimate rather than underestimate the actual neutron dose 

(Endres et al. 1981; Scherpelz et al. 2000; Brackenbush et al. 1980). A timeline of significant events 

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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at Hanford associated with radiation protection of N Reactor workers is presented in Attachment D, 

Table D-2. 

An option to retrospectively estimate a favorable-to-claimant neutron dose to N Reactor workers is to 

multiply the measured photon dose by a NP ratio. This option, assuming the distribution is properly 

chosen, will provide a favorable-to-claimant dose reconstruction because the vast majority of dose to 

N Reactor workers is the result of photon radiation exposure. It is clear from documentation in 

Attachment D that extensive surveys of N Reactor photon and neutron radiation exposures throughout 

the facility were required to comply with AEC-approved startup power accession plans. The record of 

TLD-measured doses confirms that neutron radiation exposure to workers was comparably low in 

comparison with the photon dose. The option to utilize an NP ratio to reconstruct potential neutron 

dose to individual workers avoids significant issues concerning:

1. During the period from December 1963 through April 1966, only selected N Reactor workers 

were assigned a Hanford NTA film neutron dosimeter.

2. During the period from May 1966 through December 1971, Hanford NTA film neutron 

dosimeters were not assigned to Hanford N Reactor workers. 

3. Hanford neutron dosimeters did not reliably provide a reasonably accurate estimate of the 

actual neutron dose for N Reactor workers. 

4. Substantial effort would be necessary to resolve unknowns regarding the completeness of the 

process whereby N Reactor workers signed a Neutron Exposure Register form upon access 

into N Reactor radiation zones where a neutron dose rate had been established (DUN 1966). 

The accuracy of the estimated neutron dose that was entered on the form would also need to 

be evaluated. 

E3. SITE PROFILE NEUTRON DOSE RECONSTRUCTION RECOMMENDATIONS

The Hanford Site Profile External Radiation Technical Basis Manual prepared originally during 2003 

recommends reconstruction of the neutron dose as follows:

• Use TLD-measured neutron dose from January 1972 to date along with the missed neutron 

dose using OCAS-IG-001 guidance (NIOSH 2007b).

• Prior to 1972, multiply the NP dose ratio times the measured and missed (using OCAS-IG-001 

guidance) photon dose using ratios obtained from the following:

Process GM GSD Upper 95th %

N Reactor 0.06 3.1 0.4

E4. HISTORY

Historically, several Hanford contractors were involved in N Reactor operation and maintenance and 

in evaluation of radiation exposure to workers (Marceau et al. 2002, p. 1.69) as follows:

• GE prior to January 1, 1965, managing all Hanford operations.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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• GE through June 30, 1966, responsible for 100-N reactor operations.

• DUN, July 1, 1966 to August 1967, responsible for Hanford reactor operations and fuel 

fabrication.

• UNI, September 1967 to April 1973, responsible for Hanford reactor operations and fuel 

fabrication.

• UNI, April 1973 to June 1987, responsible for Hanford reactor operations and fuel fabrication.

• Battelle Memorial Institute as the Pacific Northwest Laboratory, contractor beginning January 

1, 1965, in the capacity of assuming responsibility for technical direction of Hanford central 

personnel dosimetry services such as the WB counting facility, personnel dosimetry, site-wide 

radiological calibrations, research and development, etc. 

• U.S. Testing Company beginning January 1, 1965 responsible for Hanford environmental and 

occupational radiochemical analyses and dosimetry services. 

• JA Jones and subcontractor craftsmen were involved throughout the operation of N Reactor as 

noted in the various routine reports in Attachment D. 

E4.1 FACILITY DESIGN

The design of the N Reactor [also commonly referred to as the 100-N or historically as the NPR (i.e., 

New Production Reactor)] was substantially different from the earlier eight Hanford single-pass 

cooling plutonium production reactors constructed during the period from 1943 through 1954. The 

earlier single-pass reactors, known as "piles" in the 1940s, drew cooling water from the Columbia 

River; the water was treated through a series of filtration and chemical processes before entering the 

pile; and then the water was returned to the river after holdup (~30 min to 6 hours) in retention basins 

to allow for short-term radioactive decay.

In contrast, the N Reactor primary coolant water was recirculated, thus releasing significantly less 

radioactive effluent to the Columbia River. The coolant circulated under pressure, allowing for much 

higher operating temperatures, and the water was demineralized so that less film was deposited 

inside the process channels. However, as is typical of commercial light-water reactors, substantial 

buildup in the coolant system of neutron activation and fission product nuclides did occur, which 

increased the significance of penetrating photon fields generally, and in maintenance work of reactor 

components of beta/photon radiation fields. The N Reactor core was surrounded by special layers of 

reflector graphite, water-cooled thermal shields constructed of boron steel and cast iron, and a 

primary shield of high-density concrete. Helium gas formed the pile atmosphere in a sealed system 

that prevented worker access without reactor operator knowledge while the reactor was operating. A 

fog spray system at both the front and rear reactor faces was provided for contamination control and 

cooling in case of a loss of contaminated steam from the core (WHC 1988). 

The radiation environment at N Reactor was divided into zones with different shielding requirements 

(Bunch, 1962). Each zone had different entry requirements. N Reactor had five protective zones as 

follows:

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AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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• Zone 1, which is adjacent to the charge face, the discharge face, and the top of the reactor. 

No access is possible to this zone during operation. Monitored access is possible during 

reactor shutdown. This zone is operated at a negative pressure relative to Zone 2.

• Zone 2, which includes secondary radiation areas such as the inner and outer rod rooms, the 

gas system, the flux and rupture monitor room, the ball system, and the ventilation exhaust 

system from Zone 1. Normally, no access to the restricted areas of Zone 2 will be required 

during operation but limited emergency access is possible. Zone 2 is operated at a negative 

pressure relative to Zone 3.

• Zone 3 is a normal access or buffer zone with free access at all times except perhaps for quite 

abnormal conditions. This zone includes most of the work regions and corridors around the 

reactor in which metal handling and other routine operations are conducted.

• Zone 4 is an unlimited access area with essentially no elevated radiation exposure during 

normal operations.

• Zone 5 is defined as a warranted access area in which continuous access is maintained at all 

time including emergencies. Zone 5 is limited to the main control room and the main 

instrument room beneath the main control room.

E4.2 N REACTOR OPERATION

The Hanford low-enriched uranium, graphite-moderated, and water-cooled N Reactor achieved initial 

criticality on December 31, 1963. Approximately 1 year of testing was necessary for the N Reactor to 

achieve the design power of 4,000 MW (thermal) on December 9, 1964 (WHC 1988, Chapter 14). 

Throughout its history of operation, the N Reactor produced 9% 240Pu reactor fuel-grade plutonium for 

the AEC’s breeder reactor program, and 12% 240Pu reactor fuel-grade fuel. In the 1980s, N Reactor 

produced only weapons-grade plutonium until it was shut down in January 1987. Figure E-1 presents 

N Reactor fuel and weapon-grade plutonium production throughout the years of operation (Lini 1993).

Throughout the years of N Reactor operation extensive administrative and technical limits were in 

effect such as in the form of operating safety limits and process standards. Startup of the reactor was 

particularly complex, involving a complete building radiation survey at stated levels of power 

ascension (Berrett and Hall 1964). Many operational problems were experienced in the early years of 

N Reactor operation with substantial downtime. As noted in Attachment D, a formal startup plan was 

adopted with defined tests such as the N1 physics testing, N2 testing of reactor operation just prior to 

providing steam for electrical power production, and N3 testing. Typically, formal documents were 

prepared for each step in the testing process for submittal to the AEC for its approval of advancement 

through the planned testing. During this process of testing, elevated photon and neutron radiation 

was measured (Greenborg and Berry 1964) emerging through N Reactor steam vent penetrations that 

are in the bottom shield of the reactor and open to the southeast and southwest corners of the ball 

hopper retrieval system. The corrective action consisted of adding a pipe offset to achieve a labyrinth 

design and providing additional shielding. This action was required for radiation protection and to 

reduce the possibility of neutron activation of system components in the ball recovery room (Hall 

1964).

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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N-Reactor Plutonium Production

0

200

400

600

800

1000

1960 1965 1970 1975 1980 1985 1990

Year

Plutonium Production, kg

Fuel Grade Pu Weapons Grade Pu

Figure E-1. Hanford N Reactor plutonium production (Lini 1993).

E5. RADIATION PROTECTION PRACTICES

The basic elements of Hanford radiation protection practices were well-defined prior to operation of 

the Hanford N Reactor. Pertinent Manuals of Radiation Protection specific to N Reactor Operation 

include:

• HW-78500, Radiation Protection Controls & Procedures–N Reactor (Vanderbeek 1964), 

published January 1, 1964.

• DUN-M-1, Radiation Control Manual, (DUN 1970) establishes occupational and 

nonoccupational exposure limits, and provides administrative check points, methods, and 

safeguards for use in controlling personnel exposure within limits.

Levels of beta, photon, and neutron radiation were monitored at the N Reactor during its period of 

operation from December 12, 1963 through 1987 by health physics staff members using personnel 

dosimeters, PICs, and portable radiation detection instruments. Personnel dosimeters represent the 

usual method to measure and record the official dose for a worker. Dosimeters assigned to workers 

are typically for a specified period (i.e., monthly or quarterly depending on potential for radiation 

exposure), and exchanged for new dosimeters according to an established monthly or quarterly 

schedule. The used dosimeters are typically processed and doses assigned as part of a much larger 

Hanford-wide group of dosimeters. Typically, the official dose based on the dosimeter is not received 

by the worker or their supervision until many days after a dosimeter is routinely exchanged. Until the 

official personnel dosimeter dose is received, administrative control of worker exposures is based on 

results of PICs or portable instruments and timekeeping. The portable instrument and PIC data are 

the methods actually used to measure and control worker radiation exposures. Basically, an 

administrative radiation exposure record is maintained for each worker for use in limiting exposures 

until the dose results from the personnel dosimeters are received. The dosimeter exchange cycle is 

selected based on the exposure potential for each worker and, in case of an incident, personnel 

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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dosimeters can be special-processed at any time. This process requires close attention by 

supervision and radiation safety personnel to the total exposure received by workers.

E6. METHODS

E6.1 SITE EXPERT INTERVIEWS

Interviews with site experts were conducted and documented regarding their assessment of the 

potential for significant neutron exposure of N Reactor workers, the potential work areas, and work 

tasks. A tour of the N Reactor was made during November 2008 with persons with expert knowledge 

of N Reactor design and operation. N Reactor site experts were asked to provide information 

concerning:

• Their knowledge of workplace radiation levels at the N Reactor, methods of measurement, 

exposure control practices, and particularly information concerning significant neutron 

exposure. 

• Their knowledge concerning changes in N Reactor construction and/or operations that might 

undermine the applicability of applying statistical parameters from TLD-measured doses to the 

pre-1972 period.

• Their knowledge concerning performance of workplace surveys and particularly access to the 

documented surveys as well as access to the N Reactor worker measured doses, and 

specifically access to the N Reactor measured-TLD-measured neutron and photon doses 

during the period from 1972 through 1987.

• Their knowledge concerning any other information that might be relevant to the reconstruction 

of neutron dose to N Reactor workers prior to 1972.

E6.2 DATA CAPTURE

Data capture trips to DOE–RL with the expressed objective to obtain detailed monitoring data 

occurred during: October 9–15, 2007; December 2–7, 2007; June 2–6, 2008; July 7–15, 2008; 

September 22–26, 2008; October 13–17, 2008; and November 17–24, 2008. Keyword searches were 

conducted of the multiple Hanford record systems by DOE–RL and contractors and the ORAU Team 

using DOE–RL-provided database indexes to identify pertinent technical reports, survey forms, and 

correspondence. Prior to these data collection trips, record indexes were received from DOE-RL and 

used in the analysis of workplace photon and neutron fields. A large number of boxes and documents 

were identified that potentially contained relevant records. The contents of these boxes and 

documents were reviewed during the data collection trips. Significant documents are noted in 

Attachment D. Sources of data of particularly significant value include:

• Validation of photon dose measurements at the Hanford N Reactor.

• Routine operations reports that typically included some information concerning radiological 

information such as the annual exposure reports that summarized annual collective neutron 

and photon doses as shown in Attachment D.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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• Radiation Protection Procedures manuals that covered essentially the entire operating history 

of N Reactor.

• Query of the Hanford Radiological Record system to identify N Reactor workers and 

subsequently to receive the annual shallow, deep, neutron, and extremity doses during the 

period of N Reactor operation.

• DOE Radiation Exposure Information Record System (REIRS) routine reports.

• U.S. Nuclear Regulatory Commission (NRC) measured neutron and photon doses in 

commercial nuclear plants.

Interestingly, although Hanford had available portable radiation protection instrumentation to readily 

measure neutron exposure in the workplace (WHC 1988) and there were requirements for surveys 

when there was a potential for significant exposure, few of the hundreds of survey forms examined 

actually included results of surveys for neutron radiation exposures. There were requirements for 

neutron surveys during startup, and there was a documented survey that showed elevated neutron 

exposure rates in the 109 building incoming steam penetration with recommendations for adding 

additional shielding. The annual exposure reports prepared by UNC in 1973 and 1974 did include a 

summary of the annual photon and neutron doses.

E6.3 DOE REIRS DATA

The DOE REIRS records were examined as a potential source of information regarding WB doses for 

N Reactor workers considering the “reactor” category used for many years. For Hanford, prior to 

1972, the reactor category also included doses received at the once-through reactors that would tend 

to bias the analysis towards a larger WB dose because there is greater exposure of workers, 

particularly to neutron radiation, in the once-through reactors.

E6.4 U.S. NUCLEAR REGULATORY COMMISSION (NRC) STUDIES OF COMMERCIAL 

NUCLEAR PLANTS

During the period of N Reactor operation, there were studies of neutron exposure of workers in 

commercial nuclear power plants. The NRC has documented extensive workplace studies of neutron 

spectra and dose, and was instrumental in the national adoption of the National Voluntary Laboratory 

Accreditation Program for testing personnel dosimeter performance and accreditation of the dosimetry 

service providers. Pacific Northwest National Laboratory (PNNL) was involved in many of these 

studies using the Hanford dosimeter along with personnel dosimeters (i.e., NTA, CR-39, TLDs) from 

other DOE Sites (i.e., Environmental Measurements Laboratory, Lawrence Livermore National 

Laboratory, SRS) and a wide variety of instruments (Snoopy, remballs, Bonner spheres, TEPCs, 3

He 

counters, etc.) to measure the neutron dose (Endres et al. 1981).

E7. RESULTS

E7.1 SITE EXPERT INTERVIEWS

Several site experts with detailed knowledge of N Reactor operation and radiological history were 

interviewed. Three of these experts had worked at N Reactor throughout its entire operating history.

ATTACHMENT E

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Site Expert 1 (Fix 2007a; Bihl 2008a). Documented interviews with Hanford Site expert who 

originally was hired at Hanford in 1948 and worked as a radiation monitor in the early days primarily in 

the 100 Area reactor areas and then as a health physicist for the last approximately 15 years of his 

employment. He worked at 100-N throughout all of N Reactor years of operation. There are two 

documented interviews. This expert stated that “The gamma exposures at 100-N with the 

recirculating coolant were substantially higher than the once-through reactors. Access to several high 

exposure areas were controlled. He was unaware of any significant facility modification that would 

change the general radiation field characteristics.”

Site Expert 2 (Fix 2008a). Documented interview with Hanford Site expert concerning his experience 

at the 100 Area reactors where he performed charge, discharge, and storage and shipment of 

irradiated fuel elements. Site expert also performed startup, operation, and shutdown at four of the 

reactors as the control room console operator.

Site Expert 3 (Fix 2007b). Documented interview with Hanford Site expert who originally began 

employment at Hanford in June 1956. Site expert spent substantial time in research activities such as 

in the Building 321 Exponential Pile Physics Laboratory, and in Building 326 working with several 

radiation sources such as 238PuBe, developing neutron spectrometer capabilities, performing work to 

characterize the NTA film energy response, and working to develop TLD systems. Site expert had 

several non-Hanford project roles including a multiyear NRC project to measure neutron spectra and 

dose in U.S. commercial nuclear reactors, which is described in several NUREG reports.

Site Expert 4 (Fix 2007c). Documented interview with Hanford Site expert who arrived at Hanford in 

about 1956 as a radiological engineer with primary responsibility for the 100-B/C reactors but who 

also worked at 100-D/DR and 100-F. Site expert spent entire career involved with reactor radiation 

safety supporting Hanford reactor operations. Interview concerned expert’s recollection of radiation 

exposures of workers in the Hanford reactors, the significance of neutron dose, and knowledge of the 

AEC 1972 neutron dose Investigation.

Site Expert 5 (Scalsky 2007a). Documented interview with Hanford Site expert who began 

employment at Hanford plutonium facilities in 1947. Site expert worked in all Hanford areas during his 

career at Hanford and has written numerous technical reports including historical reviews of the 

Hanford radiation dosimetry program.

Site Expert 6 (Fix 2007d). Documented interview with Hanford Site expert who began employment at 

Hanford facilities in 1950 working primarily in the 100 Area reactor and 300 Area fuel fabrication 

facilities as a process engineer. Interview concerned expert’s recollection of radiation exposure 

issues with Hanford 100 Area Reactor Facilities. Site expert did not consider himself to be a primary 

radiation worker but was very aware of radiation exposure limits, the use of SWPs, and general 

radiation safety activities (protective clothing, respirator protection, etc.).

Site Expert 7 (Fix 2008j) Documented interview with a Hanford Site Contractor Radiation Control 

Technologist (RCT) who arrived in 1983 at 100-N Reactor progressing to a Supervisor position. This 

person recalled that there were few neutron radiation fields at N Reactor accessible to workers. 

There might have been low-level neutron radiation fields of about 1 to 2 mrem/hr in the inner rod 

room. However, during reactor operation, access to the inner rod room required continuous RCT 

coverage. In general, the room was characterized by significant gamma radiation fields and could be 

accessed only while the reactor was down.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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Site Expert 8 (Fix 2007e). Documented interview with Hanford Site expert who arrived at Hanford in 

1950. Site expert had responsibilities for site-wide compliance with AEC/DOE Health and Safety 

(H&S) orders, directives, etc., as a senior health physicist. Expert stated on several occasions that all 

legitimate safety issues were resolved in favor of the workers. Expert provided a copy of a review of 

site exposure limits associated with a 1967 labor dispute at N Reactor (Hicks and Yesberger 1967).

Site Expert 8 (Fix 2008k). Documented interview with Hanford Site expert who arrived at Hanford in 

1956 working at Purex and subsequently after military and other site work activities was assigned to 

100-N in 1983 as a radiological engineer. This Site expert stated “The physical structure of 100-N 

could not be reasonably changed. Although he could not say definitively about the reactor prior to his 

employment there, his opinion was that neutron-to-photon ratios should have been reasonably similar 

throughout the operating history.” 

Generally, the site experts stated there should be extensive records of radiation instrument surveys 

that included neutron exposure measurements even though it was generally their experience that the 

neutron doses were generally not on the routine survey forms. Attempts to obtain radiation surveys 

for the startup power ascension requirements were not successful. The experts confirmed that 

neutron dose could be measured in some locations but that it was comparatively insignificant in 

comparison to the photon dose received by workers. Locations where there was neutron radiation, 

such as the inner rod room, also had photon radiation and access to these areas was limited while the 

reactor was operating.

E7.2 DOSIMETER RECORDED PHOTON DOSE

The AEC 1972 investigation of neutron dosimetry at Hanford stated the conclusion that the measured 

deep dose from photon radiation with Hanford film and thermoluminescent dosimeters is reasonably 

accurate. Additional reasons specific to N Reactor operation to judge that the recorded photon 

penetrating dose is reasonably accurate include:

• Improved Hanford multielement dosimeters were used for all years of N Reactor operation 

(i.e., December 1963 through January 1987).

• Response characteristics of these personnel dosimeters are well documented (Kocher et al. 

1972; Fix et al. 1981; Fix et al. 1982; Wilson 1987).

• Radiation Protection Procedures at N Reactor (Vanderbeek 1964; DUN 1967, 1968, 1971) 

required monitoring of all workers with significant potential for significant exposure.

The Hanford dosimeter system performance at the time of N Reactor operation had been 

extensively reviewed in the general effort to develop and adopt a national dosimeter performance 

testing standard (Barber 1967; Unruh et al. 1967).

• PICs were extensively used and photon doses based on PICs were evaluated in comparison 

with the dosimeter measured photon dose (Valentine, 1965).

The measured photon dose for the thermoluminescent, film, and pencil dosimeters was evaluated in 

studies leading to the implementation of the TLD on January 1, 1972. Comparison of dose results for 

dosimeters worn by DUN workers during November 1970, December 1970, and January 1971 is 

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shown in Figure E-2 based on data contained in BNWL-B-129 (Nichols et al. 1972). It is evident that 

all three types of dosimeters provide nearly identical penetrating photon radiation dose results. 

Concern was expressed at the time of this study regarding worker compliance to actually wear all 

three dosimeters at all times. The zero results for thermoluminescent, film, and pencil dosimeters 

(along the abscissa) are anticipated to be associated with workers not wearing one or more of these 

dosimeters. Field tests contained in BNWL-SA-3955 (Kocher et al. 1971) show similar good results in 

comparisons of penetrating photon radiation doses among the film, pencil, and thermoluminescent 

dosimeter systems. Unfortunately, comparison of measured neutron doses (i.e., NTA film, PIC-boron 

lined and thermoluminescent dosimeter systems) such as those done for many of the other Hanford 

work areas and included in the BNWL-B-129 document was not done. This might have simply been 

because N Reactor workers were not wearing NTA neutron dosimeters. However, processing the 

TLD involves automatically receiving all dose results (i.e., nonpenetrating, penetrating, slow and fast 

neutron). In BNWL-B-129, there are a couple of indications of low-level slow neutron dose for a 

couple of dosimeters only but generally there is no indication of any significant neutron dose. It is also 

possible that N Reactor was not operating during the period from November 1970 through February 

1971 when these field comparison tests were being made.

Hanford Workplace Comparison 

TLD Versus Film Versus Pencil

0

200

400

600

800

1000

1200

0 200 400 600 800 1000 1200

TLD Dose, mrem

Film or Pencil Dose, mrem

Film

Pencil

Figure E-2. Comparison of parallel field testing of thermoluminescent, film, and pencil 

dosimeters.

E7.3 N REACTOR REPORTS, POLICIES AND PROCEDURES

Data collections using key word searches were done to identify N Reactor routine operations reports 

that included: 

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• Radiological information such as the annual exposure reports that summarized annual 

collective neutron and photon doses, as shown in Attachment D, Table D-2.

• Radiation Protection Procedures manuals and reactor power ascension startup procedures for 

documented workplace surveys.

• Boxes of archive Hanford N Reactor records such as for example the documents listed in 

Table E-1.

Table E-1. Sample of Hanford N Reactor data collection.

Box # Year General description From To

9432 RAD SURVEY 

RPT+MISC 65-66

RCS-Code: C2506D Custodian: Redacted Cust Addr: 

1114n/100n Radiation Monitoring 105 kw. Radiation 

Survey Report Routine & Repetitive Surveys, 

Supplemental Routine Surveys, Startup Routines, Routine 

Neutron Survey, Building Survey Records, Shift Routine

01/01/65 12/01/66

11304 RAD SURVEY 

RPT+MISC 66-68

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Hand & Shoe Counter Background & Source 

Checks, Shift Log, Radiation Survey Report, Air Sample 

Log Sheets, Radiation Work Procedures, Neutron Survey 

Record, Portable Instrument & Inventory Check

06/01/66 12/01/68

11309 RADIATION 

SURVEY RPTS 

ETC 69

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Radiation Survey Reports, Air Sample Log, 

Routine Start Up Surveys, Supplemental Routine Surveys, 

Routine And Repetitive Surveys, Radiation Work 

Procedures.

01/01/69 12/01/69

13674 RADIATION 

SURVEY RPT 

ETC 1967

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Reactor Stack Effluent Record, Radiation 

Survey Report, Supplemental Routine Surveys, Startup 

Surveys, Routine Neutron, Portable Instrument Check & 

Inventory, Routine & Repetitive Surveys, Shift

01/01/67 12/01/67

18818 RADIATION 

SURVEY RPTS 

ETC 69

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Supplemental & Startup Routine Surveys, 

Building Survey Records, Routine & Repetitive Surveys, 

Radiation Survey Report 105b Building, Routine & 

Repetitive Surveys, Air Sample Log, Building Survey

01/01/69 12/01/69

26844 RADIATION 

SURVEY RPTS 

65-8/71

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Routine & Repetitive Survey Reports, Air 

Sample Log, Reactor Stack Effluent Record

01/01/65 08/01/71

82022 RADIATION 

SURVEY 

REPORTS

Rcs-Code: C2506d Custodian: Redacted Cust Addr: 

1114n/100n Radiation Survey Reports Ke & Kw Air 

Sample Logs Ke & Kw, Routine And Repetitive Survey 

Reports Ke & Kw

01/01/82 01/01/83

The documentation described in Table E-1 and in Attachment D, Table D-2 clearly states 

requirements for photon and neutron radiation surveys. In particular, the startup power accession 

plan (submitted to AEC for approval) clearly states requirements for building surveys to perform a 

complete building radiation survey for shielding adequacy and detect any unforeseen radiation 

beams, in each test step calling for special data (i.e., power levels of 0, 100, 200, 300 and 400 MW). 

A significant beam was detected in early 1964 (Greenborg and Berry 1964) in which significant dose 

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rates of gamma and neutron radiation were emerging below the steam vent penetrations. The N 

Reactor steam vent penetrations are located in the bottom shield of the reactor and open to the 

southeast and southwest corners of the ball hopper retrieval system. Hanford Laboratories personnel 

were called in to instrument these penetrations to determine the gamma and neutron radiation 

intensities. As noted in Hall (1964), the cause on investigation was neutron radiation streaming down 

the steam vent piping provided at two locations to permit venting of steam from a process tube 

rupture. Corrective action was noted at the time as being required for purposes of radiation protection 

and to reduce the possibility of neutron activation of system components in the ball recovery room. 

The action consisted of adding a pipe offset to achieve a labyrinth design and to provide additional 

shielding.

E7.4 QUERY OF N REACTOR WORKERS DOSIMETER MEASURED NEUTRON AND 

PHOTON DOSE

A collaborative effort with DOE Hanford Radiological Records was conducted with the objective to 

select only the N Reactor workers recorded neutron and photon doses (i.e., actually shallow, deep, 

neutron, X-ray, eye dose categories) from 1964 through 1987 separately from doses for workers at 

the other single-pass reactors (i.e., which generally stopped operations prior to 1972) and other 

Hanford operating areas. The basic premise to select the appropriate workers was based on the 

observation by working with the database of a continued affiliation into 1967 of General Electric 

identified personnel to support operation of the N Reactor following the general termination of General 

Electric’s role as the primary Hanford Site operations contractor which occurred approximately on 

January 1, 1965. Therefore, a query was made of the Hanford Radiological Record System to select 

only employees that met the following criteria.

• A recorded dose during 1967 (last year of GE contract role at Hanford to operate 100-N).

• A contractor code of AA (General Electric) during 1967.

• A payroll identification number less than 30000.

• Worker does not have an excreta result record for Pu-239 or U. This was necessary to 

distinguish between workers at N Reactor who might have transferred in earlier years from fuel 

fabrication or plutonium separation facilities.

• Only workers with contractor codes of AA (General Electric), HH (Douglas United Workers), 

VV or WC (Westinghouse Hanford) for any year.

• Subsequently, a few workers with significant X-ray doses were eliminated because this is seen 

only at Hanford plutonium facilities.

The query resulted in dose results for a total of 592 selected workers for which there were a total of 

4,825 dose records with a collective dose of 3,301,070 mrem of photon penetrating dose. A scatter 

plot of the recorded annual shallow, neutron and extremity dose normalized to the recorded deep 

(photon) dose for each worker and each year is shown in Figure E-3. The shallow and deep dose is 

closely associated as would be expected because the majority of the shallow dose results from 

penetrating photon radiation.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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N-Reactor (1963-87) Worker Dose Pattern

0.001

0.01

0.1

1

10

100

1955 1960 1965 1970 1975 1980 1985 1990

Year

Recorded Dose/(Deep Dose)

Shallow/Deep

Neutron/Deep

Extremity/Deep

NTA TLD NTA Stopped

Figure E-3. Trend of recorded shallow, neutron, and extremity annual dose to 

recorded deep dose for 4,777 records with deep annual dose >0.

There is occasional high extremity dose for some workers likely associated with maintenance 

activities. There is also occasional neutron dose for some workers at generally much lower doses 

than the recorded deep dose. There also does not appear to be any significant change in the 

magnitude of the measured neutron dose prior to 1972 when either NTA or no neutron dosimeter was 

used and after 1971 when all workers were assigned the TLD which inherently measured any positive 

neutron dose. A plot of all of the data with a positive neutron dose and the NP ratio for each year of 

record is shown in Figure E-4. There is no distinct trend in the plotted data. A plot of the recorded 

annual photon dose for only those records with a positive recorded annual neutron dose is shown in 

Figure E-5. The data in Figure E-5 illustrate that there is essentially no correlation between the 

recorded neutron and photon doses overall. There are only 30 annual dose records with photon and 

neutron doses ≥30 mrem, respectively; and only 14 records for TLD only results. The explanation is 

likely that there are few occasions when workers receive a measurable neutron exposure, whereas 

significant photon dose is received in many routine work tasks including when the reactor is not 

operating and there is no neutron exposure. This was also observed by investigators analyzing a 

large amount of commercial power reactor neutron and photon measured doses (Eisenhauer and 

Schwartz 1983). All 30 of the dose results are shown in Table E-22

 2 Upon review, it was subsequently determined that a single worker was erroneously identified as a 100 N worker in 1964 

and 1965. This worker had the highest observed NP ratio but the exposure occurred at the Hanford Plutonium Facility 

prior to this worker becoming a 100N worker.

. A lognormal analysis of the 14 

TLD results is presented in Table E-3. 

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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Historical 100-N Worker Dosimeter Measured Annual Dose

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1.E+05

1960 1965 1970 1975 1980 1985 1990

Year

Annual Deep and Neutron Dose (mrem) and NP Ratio

Photon Dose

Neutron Dose

Neutron to Photon Dose Ratio

TLD

Figure E-4. Graph of N Reactor worker annual measured photon and neutron, and the calculated NP 

ratio.

Neutron Versus Photon Dose

0

100

200

300

400

500

600

700

800

900

1000

0 1000 2000 3000 4000 5000 6000 7000 8000

Photon Dose, mrem

Neutron Dose, mrem

Figure E-5. Trend of recorded photon versus neutron dose for all >0 recorded neutron 

doses.

There is only one worker (i.e., unique REX-ID) who apparently received a TLD measurable neutron 

exposure in four different years as shown in Table E-4. Recorded doses for this person for all years 

are shown in Table E-5. Table E-5 also includes the pre-1972 Site Profile options to assign neutron 

dose using the GM = 0.04 and 95th percentile = 0.08 or to utilize the lognormal statistical parameters 

(GM = 0.06, 95th Percentile = 0.4) of the 14 positive TLD neutron dose measurements. The selection 

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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Table E-2. List of N Reactor worker measured neutron and 

photon dose, ≥30 mrem, respectively.

IDa Year

Dose (mrem)

Shallow Deep Neutron NP ratio

Pre-TLD determined neutron dose

#1 1964 2,480 2,450 490 0.20

#2 1964 2,690 2,690 210 0.08

#3 1964 2,860 2,860 120 0.04

#4 1964 2,860 2,850 80 0.03

#5 1964 2,760 2,740 80 0.03

#6 1964 2,910 2,900 30 0.01

#7 1964 2,890 2,820 30 0.01

#8 1964 540 540 30 0.06

#9 1965 1,280 1,240 220 0.18

#6 1965 1,540 1,520 60 0.04

#3 1965 1,390 1,390 60 0.04

#10 1965 2,760 2,730 30 0.01

#11 1971 730 730 50 0.07

TLD-measured neutron dose

#12 1972 2,960 2,920 80 0.03

#13 1972 2,640 2,390 30 0.01

#14 1973 2,550 2,480 40 0.02

#15 1974 240 150 140 0.93

#16 1974 2,740 2,690 130 0.05

#17 1974 930 860 70 0.08

#18 1974 2,340 1,660 60 0.04

#19 1977 7,770 7,300 910 0.12

#20 1977 2,980 2,840 120 0.04

#21 1977 400 380 100 0.26

#12 1978 3,040 2,580 70 0.03

#22 1979 3,110 2,890 190 0.07

#23 1983 2,050 920 110 0.12

#3 1987 580 520 30 0.06

a. Assigned unique worker number. 

Table E-3. Lognormal statistical parameters to measured TLD neutron 

dose. 

Process No. of values GM GSD 95th-percentile Fit*

TLD Results 14 0.06 3.1 0.4 0.13

a. Kolmogorov-Smirnov test used as a measure of goodness of fit to a lognormal 

distribution.

of the statistical parameters certainly appears to be favorable-to-the-claimant based on the assigned 

neutron dose for this worker in that substantially greater neutron dose is assigned for the post-1972 

period than measured with the TLD as shown in Table E-5.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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Table E-4. Unique REX-ID worker annual dose records 

with positive neutron dose.

ID

Year of 

dose

Dose (mrem)

Shallow Deep Neutron NP ratio

#12 1972 2960 2920 80 0.027

#12 1974 3180 2930 10 0.003

#12 1977 2980 2840 120 0.042

#12 1978 3040 2580 70 0.027

Table E-5. Unique REX-ID worker measured and assigned annual neutron doses for 1964–86.

ID

Year

of dose

Recorded dose (mrem) Assigned neutron dose options

Shallow Deep Neutron GM= 0.04 95%=0.08 GM= 0.06 95%=0.4

#12 1964 1,480 1,450 0 58 116 87 580

#12 1965 2,770 2,590 0 104 207 155 1,036

#12 1966 2,460 2,460 0 98 197 148 984

#12 1967 2,130 2,130 0 85 170 128 852

#12 1968 2,920 2,920 0 117 234 175 1,168

#12 1969 2,990 2,990 0 120 239 179 1,196

#12 1970 2,760 2,760 0 110 221 166 1,104

#12 1971 2,900 2,850 0 114 228 171 1,140

Subtotal 1964–71 20,410 20,150 0 806 1,612 1,209 8,060

TLD-measured doses below Assigned neutron dose

#12 1972 2,960 2,920 80 117 234 175 1,168

#12 1973 2,760 2,750 0 110 220 165 1,100

#12 1974 3,180 2,930 10 117 234 176 1,172

#12 1975 3,320 2,870 0 115 230 172 1,148

#12 1976 2,230 2,000 0 80 160 120 800

#12 1977 2,980 2,840 120 114 227 170 1,136

#12 1978 3,040 2,580 70 103 206 155 1,032

#12 1979 2,780 2,540 0 102 203 152 1,016

#12 1980 1,470 1,170 0 47 94 70 468

#12 1981 140 100 0 4 8 6 40

#12 1983 510 500 0 20 40 30 200

#12 1984 140 100 0 4 8 6 40

#12 1985 230 40 0 2 3 2 16

#12 1986 20 10 0 0 1 1 4

Subtotal 1972–86 25,760 23,350 280 934 1,868 1,401 9,340

This data seems very limited other than it does appear that neutron dose to N Reactor workers is low 

compared to the measured photon dose considering that during the period from 1972 through 1987 

using the very neutron radiation sensitive Hanford TLD, only 14 dosimeters measured a dose ≥30 

mrem, respectively.

E7.5 DOE REIRS ANNUAL DOSE SUMMARIES 

The DOE/AEC required annual reports of the measured doses do include separation of dose 

according to a reactor facility category. The dose data for Hanford for the Reactor category and the 

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dose ranges is shown in Table E-6 according to the total measured WB dose (i.e., photon plus 

neutron). This data does not include identification of the neutron dose component only.

Table E-6. Hanford reactor category REIRS/REMS reporting.

Year Total <MDL <0.1 ≤0.5 ≤1.00 ≤2 ≤3 ≤4 >4

Total collective 

dose, person (rem)

1981 868 39 199 217 119 194 99 1 698

1980 685 15 172 159 76 136 134 2 652

1979 667 13 85 88 87 140 157 12 761

1978 583 2 129 154 48 122 168 2 721

1977 568 4 16 124 86 138 183 13 4 827

1976 542 1 12 106 100 171 138 14

1975 446 3 10 72 70 108 155 26 2

1974 390 21 45 58 82 149 30 5 679

E7.6 UNC ANNUAL EXPOSURE SUMMARIES

The 1973 and 1974 UNC annual reports received from DOE RL contain an overview of dosimeter 

measured neutron doses to workers during 1973 and 1974. This is shown in Table E-7 along with the 

measured photon dose. It is evident that the collective neutron dose is a very small fraction of the 

collective photon dose (i.e., 1973-0.2%; 1974–0.4%). The Hanford multipurpose TLD was used for 

the monthly and quarterly exchanged dosimeters (i.e., basic dosimeter likely used for annual 

exchanged dosimeter). The Hanford TLD is comparatively very sensitive to workplace neutron 

radiation (Brackenbush et al. 1980). The distribution of the measured neutron dose is shown in 

Table E-8. This data confirms that there is comparatively very little neutron dose in comparison with 

the recorded photon dose.

Table E-7. UNC annual report identified dose components.

Year

Annual dose (mrem)

Reference

Collective photon radiation dose

Month Quarter Annual Total Neutron

1973 658,830 100,240 26,000 785,090 1,330 UNI-174

1974 665,890 108,620 43,450 817,960 2,700 UNI-372

Table E-8. Neutron dose distribution for UNC annual reports.

Year

Number of workers within annual mrem dose category

<50 <100 <200 >200 Collective dose Reference

1973 13 3 5 1a Total = 1,330 mrem UNI-174

1974 56 5 2 0 Total = 2,700 mrem UNI-372

a. Maximum dose = 210 mrem

E7.7 NRC MEASURED NEUTRON AND PHOTON DOSES IN COMMERCIAL NUCLEAR 

PLANTS

During the period of N Reactor operation, there were efforts underway by the NRC to evaluate 

personnel exposures to neutron radiation in commercial nuclear reactors. Hanford GE and 

subsequently PNNL staff were involved in these efforts using Hanford dosimeters along with a 

selection of dosimeters and instruments to measure neutron spectra and dose. A summary of the 

measurements pertinent to the N Reactor were basically, that the NTA film dose results failed to 

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respond above levels needed for a positive indication of neutron dose and the TLD dosimeters 

showed a very high response that required spectral corrections for proper dose interpretation. It is 

very important to consider that these measurements were primarily conducted inside containment with 

the reactor operating at a reduced power level and would overestimate the doses received in work 

areas outside confinement at N Reactor. An evaluation was done of the potential use of the NP ratio, 

to assign a neutron dose (Eisenhouer and Schwartz 1983). Many of these dose measurements inside 

containment showed a ratio of about 1 between the measured photon and neutron dose, although 

there were some instances of much wider variation. This measured dose would tend to support the 

Hanford worker TLD measurements of a NP annual dose ratio substantially less than 1.0 in 

workplaces outside of N Reactor confinement.

E8. SUMMARY

There is comparably low level neutron dose received by some N Reactor workers on some occasions 

that was not reliably measured prior to the implementation of the thermoluminescent dosimeter on 

January 1, 1972. The photon dose was reasonably accurately measured throughout N Reactor 

Operation from December 1963 through January 1987. A feasible technical option to reconstruct a 

favorable to claimant neutron dose to N Reactor workers prior to the use of the TLD is to multiply the 

measured photon dose by a NP dose ratio. There is very little actual measured data on which to 

calculate a realistic NP ratio to be applied to the annual measured photon dose. The collective 

neutron dose during 1973 and 1974 was 0.002 and 0.004, respectively, of the collective photon dose 

measured with Hanford multipurpose TLDs. There appear to be two options. One option is to base 

the NP ratio on single worker who had TLD-measured neutron dose during 4 years (1972–0.027, 

1974–0.003, 1977–0.042, 1978–0.027) and for the other years there was no measured neutron dose 

(1973, 1975, 1976, 1979, 1980, 1981, 1982, 1983, 1984, 1985 and 1986). In this option the 50thpercentile (i.e., GM) is equal to 0.04 and to the maximum NP ratio a factor of 2 greater (i.e., 0.08) 

which is assumed in this analysis to be approximately the 95th-percentile. The second option is to 

utilize the statistical parameters for a lognormal distribution of the 14 TLD results. There is a large 

difference in the assigned neutron dose between these two options (i.e., Option #1: GM = 0.04, 95th

percentile = 0.08; Option #2: GM = 0.06, 95th Percentile = 0.4) as shown in Table E-5. Certainly, the 

most favorable to claimant option is provided using Option #2. The assigned neutron doses must also 

incorporate the ICRP Publication 60 weighting factor, which for the neutron category of 0.1 to 2 MeV 

is equal to 1.91 (ICRP 1991), and thus a further increase in assigned neutron dose of nearly a factor 

of 2 will occur.

ATTACHMENT E

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 100 AREA N REACTOR FACILITY OPERATIONS AT THE HANFORD SITE 

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TABLE OF CONTENTS

SECTION TITLE PAGE

F1. Executive Summary .............................................................................................................221

F2. Introduction ..........................................................................................................................222

F3. History..................................................................................................................................223

F3.1 200 Area Plutonium Facilities ................................................................................... 223

F4. Plutonium grade...................................................................................................................229

F5. Radiation Protection.............................................................................................................229

F6. Methods ...............................................................................................................................230

F6.1 Site Expert Interviews............................................................................................... 230

F6.2 Data Identification..................................................................................................... 231

F6.3 Data Capture............................................................................................................ 231

F7. Results.................................................................................................................................231

F7.1 Site Expert Interviews............................................................................................... 231

F7.2 Workplace Measurements of Neutron Radiation....................................................... 234

F7.3 Technical Reports..................................................................................................... 234

F7.4 Radiation Survey Data.............................................................................................. 237

F7.5 Analysis of NP Ratio Measurement Data.................................................................. 237

F7.6 Recommended NP Ratios ........................................................................................ 247

LIST OF TABLES

F-1 NP ratio determined from 1971 workplace study of neutron dose 

measurements ..................................................................................................................... 235

F-2 Summary of 1981 Hanford workplace neutron dose measurements .................................... 236

F-3 Summary of 1982 Hanford workplace neutron dose measurements .................................... 236

F-4 200 Area workplace measurement comparisons with HMPD ............................................... 237

F-5 SRDB references containing neutron and photon dose survey 

measurements ..................................................................................................................... 238

F-6 Hanford 200 Area plutonium facility NP ratio survey records................................................ 239

F-7 1972 AEC NP ratios used to reconstruct maximum worker dose.......................................... 241

F-8 Statistical parameters for lognormal distribution for the respective 

selections of NP ratio measurement data............................................................................. 243

F-9 Illustration of assigned dose to long-term PFP worker.......................................................... 248

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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LIST OF FIGURES

F-1 Timeline of Hanford plutonium plant facilities and operational changes................................ 224

F-2 Hanford plutonium production .............................................................................................. 230

F-3 Variation in measured neutron and photon dose rates with distance, and 

the associated calculated NP ratio ....................................................................................... 238

F-4 1,419 measured NP ratios in Hanford 234-5Z plutonium facility ........................................... 240

F-5 Scatter plot of 1,346 measured neutron and photon doses .................................................. 242

F-6 Lognormal probability plot of 1,419 measured NP values..................................................... 242

F-7 Radiation control report instrument measured monthly neutron dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-8 Radiation control report instrument measured monthly photon dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line 

and other line workplace locations during the period of 1963 to 1976 .................................. 244

F-9 NP ratios calculated from the data contained in Figures F-5 and F-6 ................................... 245

F-10 Correlation of TLD measured neutron and photon doses ..................................................... 246

F-11 Lognormal probability plot for TLD measured neutron-photon ratios .................................... 246

F-12 Fluorination 7C/9B and 7A/9A hoods instrument and worker TLD NP ratio 

measurements ..................................................................................................................... 247

F1. EXECUTIVE SUMMARY

The neutron to photon dose (NP) ratio distribution presented in the 2003 Hanford ORAUT-TKBS0006-6 External Dose Technical Basis Document (TBD-6) has been updated using substantially 

greater data than available in 2003. Analyses in 2003 used 186 thermoluminescent dosimeter (TLD) 

measured neutron and photon doses (respectively ≥ 20 mrem) that had been obtained from dosimetry 

records submitted by DOE Richland for Hanford claims existing in 2003. The available data currently 

consists of 1,419 selected TLD and instrument measured NP ratio records that have been obtained 

from the extensive DOE Richland archives of historical documentation. Based on this expanded data, 

the recommended dose reconstruction parameters to be applied for 200 Area plutonium workers are:

• TLD measured neutron dose should be used from January 1, 1972 to date. 

• Prior to 1972, the measured (and missed) photon dose should be multiplied by a NP ratio to 

arrive at an assigned neutron dose.

The recommended favorable-to-claimant NP ratios are:

• For glovebox workers, the guidance in OCAS-TIB-010 for plutonium glovebox workers should 

be applied.

• Consistent with OCAS-IG-001 (2007) guidance, the measured and assigned neutron doses 

must incorporate the ICRP Publication 60 weighting factors for the respective neutron energy 

categories in Hanford plutonium workplaces (ORAUT-OTIB-0055) (i.e., < 0.01 MeV = 2.13, 

0.01-0.1 MeV = 1.86, 0.1–2.0 MeV = 1.91). 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

Page 1 of 4

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Process GM GSD 95th-percentile

Non-glovebox worker 1.1 2.3 4.5

Glovebox worker 1.7 2.6 7.9

Applying these NP ratios will result in significant assigned neutron dose prior to 1972.

F2. INTRODUCTION

The purpose of this attachment is to update the technical basis for neutron dose reconstruction for 

Hanford 200 Area Plutonium Facility Workers based on additional workplace measurement data 

obtained since preparation of the original TBD-6 in 2003. As described in TBD-6 (2003), neutron 

radiation exposures to workers in the Hanford 200 Area Plutonium Facilities were not accurately 

measured using personnel dosimeters prior to implementation of the Hanford thermoluminescent 

personnel dosimeter (TLD) on January 1, 1972. Prior to January 1, 1972, Hanford used four general 

methods (Wilson 1987) to measure and control neutron exposure to workers as follows:

1. 1940s to present: Workplace surveys using portable neutron radiation responsive instruments 

and time-keeping.

2. 1940s to present: Pocket Ionization Chambers (PICs) with originally a boron liner and later of 

other radiation sensitive materials. 

3. 1950 through 1971: Eastman Kodak Nuclear Track Emulsion, Type A, (NTA) personnel 

neutron film beginning in 1950 with three different Hanford neutron personnel dosimeter 

designs (two-element, 1958 multi-element and 1962 multi-element).

4. 1954 to ~1972: Measurement and control of worker photon exposure to Hanford Operational 

dose limits (3 R/y) with the expectation that the total whole body dose (photon plus neutron) 

would be less-than Hanford official dose limits (5 rem/y). 

These methods were used jointly to measure and control worker radiation exposures since 

dosimeters in Method #3 do not provide capabilities for effective workplace exposure control. 

Dosimeters were exchanged on a routine weekly, biweekly, monthly, or quarterly schedule with dose 

results received long after radiation exposure has been received. There are records of dose 

assessments with Methods #1 and #2 but it is not certain that the neutron doses were incorporated 

into the official Hanford radiological records in instances where NTA dosimeter results are less-than 

doses determined from Methods #1 or #2, or if NTA dosimeters were not used. Method #4 was 

incorporated in 1954 into Hanford Operational Radiation Protection Standards as discussed under 

Hanford Radiation Protection Standards in Attachment D of this document. This method has an 

implied bound on the ratio of the neutron to photon dose (i.e., 5 rem/3 R = 1.7) which was adopted to 

ensure Hanford workers did not exceed annual radiation protection dose limits. Based on the neutron 

dose record for the Hanford Worker Health and Mortality Study (Buschbom and Gilbert 1993) which 

includes essentially all Hanford workers employed with a primary Hanford contractor for a period 

longer than six months, there is no recorded neutron dose prior to 1950. The judgment in TBD-6 

(2003) that the neutron dose is underestimated for workers at the Hanford 200 Area plutonium 

facilities prior to 1972 is consistent with findings of an AEC/HQ technical committee investigation 

conducted in 1972 involving dosimetry experts from other AEC sites and Hanford (Biles 1972). This 

investigation was conducted because of the significant increase in measured neutron dose with the 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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TLD compared to the NTA film (Fix et al 1997b). There is a set of files that contain NTA processing 

results for Hanford workers issued NTA film during the period of 1950 through 1961 (SRDB 38336) 

and additional years of records are available in DOE Richland record archives in the Seattle Federal 

Record Center. A timeline of significant events at Hanford associated with radiation protection of 200 

Area plutonium workers is presented in Attachment D, Table D-2. 

2003 Site Profile Neutron Dose Reconstruction Recommendations

TBD-6 (2003) recommended for 200-Area Plutonium Facility worker neutron dose reconstruction that:

• TLD measured neutron dose be used from January 1, 1972 to date. 

• Prior to 1972, the measured (and missed) photon dose is multiplied by a neutron-to-photon 

dose ratio to arrive at an assigned neutron dose. The parameters of the 2003 determined 

neutron-to-photon dose distribution using available TLD dose measurements from claims were 

a geometric mean (GM) of 0.73, a geometric standard deviation (GSD) of 2.10 and a 95thpercentile of 2.47.

F3. HISTORY

The history of neutron radiation exposure to workers in Hanford 200 Area plutonium facilities extends 

to the beginning of the respective chemical processing and plutonium chemical/metallurgical facilities 

that produced plutonium. Radiation exposure hazards to workers in Hanford plutonium facilities 

increased slowly in proportion to the increasing amount of 239Pu fissile material handled. In the 

earliest years, the comparably small quantities of 239Pu were not fully converted to usable product 

forms at Hanford but rather provided to Los Alamos in the form of a nitrate paste. Hanford workers 

began processing the plutonium nitrate in the 234-5 Building Rubber Glove (RG) Line on July 5, 1949. 

A timeline of the expanding capabilities is shown in Figure F-1. There was substantial pressure 

during the 1950-60s for Hanford to meet 239Pu production targets as a crucial component of the 

national mission to develop a wide array of nuclear weapon capabilities. Hanford was involved in a 

broad range of nuclear research activities regarding reactor fuels, reactor designs, spent fuel 

processing, nuclide recovery from waste, plutonium metrology, and fissile materials in support of the 

national mission. A description of significant events as noted in Hanford documents is presented in 

Attachment D, Table D-2. 

F3.1 200 AREA PLUTONIUM FACILITIES

ORAUT-TKBS-0006-2 describes the various Hanford plutonium facilities and the respective operating 

histories. The facilities can be divided according to: 

1. Supporting Facilities involved in testing processes, handling waste or preparing plutonium 

bearing solutions for delivery to the Hanford Plutonium Finishing Plant (PFP) as follows:

200-East Area

• 209-E, Critical Mass Laboratory (Hanford critical mass laboratory facilities were also 

located in the 100 [120 Bldg] and 300 [326 Bldg] Areas and these operations are examined 

in Attachment G “Bounding Estimate of Neutron Dose Based on Measured Photon Dose at 

Hanford 300 Area and Miscellaneous Facility Operations at the Hanford Site.” 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

Page 5 of 30

Figure F-1. Timeline of Hanford plutonium plant facilities and operational changes.
Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 225 of 265

• 202-A PUREX Processing Plant N-Cell

• 224-B Plutonium Concentration Facility

200-West Area

• 216-Z-9 Covered Crib Facility

• 224-T Plutonium Concentration Facility

• 233-S REDOX Plutonium Processing Facility

2. Primary PFP Facilities involved in handling plutonium products include: 

• 231-Z Plutonium Isolation Facility

• 232-Z Incinerator Facility

• 234-5Z Plutonium Finishing Plant Complex

• 236-Z Plutonium Reclamation Facility (PRF)

• 242-Z Waste Treatment Facility

• 2736-Z Plutonium Storage Vault

There was intended duplication in capabilities among these facilities and between the 200-

East and 200-West facilities. An approximate chronological history of the 200 Area facilities 

and a description of operations are provided in the following sections.

224-B, -T Concentration Buildings. The Hanford Irradiated Fuel processing capabilities originally 

involved the T, B and U Process Groups of buildings. The T Group consisted of the 221-T Building, 

also known as T-Plant or T-Canyon, which began operations in the Hanford 200 West Area on 

December 26, 1944 dissolving irradiated uranium fuel from the Hanford B-Reactor using a bismuthphosphate chemical separation process. The operation was a batch, precipitation process that 

achieved separation of the plutonium by repeatedly dissolving and centrifuging plutonium-bearing 

solutions. The Hanford B Process Group facilities were built in the Hanford 200 East Area consisting 

of the 221-B Building (or B-Plant), 224-B Concentration Building and associated facilities also using 

the bismuth-phosphate chemical separation process that began operations on April 13, 1945. The 

Hanford U Process Group (221-U, 224-U) was built in the Hanford 200W Area but never dissolved 

irradiated uranium reactor fuels. The respective 224-T or -B Building received the plutonium bearing 

solution from the corresponding T or B processing plant through an underground pipe tunnel. The 

dilute plutonium solution was processed in batches with a starting volume of about 330 gallons that 

underwent several chemical steps to reduce volume, achieve higher purity plutonium, and eventually 

to form the plutonium nitrate that was transported to 231-Z in the early years and later to 234-5Z. The 

potential for neutron exposure to Hanford workers at these facilities handling plutonium solutions was 

similar to the transportation of plutonium nitrate among Hanford facilities. 

231-Z Plutonium Isolation Building. The 231-Z, Plutonium Isolation Building, began the plutonium 

finishing process during January 1945 when the first plutonium nitrate solution was received (Lini, 

2008) Throughout the early years, the mission of the 231-Z facility was to receive plutonium nitrate 

from the 224-B and 224-T facilities and to conduct further chemical treatment to purify the product. 

The eventual Hanford-produced plutonium nitrate (a “super-dried” thick paste) was placed in special 

shipping cans for transfer to Los Alamos prior to the construction of the Hanford 234-5Z facility to 

convert plutonium nitrate to plutonium metal. In later years, the 231-Z building was used for piece 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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fabrication until about December 1965 and subsequently for metallurgical research. In the early 

years, the potential for neutron exposure to workers was associated with handling plutonium nitrate. 

In approximately 1956, the mission of 231-Z changed to a spectrum of plutonium chemical and 

metallurgical processes with significant potential for neutron exposure to workers.

234-5Z Plutonium Facility RG Line. Construction of the Hanford 234-5Z Plutonium Purification and 

Fabrication Building began in 1948. The original 234-5Z plutonium finishing equipment was termed 

the “RG” (Rubber Glove) line because its operation depended on personnel working with gloveboxes 

and manipulating the Pu mixtures through rubber gloves that served as contamination barriers. The 

RG Line was composed of 28 stainless steel hoods, and measured 180 feet in total length. “Hot” 

processing (i.e., processing using Pu nitrate as feed) in the 234-5Z Building RG Line began July 5, 

1949. The basic plutonium finishing operations consisted of several standard steps known as “Tasks” 

as follows:

• Task I, Purification or Oxalate Precipitation (also known as Wet Chemistry or Feed 

Preparation), consisted of precipitating the Pu nitrate feed solution with oxalic acid and other 

agents. 

• Task II, Hydrofluorination (also called Dry Chemistry in the very early years), hydrogen fluoride 

gas was diffused through the precipitate at a very high temperature in a furnace, producing a 

plutonium tetrafluoride powder. 

• Task III, Reduction, the plutonium tetrafluoride was combined with calcium metal, a small 

percentage of other agents and fired at very high temperature, under an inert atmosphere, 

until it fused or “reduced” into Pu metal. The metal was produced in chunks roughly the size 

and appearance of a hockey puck and were known as “buttons.” 

• Task IV, Casting, the plutonium metal was then rendered molten and ingoted, and cast into a 

mold roughly approximating one-half of the desired “pit.” 

• Task V, Machining, the pit was formed and lathed to precise, specified dimensions.

• Task VI, Cleaning in which the pit is chemically cleansed.

• Task VII, Coating, the plutonium metal pit was placed on a tripod and coated with nickel using 

carbonyl gas through three separate applications to make sure that all portions of the bare Pu 

metal were covered. This coating served as a contamination barrier during inspection, 

transport and storage. 

• Task VIII, Final Inspection, the pit was measured for thickness, uniformity of coating, neutron 

energy, isotopic content, dimensional precision, and cracking. 

• Tasks IX through XIV were identified as topics, not actual process steps. Instrumentation was 

Task IX, Control was Task X, Ventilation was Task XI, the Conveyor System (not present in 

the RG Line, but present in later 234-5 Building process lines) was Task XII, Maintenance of 

equipment was Task XIII, and Sampling was Task XIV.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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ATTACHMENT F

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AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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234-5Z Plutonium Facility RMA Line. Even as processing using the RG Line was begun in the 

Hanford 234-5Z Building, efforts were underway to design a line that would operate remotely, in a 

mechanized manner or what was termed a Remote Mechanical (RM) line. The Remote Mechanical A 

(RMA) Line commenced hot operations on March 18, 1952 and performed all of the process steps in 

Pu metal production and fabrication except for Task I (feed make-up and purification). In early 1953, 

in response to the rapidly growing demand for increased plutonium production, the decision was 

made to “modify and expand” the RMA Line. In May, various design proposals coalesced into two key 

projects:

1. Activation of Task I focused on building into the RMA Line a new Task I process capable of 

bypassing the precipitation and purification activities then being carried out in Hanford’s 231-Z 

Isolation Building. 

2. Expansion of Building 234-5Z focused on a sweeping series of revisions to Task II and III 

(hydrofluorination and reduction), aimed at increased production and efficiency in the facility. 

During January and February of 1955, 234-5 production operations were shut down to enable 

modifications and new equipment to be installed for these two projects. The RMA Line then ran until 

mid-1957, when it was again closed briefly to install and activate equipment for Project GC-691, 

Improved Task I and Task II Facilities. This project installed a continuous calcination and 

hydrofluorination process that essentially combined the flow of Task I and II.

The RMA Line consisted of a row of 30 interconnected stainless steel glove boxes (e.g., hoods), 30 

control desks, 10 control cubicles, 24 instrument panels, nine resistance furnaces, five induction 

furnaces, a sample can handling assembly, a 110-foot long general conveyor and manipulator, other 

smaller conveyors and furnace loaders, and miscellaneous support equipment. It was located in six 

rooms in the 234-5 Building.

234-5Z Plutonium Facility Recuplex. The Recovery of Uranium and Plutonium by Extraction Facility 

(RECUPLEX) solvent extraction process was developed to recover plutonium from 234-5 waste such 

as slag and crucible fragments, scrap powders from RMA line operations, oxidized plutonium turnings 

from Task V, and remnants from metal samples. The RECUPLEX facility began operation in July 

1955. In April 1962, a criticality accident occurred resulting in high external radiation exposures to 

several workers. In May 1962, the AEC decided to deactivate this section of the 234-5Z Facility.

234-5Z Plutonium Facility RMC Line. Operations with the RMC Button Line and the RMC 

Fabrication Line with radioactive materials began in 1960. The RMC Line (both the button and 

fabrication components) consisted of a completely self-contained, remotely operated series of 

gloveboxes very similar to the RMA Line. Like the A Line, C Line functioned to convert Pu solutions to 

metal and then to fabricate actual pieces from the metal. It differed from the RMA Line in that it had 

an automatic vacuum cleaning system that served Tasks I-IV, greater radiation shielding, and 

improved radiography facilities. The RMC Line was placed where the former RG Line (removed in 

1957) had stood. Associated PFP upgrades in the late 1950s and early 1960s included fire protection 

improvements, strengthening and refurbishing of the vacuum and exhaust systems, shielding 

upgrades, multiple waste management projects, improved plutonium storage facilities, laboratory 

modifications, and modifications to the Metallurgy Laboratory production equipment. The fabrication 

program concluded at PFP in December 1965. Shutdown of the fabrication portion of the RMA and 

RMC Lines (Tasks V onward) was undertaken immediately and essentially completed in March 1966. 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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The metal conversion portions of the RMC Line (Task I-III) continued to operate, while Task IV was 

converted to bag-out and sealing for shipment operations. The RMA Line was taken out of service 

completely. It remained closed until 1968, when Tasks I-IV equipment was cleaned out and reactivated to participate in PFP programs that prepared plutonium oxides in specified, tailored blends 

for commercial nuclear experiments and development. From that time forward, the A Line became 

known as the “oxide line” and the C Line became known as the “metal line.”

As PFP participation in fabrication was declining, initiatives were undertaken to support commercial 

nuclear industry needs. In late 1962, the AEC first investigated the feasibility and costs associated 

with receiving, storing and disbursing power reactor grade (”fuels grade”) plutonium. The plutonium 

recycle concept was being tested at the 309 Building Plutonium Recycle Test Reactor (PRTR). 

During 1965-66, receiving, re-packaging and storage facilities were built into the 234-5Z Building as 

the Plutonium Buy-Back Facility. This project was completed in May 1966. In the meanwhile, 

production of specially blended, non-defense Pu oxide for EURATOM (European Atomic Energy 

Community–a consortium of the governments of France, West Germany, Italy, the Netherlands, 

Belgium and Luxembourg) for commercial nuclear power development was begun in the PFP in 

September 1964. That same year, the 234-5Z Building began supplying non-defense Pu (known as 

“unclassified Pu”) nitrate or oxide to Hanford’s 209-E Critical Mass Laboratory for experimental 

purposes. 

The RECUPLEX criticality accident during April 1962 led to deactivation of this area of the 234-5Z 

Building. During the 1970s, PFP operations continued to support the commercial nuclear industry, 

nuclear research customers and foreign nuclear customers until shutdown of PUREX in 1973. During 

this time PFP continued producing plutonium metal buttons that were sent to the DOE Rocky Flats 

Plant. The mid- and late-1970s were devoted largely to facility upgrades and to projects that achieved 

better control of effluents. During 1974-75, the Division of Military Application (DMA) equipment was 

removed from the PFP and disposed. This equipment included glove boxes from the A and C Lines.

In 1984 and 1985 respectively, the PRF and the RMC-Line re-opened in response to the late 1983 restart of the PUREX Plant and the defense materials build-up ordered by President Reagan. Both 

facilities operated several campaigns on an as-needed basis until the PRF was permanently shut 

down in December 1987 and the RMC Line was permanently shut down in June 1989. 

202-A Purex N-Cell and Redox 233-S Facility. The T- and B-Plant Reprocessing facilities were 

replaced with the more efficient continuous feed (i.e., not a batch process) reduction oxidation 

process (REDOX, 200 West Area, operation began January 1952) and plutonium uranium extraction 

(PUREX, 200 East Area, operations began January 1956) separation facilities. Plutonium nitrate was 

produced in the Redox (S-Plant) 233-S Facility and Purex (A-Plant), and transported to the 231-Z 

Plant or directly to 234-5Z following completion of Task I precipitation and purification capabilities 

incorporated into the RMA Line. Later, some plutonium oxide was produced in the N-Cell at Purex. 

216-Z-9 Covered Crib Facility. Several soil disposal cribs were constructed and used near 231-Z 

and 234-5Z for discard of plutonium-bearing liquid waste solutions. Most notably, the 216-Z-9 below 

grade covered crib facility received about one million gallons of plutonium solvent extraction waste 

effluent from 1955 to closure of the crib in 1962. During the mid-1970s, plutonium contaminated soil 

in the Z-9 crib just south of the PFP was mined and partially remediated. 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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232-Z Incinerator Facility. The 232-Z incinerator began processing miscellaneous solid wastes to 

recover small quantities of plutonium in January 1962. The process involved incineration of

combustible materials, leaching noncombustible materials in nitric acid, and wet leaching of ash. The 

recovered plutonium was transferred to RECUPLEX and later the Plutonium Reclamation Facility. 

The 232-Z facility operations were terminated in 1973.

242-Z Waste Treatment Facility. The 242-Z facility was placed into operation in 1963 to recover 

plutonium from aqueous waste streams from the PFP. An 241Am recovery process was installed in a 

glovebox in 242-Z and began operation in May 1965. The product was americium nitrate. In 1969, 

equipment was installed to convert the 241Am recovery operation from a batch to a continuous process 

and to increase the purity and concentration of the americium product. In August 1976 an explosion 

occurred with subsequent permanent shut down of the 242-Z facility. 

236-Z Plutonium Reclamation Facility (PRF). The 236-Z facility was placed into operation in May 

1964 to recover plutonium from liquid waste generated in the plutonium finishing plant operations. 

This facility was shut down in December 1975 for maintenance upgrades and reviews of criticality 

safety specifications and procedures. In 1976, PRF operated for only a short time after restart until 

the explosion in 242-Z resulting in shutdown of the facility during April 1976. The facility was cleaned 

up and operated in 1977 to process available plutonium, and later in the 1980s was operated again.

2736-Z Plutonium Storage Vaults. The 2736-Z Plutonium Storage vaults were finished during 1972-

73 and used to store plutonium.

F4. PLUTONIUM GRADE

An important consideration in the analysis of neutron exposure to workers in relation to the photon 

dose concerns the specifics of the type of fuel (i.e., uranium natural or level of 235U enrichment, mixed 

uranium and plutonium oxide or thorium) and the reactor exposure time in megawatt-days (MWD) 

because this is directly associated with the isotopic composition of the plutonium handled at PFP. 

There are also issues associated with the effectiveness of the respective T-Plant, B-Plant, REDOX 

and PUREX processing with respect to the type and concentration of potential contaminants (e.g., 

zirconium, ruthenium, etc.) as well as inventories handled at PFP associated with Buy-Back Program 

and various national and international research activities. Broadly speaking, the plutonium is 

categorized as weapons or reactor (or fuel) grade as shown in Figure F-2 (note: the production total 

in 1947 is actually the total production during 1944-47). Worker neutron exposure is highly associated

with the concentration of 240Pu which increases in the irradiated fuel with the total exposure (i.e., 

megawatt-days). Reactor grade fuel typically receives much higher exposures as compared to 

weapons grade fuel and will result in higher exposures to workers. 

F5. RADIATION PROTECTION

A description of Hanford radiation protection standards, procedures and practices is described in 

Attachment D along with a historical review of applicable radiation protection limits in Table D-1 and a 

timeline of radiation associated events in Table D-2.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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ATTACHMENT F

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Hanford Pu Production

0

500

1,000

1,500

2,000

2,500

3,000

3,500

4,000

4,500

5,000

1945 1950 1955 1960 1965 1970 1975 1980 1985 1990

Year

Pu Production (kg)

Weapons Grade

Fuel Grade

Figure F-2. Hanford plutonium production (DOE/DP-0137, Plutonium: The First 50 

years).

F6. METHODS

There are several documented historical analyses of neutron exposure received by Hanford workers. 

In the earliest years during the 1940s and 1950s there was concern primarily for the potential dose to 

the hands of workers in the plutonium facility. The extent and primary findings from these studies can 

be viewed according to the publication date of the respective studies in Attachment D, Table D-2. 

Studies performed in the 1950 and 1960s were primarily motivated by a concern that the total whole 

dose limits (shown in Attachment D, Table D-1) were not exceeded. 

F6.1 SITE EXPERT INTERVIEWS

Interviews with Site Experts were conducted and documented regarding their assessment of the 

potential for significant neutron exposure of Hanford 200 Area plutonium facility workers, the potential 

work areas, and work tasks. Tours of the Hanford 234-5Z facility and the 231-Z facility were made 

during June and November 2008 with persons with expert knowledge of Hanford plutonium facility 

design and operation. The respective site experts were asked to provide information concerning:

• Their knowledge of workplace radiation levels at the respective plutonium facilities, methods of 

measurement, exposure control practices and particularly information concerning significant 

neutron exposure.

• Their knowledge concerning changes in plutonium facility construction and/or operations 

important to understanding the applicability of statistical parameters determined from TLD 

measured doses to the pre-1972 period.

ATTACHMENT F

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AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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• Their knowledge concerning performance of workplace surveys and particularly feasibility of 

access to the documented surveys, access to the plutonium facility worker measured doses, 

and specifically access to the measured TLD measured neutron and photon doses during the 

period of 1972 through 1987.

• Their knowledge concerning any other information that may be relevant to the reconstruction 

of neutron dose to Hanford 200 Area plutonium facility workers prior to 1972. 

F6.2 DATA IDENTIFICATION

There are extensive Hanford historical records of instrument survey results of photon exposure rate 

and contamination levels (i.e., instrument alpha and beta radiation surveys) in the 200 Area plutonium 

facility workplaces, and personnel beta/photon dosimeter measured doses. An Excel database is 

available that shows the assignment of NTA dosimeters to Hanford workers according to operating 

area during the period of 1950 through 1961 (SRDB 23028). Typically, a brief description of the 

relevant data is included in Attachment D, Table D-2. The survey results were primarily used for 

defining workplace radiological control zones and workplace hazards such as in the preparation of the 

Special Work Permits (SWPs) which number into many tens of thousands each year. Data searches 

of the various DOE Hanford archive record systems was done using numerous combinations of words 

or abbreviations “survey,” “control,” “neut,” “NTA,” “A-film,” repetitive, etc., associated with neutron 

radiation or monitoring surveys, neutrons, nuclear track emulsion, Type A (NTA) film, A-film, routine 

and repetitive (R&R) surveys. Substantial efforts have been made to find actual original records of 

instrument measured photon and neutron doses done at the same time and location (i.e., paired 

data).

F6.3 DATA CAPTURE

Data capture trips to DOE Richland with the expressed objective to obtain detailed monitoring data 

occurred during: April 18-19, 2007; September 18-20, 2007; October 9-15, 2007; December 2-7, 

2007; June 2-6, 2008; July 7-11, 2008; September 22-26, 2008; October 13-17, 2008; and November 

17-24, 2008. Keyword searches were conducted of the multiple Hanford record systems by DOE 

Richland, DOE Hanford contractors and ORAUT staff using DOE Richland-provided database indexes 

to identify pertinent technical reports, survey forms and correspondence. Prior to these data collection 

trips, record indexes were received from DOE Richland and used in the prioritization of records of 

interest for workplace photon and neutron fields. A large number of boxes and documents were 

identified that potentially contained relevant records. The contents of these boxes and documents 

were reviewed during the respective data collection trips. 

F7. RESULTS

F7.1 SITE EXPERT INTERVIEWS

Interviews with several Hanford Site experts were performed with the objective to identify potentially 

relevant information regarding the significance of photon and neutron radiation exposure and to the 

feasibility of dose reconstruction. Questionnaires were developed in conjunction with the respective 

interviews and used in the interview documentation. Each of these documented interviews was 

submitted to DOE for classification review. Abbreviated results from the respective interviews are 

described in the following:

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Site Expert 1 (Fix 2008b). Documented interview with Hanford Site expert hired at Hanford in June 

1951 with several site roles in chemistry and radiation protection, including dismantling the RG line in 

the 234-5Z Building. Site expert also provided special training for operators and monitors involved in 

plutonium work. Expert was one of the first persons to use the DePanger double moderator neutron 

counter for workplace neutron measurements and was involved in the development of improved 

monitoring and dosimetry capabilities.

Site Expert 2 (Fix 2008c). Documented interview with Hanford Site expert hired at Hanford in 1959. 

Site expert worked in the 308 Building making and performing quality assurance measurements on 

plutonium-aluminum coextruded fuel elements. Site expert participated in investigations of radiation 

exposure issues associated with processing of Hanford higher exposure plutonium and the increase 

in the gamma dose rate with plutonium isotopic composition, age since separation, and glovebox 

through-put. Site expert has performed neutron dose and spectra measurements at several Hanford 

and other DOE laboratory workplaces and was the lead technical author of a DOE complex analysis 

of personnel neutron dosimetry in DOE facilities.

Site Expert 3 (Fix 2008d). Documented interview with criticality safety expert who began 

employment at Hanford during October 1948 and, during the period from approximately 1952 to 1959, 

was tracking plutonium production units through the plutonium product lines. Expert recalled the 

philosophy that the highest dose rates were primarily dependent on the mass of plutonium. So it 

followed that spills, dust coating the equipment, residual powder in corners, etc., should be kept to a 

minimum to keep dose rates low. Hood cleanups were made accordingly. Expert recalled that 

visibility into the powder processing gloveboxes was sometimes a problem. Expert said it was 

common knowledge that the PuF4 gloveboxes were the highest neutron dose rate areas. In dealing 

with dose rates, there is another factor that might not have been considered regarding the powder pan 

and the button storage conveyors. These were down around Tasks II and III. The powder pans were 

part of the RMC and held PuF4 batches. The storage areas held many plutonium units and would be 

expected to have commensurate higher exposure.

Site Expert 4 (Fix 2008e). Documented interviews with Hanford Site expert who spent several years 

providing technical health physics support to the PFP, where he was involved in reviewing procedures 

and work plans for compliance with Hanford radiological standards and practices. Expert maintained 

a detailed monthly radiological protection performance report for plant management and support 

organizations. Site expert participated in Readiness Reviews for the restart of the PRF and the RMC 

Line. Site expert also supported operation and outages at all 100 Area reactors; charge, discharge, 

storage and shipment of irradiated fuel elements; and control room assistance for reactor startup and 

operation.

Site Expert 5 (Fix 2007c). Documented interview with Hanford Site expert hired at Hanford in June 

1956 who worked in various research activities such as in the 326 Building Exponential Pile Physics 

Laboratory and in 326 Building working with radiation sources such as 238PuBe, developing neutron 

spectrometer capabilities, performing work to characterize the NTA energy response, and working to 

develop TLD systems. Expert had several non-Hanford project roles including a multiyear NRC 

Project to measure neutron spectra and dose in U.S. commercial nuclear reactors, which is described 

in several NUREG reports.

Site Expert 6 (Fix 2008f). Documented interview with Hanford Site expert hired at Hanford in 

February 1959 who worked on 234-5Z personnel exposure issues such as extremity dose, dosimetry 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

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systems, and instrument capabilities. Expert described measurements at Hanford in which photon 

dose rate was measured with a CP and, for neutron radiation, the Snoopy and DePanger double 

moderator was used. The Snoopy was often used because the signal could be integrated for an 

extended measurement, thereby obtaining a better result. The Long Counter was used to measure 

neutron yields and was used during measurements at the Hanford 234-5Z and 308 Buildings as well 

as many other DOE sites. TEPC and personnel dosimeters were also used. Expert has been

involved in various national committees, projects, etc., and has been involved in neutron and photon 

spectra and dose measurements at numerous DOE sites. Expert was a primary author of the original 

DOE Good Practices Standard in Plutonium Facilities.

Site Expert 7 (Fix 2007f). Documented interview with Hanford Site expert hired at Hanford in 1947 

who worked with health physics instruments and later managed Hanford site-wide personnel radiation 

dosimetry and radiological records projects.

Site Expert 8 (Fix 2008g). Documented interview with Hanford Site Expert hired at Hanford in June 

1948 who worked with technical function tests, calibration and distribution of health physics 

instruments to the 100, 200, and 300 Areas. The results of these tests were documented. Expert 

mentioned that the calibration technicians were actually receiving significant exposures and steps 

were taken to build a Well calibration facility whereby the technicians were not directly exposed to the 

calibrating source. Expert was directly involved in 234-5Z Building radiation exposure measurements 

and efforts to resolve radiation exposure problems that existed in the 234-5Z and 231-Z Buildings. 

Expert recalled being involved in "time and motion studies" to determine the length of time required to 

do specific tasks. Expert wrote many Hanford technical reports and subsequently was involved in 

national and international measurements of radiation.

Site Expert 9 (Fix 2007b,g). Documented interviews with Hanford Site expert involved in radiological 

physics issues throughout his career, handling issues such as personnel dosimeter performance, 

calibration, and, in particular, neutron radiation measurements using, for example, the DePanger 

Precision Long Counter developed at Hanford. The Long Counter was used to evaluate the neutron 

fluence when health physics dosimeters or health physics instruments were irradiated. The DePanger 

double moderator instrument was invented for monitoring neutron dose in the workplace. The 

instrument could measure a ratio that could be applied to the measurement to get the correct neutron 

dose as a function of neutron energy. Expert spent significant time in 100 Area reactors (i.e., B, D, 

KE, KW, N, and perhaps F), 200 Area plutonium facilities, and 300 Area accelerator facilities, which 

were used to evaluate all Hanford neutron instrument and dosimeter systems. Expert stated that the 

original values to reconstruct 234-5Z worker exposures in the 1972 AEC investigation depend on the 

method used to determine the ratios from the TLD data. For example, the calibration with the TLD 

implemented in 1972 involved consideration of the combined phantom and dosimeter neutron 

response because of the so-called albedo effect. The TEPC was used to evaluate the TLD response

on-phantom at 234-5Z workplaces and to use this in the development of the routine neutron 

calibration. Fundamentally, the distance of the midpoint of the phantom from the Hanford calibration 

source was used in routine calibration exposures and not the distance from the dosimeter mounted on 

the phantom to the source.

Site Expert 10 (Scalsky 2007b). Documented interview with Hanford Site expert involved in the 

Hanford personnel dosimetry program beginning in the mid-1950s. Expert had numerous radiation 

safety individual contributor and management roles in the centralized Hanford radiological services 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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organization involving calibrations, radiation standards and engineering, and radiological records and 

in AEC/DOE-HQ health physics programs.

Site Expert 11 (Fix 2008h). Documented interview with Hanford Site expert hired at Hanford as a 

process engineer in July 1969 working throughout his career primarily in Hanford 200 Area production 

operations such as 234-5Z. Expert’s responsibilities included analyses of radiation exposures with 

respect to process source material and options, and personally gathered a few years of monthly PFP 

button line production and dosimetry records for evaluation of worker exposure and process options.

Site Expert 12 (Fix 2008i). Documented interview with Hanford Site expert who worked as an 

engineer and production supervisor at PFP during the period from 1956 through 1994.

Site Expert 13 (Scalsky 2007a, Fix 2008l). Documented interview with Hanford Site expert hired for 

work at Hanford plutonium facilities in 1947. Expert worked in all Hanford areas during his career, 

participated in activities associated with the AEC 1972 Investigation of the increase in TLD-measured 

worker neutron doses in comparison with the NTA measured doses. Expert wrote numerous 

technical reports including historical reviews of the Hanford radiation dosimetry program.

Site Expert 14 (Fix 2007e). Documented interview with Hanford Site expert hired at Hanford in 1950 

for work in radiation protection with primary responsibilities in the 200 and 300 Areas, and as the HP 

assigned to 100 Area biology operations. Later, this expert assumed responsibilities for Hanford sitewide compliance with AEC/DOE H&S orders, directives, etc., as a senior health physicist.

F7.2 WORKPLACE MEASUREMENTS OF NEUTRON RADIATION 

The respective boxes of DOE Richland archival records available from the federal repository in 

Seattle generally contain either technical reports or data of one type or another. Technical reports in 

which data have been gathered and analyzed are particularly helpful and tend to minimize uncertainty 

in the overall analysis.

F7.3 TECHNICAL REPORTS

Numerous boxes containing Hanford technical reports and workplace radiation survey sheets were 

reviewed by a team of health physicists. Several Hanford documents were identified that contained 

paired neutron and photon radiation survey data as follows:

• Early 1950s reports of radiation measurements of Hanford 231-Z and 234-5Z processes that 

collectively provide information regarding relative neutron and photon doses.

• Routine quarterly publications entitled “Radiation Control Report” for the Hanford 231-Z and 

234-5Z facilities from 1962 through the first quarter of 1976. These documents typically 

contain paired photon and neutron workplace dosimeter and instrument measurements stated 

to be representative of potential worker exposures.

• An appendix to the 1972 AEC Investigation of neutron doses contained several neutron and 

photon ratio results collected for the purpose to estimate the potential career whole body 

(neutron and photon) doses for selected highly exposed workers. 

• NP ratio results of measurements taken in 1959 (Unruh 1962) 

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A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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• BNWL-B-127 (Nichols et al 1972) that provides dose results from parallel field tests of the TLD 

along with the Hanford beta/photon film and, for some workers, NTA film. Information from 

this document is presented in Table F-1 since it illustrates one approach to determining a NP 

ratio. In Table F-2 the NP ratios for various processing or storage environments in the 234-5Z 

Bldg were calculated based on the photon and neutron instrument and TLD dose 

measurements shown in the original document. 

Table F-1. NP ratio determined from 1971 workplace study of neutron dose measurements

(BNWL-B-127).a

Bldg. Location

Exp time 

(hrs)

Instrument NP 

ratio

TLD (mrem) NP 

Snoopy CP TEPC Derma Pen SN FN ratio

234-5Z

228-17DC 72.4 200 150 1.33 210 150 — 200 1.33

192-194 72.7 950 150 6.33 210 140 138 1360 10.70

228-HC-11 2.34 330 60 5.50 80 80 18 650 8.35

228-9-B 72.5 360 510 0.71 450 450 135 730 1.92

228-H618BS 72.5 360 510 0.71 100 100 6 170 1.76

194 2.75 550 90 6.11 60 60 9 390 6.65

221-center 73 660 1,460 0.45 1,470 1,470 18 940 0.65

221-N 73 1,310 2,480 0.53 1,640 1,640 24 1,060 0.66

105-KE

X-1 60 270 57 530

Top #23 1,400 1,700 141 4,100

Mon 0 0 <3 60

Front face 50 900 7 250

308

Room 208 2,000 2,700 84 3,700

Corr #7 4,200 14,100 390 11,100

Vent room 30 30 3 0

Room C 70 730 18 870

234-5Z

17DC 340 6 100

HC-11 280 12 180

9B top stairs 410 11 440

9B under 

stairs

280 18 450

Room 221 410 790 18 460

Room 192 510 620 66 490

Room 192-C 150 230 6 240

Room 193 380 500 36 600

2731-Z 200 <3 50

a. Dosimeters mounted on carboys in workplace for designated exposure duration.

Attachment D, Table D-2 provides a chronological listing of a large number of technical references 

along with brief summaries of those with particularly relevant information. There is an Excel database 

(SRDB 38336) of Hanford NTA dosimeter assignments at Hanford with the reported neutron dose 

which was developed in the preparation of PNNL-11196 (Fix et al 1997).

Another type of examination regarding the accuracy of TLD neutron dose measurements is made of 

summaries of field measurements published in 1981 (PNL-3536) and 1982 (PNL-3736) which are

presented in Tables F-2 and F-3, respectively. These tables do not include a photon dose 

measurement, only a comparison of different methods to measure the workplace neutron dose. 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Table F-2. Summary of 1981 Hanford workplace neutron dose measurements (PNL-3536).

Bldg Location

Energy

keVa

Neutron dose (mrem/hr) according to measurement methodb

MS Snoopy Rascal TEPC TLD TLD*

308

Pu storage vault 576 1.2 17.7

Above fuel storage pit 530 0.9 0.54 0.96

Above pit storage pit 1,100 0.8 2.0 1.3 1.2

0.46c

Fuel pin storage boxes on 

wall

660 4.1

Bare fuel subassembly 1,500 17.6 11

234-

5Z

HA-9A Glovebox 395 4.4 4 4.7 1.7 0.9

HC-9B Glovebox 390 12.1 11.5 12.7 14 7.4

18.7 9.8

2736

-Z

Vault 3 3EE-3FE 300 26.9 26 23.4 1.5 0.6

3.7 1.6

Vault 3 3CE-3DE 346 69.3 65 71.9

Vault 4 4ED-4FD 290 41.8 40 39.0

Vault 4 4GE-4NE 290 46.9 45 47.8 50.7 21.1

60.2 25.1

Hallway 146 1.3 0.8 1.0

Nuclear criticality detector 374 27.1 40

a. Average energy of neutron spectra

b. Measurement method: MS = multisphere, TEPC–Tissue Equivalent Proportional Counter, TLD–Hanford 

c. Multipurpose Dosimeter using normal algorithm, TLD* using alternate algorithm.

d. Phantom on floor.

Table F-3. Summary of 1982 Hanford workplace neutron dose measurements (Fix et al 1981).

Bldg Location

Measurement methoda

MS TEPC PTEPC He-3 Rascal Snoopy TLD

324 Pu storage vault 2.8 4.6 5.1 2.1 — 5.0 6.5

FFTF Location 8 3.8 5.6 — 14.7 13.0 18.0 29.1

Location 10 1.9 1.2 — 4.1 5.3 12.0 12.3

209-E Location 13 — 3.1 3.8 — — 2.0 1.8

Location 17 — — 0.6 — — 0.4 0.5

234-5Z

Maintenance office — 0.4 0.4 — — 0.5 0.4

Duct level, Col. 16 — — 1.6 — — 0.8 0.6

Duct level, under 52 — — 1.7 — — <0.1b 2.7

Duct level, over HA23 — — 2.6 — — 0.1b 5.1

Pu hood, top 2.8 14.7 12.3b 3.2 — 10.5c —

Pu hood, side — — 7.2 — — 7.0 —

General background — — 1.2 — — 1.5 —

a. MS–Multisphere, TEPC–Tissue Equivalent Proportional Counter, PTEPC–Portable Tissue Equivalent Proportional 

Counter, He-3–Helium-3 counter, TLD–Hanford Multipurpose Dosimeter.

b. These Snoopy readings are suspect due to geometry differences.

c. Average of four readings shown in table. 

The estimate of the actual neutron dose in well shielded work areas because of its significant 

response to measurements in these reports were performed with the objective to identify Hanford 

work areas in which analysis of the Hanford TLD could result in incorrect dose estimates to personnel. 

The studies included examination of workplace energy spectra and radiation type as well as a 

comparison of the neutron dose between several techniques of measuring neutron dose. The Tissue 

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A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

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Equivalent Proportional Counter (TEPC) method is generally accepted as providing the best estimate 

of the actual neutron dose. As noted in these reports, the TLD tended to over-estimate the instrument 

measured neutron dose on average. The TLD albedo dosimetry method is well known to over-lowerenergy neutrons. 

The Hanford TLD measured dose in 234-5Z locations compared with measurements with a Snoopy, 

TEPC, multisphere, and PNR-4 (i.e., common portable neutron instruments used to measure neutron 

dose based on 9-inch to 3-inch sphere ratio) as reported in Roberson et al (1985) is presented in 

Table F-4. These measurements show close agreement in estimated dose between the Hanford TLD 

and the respective instruments. 

Table F-4. 200 Area workplace measurement comparisons with HMPD (Roberson, 

Cummings and Fix 1985).

Location

Ratio of TLD dose to instrument dosea

Snoopy PNR-4b TEPC Multi-sphere

2736-Z, storage vault, Room 4 0.98 (0.37) 0.84 (0.18) 1.02 (0.18) 1.28 (0.24)

2736-Z, storage vault, Room 1 0.92 (0.14) 0.87 (0.56) 0.84 (0.10) 0.95 (0.13)

236-Z, gloveboxes 5-6 0.85 (0.18) 0.95 (0.43) 1.03 (0.41) 1.13 (0.41)

234-5Z, process line C, Room B 0.88 (0.28) 0.88 (0.21) 1.17 (0.26) 1.17 (0.25)

Average 0.90 (0.10) 0.87 (0.13) 0.92 (0.08) 1.05 (0.10)

a. Numbers in parentheses represent one-standard deviation.

b. Portable neutron REM instrument based on 9” to 3” sphere measurements.

F7.4 RADIATION SURVEY DATA

A team of health physicists examined many boxes of archive records containing Hanford workplace 

radiation survey sheets with the objective to identify those with paired photon and neutron 

measurements. Many records were identified and tagged for scanning. The selected records were 

included in the SRDB and the respective SRDB references have been included in the analysis files. 

An example of a few fields from this type of record is shown in Table F-5. The distance of the 

respective photon and neutron dose measurement is included in the file as noted on the original 

survey documentation. This is an important consideration in that the measured NP ratio typically 

varies with distance. An example of this dependency for measurements at various distances from the 

same, single source (PuF4, 836.4 grams) is shown in Figure F-3 from data taken from SRDB 36984 

(HW-28918). The cause of this variation may in fact be associated with the “field of view” of the 

respective gamma and neutron instrument measurements. Figure F-3 does show a typical 1/r2

relationship for either the measured photon or the neutron dose at distances greater than about 8 

inches. In the analysis of the NP ratio to be applied to dose reconstruction, only the measurements 

indicating a field (“F”) measurement (i.e., at a large distance) were used to avoid this potential cause 

of variability. It is also interesting in that the measurements in Figure F-3 show a consistent ratio (at 

greater than 8 inches) of about 5 for this single source of PuF4 with little shielding to scatter the 

radiation. 

F7.5 ANALYSIS OF NP RATIO MEASUREMENT DATA 

Originally, 2,050 paired neutron and photon dose measurements from workplace instrument survey 

measurements, NTA dosimeters, TLDs, technical reports, TLD dose histories for workers included in 

AEC 1972 Study, and TLD dose histories for Hanford claims selected in 2003 were collected by the 

team of health physicists as summarized in Table F-6. Certain of the workplace records of measured 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Table F-5. SRDB references containing neutron and photon dose survey measurements.

Document title

SRDB 

#

Date of 

reading

Building 

number

Room 

number

Survey specific 

description

General location 

description

234-5Z Survey Log 

Sheets 17285–17784, 

June 23–July 24, 1953

60723 6/25/1953 234-5Z 166 Box containing sand 

paper Hd 14 sample 

residue

Monthly survey of 

vault

234-5Z Survey Log 

Sheets 17285–17784, 

June 23–July 24, 1953

60723 6/25/1953 234-5Z 166 Box containing sand 

paper Hd 14 sample 

residue

Monthly survey of 

vault

Survey Log Sheets 

14244–14732 

December 26, 1952–

January 24, 1953

60724 12/29/1952 234-5Z 166 Boxes crucibles avg 

box

Operations to move 

boxes crucibles 

from 166 to waste 

storage hutment

Survey Log Sheets 

14244–14732 

December 26, 1952–

January 24, 1953

60724 12/29/1952 234-5Z 166 Avg reading boxes & 

crucibles 

Operation to 

remove boxes & 

crucibles from rm 

166 to waste 

storage hutment

Radiation Survey for 

Neutron Building 235

60793 12/9/1955 234-5Z 221 @ face of hood ER requested @ 

charging hood Rm 

221 recuplex

Radiation Survey for 

Neutron Building 235

60793 1/20/1956 234-5Z 221 H-9 base of gloves Routine surveys 

recuplex

Instrument Measured Neutron and Photon Dose from PuF4

1

10

100

1000

1 10 100

Distance from source, inches

Dose rate, mrem/hr

Gamma Dose Rate, mr/hr

Neutron Dose Rate, mrem/hr

Neutron to Gamma Ratio

Figure F-3. Variation in measured neutron and photon dose rates with distance, and 

the associated calculated NP ratio (SRDB 36984, HW-28918).

NP ratios are considered to be of lesser quality and were not selected for the primary analysis as 

noted in Table F-6. Notably, the NTA film data were not selected and a set of area TLD results were 

not selected since the measured neutron dose was comparatively low and it was not known if a 

phantom was included in the measurements which is essential for accurate dose response with the 

TLD albedo dosimeter. Reviews of this data resulted in the selection of 1,419 records of NP ratio 

ATTACHMENT F

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measurements that were unique and had a documented pedigree to the respective source 

documents. The records of this data in the analysis file include notation of the original document and 

page where the data was obtained. The distribution of NP ratios in the Hanford TBD prepared in 2003 

used only a selection of the TLD data (i.e., ≥20 mrem for photon and neutron dose, respectively). For 

years prior to 1972, Hanford policy was to control worker total (i.e., photon plus neutron) whole body 

external radiation dose using the photon component only.

Table F-6. Hanford 200 Area plutonium facility NP ratio survey records.

Description

No. of 

records

Selected for 

NP analysis Basis for selection

2003 Claim TLD Data 186 186 TLD measurements after 1971 with paired neutron 

and photon doses, respectively ≥ 20 mrem.

1972 AEC Study, Film Data 189 0 Paired pre-1972 NTA data are suspect.

1972 AEC Study, TLD Data 113 113 Paired TLD measurements after 1971 with paired 

neutron and photon doses, respectively ≥ 20 mrem.

1962-71 Radiation Control 

Report, Film Data

177 0 Paired pre-1972 NTA data are suspect.

1972-76 Radiation Control 

Report, TLD Data

16 0 TLD area measurement data are suspect because 

of comparatively low measured neutron dose. The 

presence of an albedo material, which is essential 

for accurate TLD performance is not known.

1962-76 Radiation Control 

Report, Instrument Data

161 161 Routine workplace instrument measured doses. 

Technical Reports, 

Instrument Data

114 114 These documents results from various Hanford 

initiated studies

Workplace Surveys, 

Instrument Data

1,194 845 All of the instrument measured doses by trained HP 

technicians were considered to be of good quality. 

Reduction in records analyzed was primarily 

associated with elimination of duplicate records.

Total 2,150 1,419

Figure F-4 is a graph of the 1,419 records of NP ratios according to the time and method of 

measurement, and the source of information. From this data there does not appear to be a clear 

trend over time. There is substantial variability for essentially all years of measurement which is likely 

associated with the location of measurements, the method of measurement as well as variations in 

process. The Radiation Control Data reports are monthly doses in 1963, and quarterly thereafter from 

1964 through first quarter 1976, based on daily and weekly measurements. The TLD data are 

measured monthly or quarterly doses for dosimeters assigned to workers. These longer-term 

measurements tend to have less variability. The workplace survey instrument measurements are 

short term measurements for a specific place and time as noted on the survey forms. Undoubtedly, 

there are many thousands of these workplace survey records which could be retrieved given sufficient 

time and resources. The data available however are expected to provide a reasonable basis to 

determine the distribution of the NP ratio. The various Technical Reports describe instrument 

measured NP ratios during 1956-57. The Radiation Control Report instrument measured and worker 

assigned TLD measured NP ratios cover a period from 1963 through 1994. 

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AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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1,419 NP Ratio Measurements

0.01

0.10

1.00

10.00

100.00

Jan-50 Jan-55 Jan-60 Jan-65 Jan-70 Jan-75 Jan-80 Jan-85 Jan-90 Jan-95

Year

NP Ratio

2003 Claim Data - TLD AEC Study - TLD Rad Control Reports - Inst. Technical Reports - Instr. Workplace Surveys - Instr.

TLD

Figure F-4. 1,419 measured NP ratios in Hanford 234-5Z plutonium facility.

There are many considerations in the analysis of neutron and photon dose measurements based on 

the history of 234-5Z operations as follows:

• The most significant radiological constituents of interest are those of the various plutonium 

isotopes (238Pu, 239Pu, 240Pu, 241Pu and 242Pu) and their decay products which include 241Am, 

234U, 235U, 236U, 237U, 238U, 237Np and a lesser amount of other isotopes. The relative 

abundance of these nuclides depends upon the characteristics of the nuclear fuel and the 

extent of burnup (i.e., extent of nuclear fuel exposure in the reactor).

• The nuclide 241Am poses one of the most significant long-term photon exposure sources. 

Plutonium with higher burnup, and thus higher amounts of 240Pu and 241Pu, will have 

significantly higher concentrations of 241Am, eventually, beginning from an abundance of about 

zero shortly after separation to a peak concentration in approximately 73 years. 

• Plutonium containing a higher percentage of 240Pu will normally have a lower NP ratio shortly 

after separation because there is a higher photon yield due to shorter half-life isotopes (238Pu, 

240Pu, 241Pu). 

• The NP ratio can be significantly affected by fission product (e.g., Ru, Nb, Zr) contamination of 

the plutonium which was greater in the earlier years.

• At Hanford, a major shift in plutonium isotopic content occurred around 1965 in the switch from 

weapons-grade (lower burnup) to fuel-grade (higher burnup) plutonium as shown in 

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Figure F-2. Considering only this issue, the NP ratio would be expected to be greater prior to 

1965 because of the lower 240Pu content in the relatively lower-exposed weapon-grade fuel.

The historical trend in the NP ratio in the workplace was considered in the 1972 AEC/HQ investigation 

using a committee of technical experts from throughout the DOE complex. The committee was 

formed to evaluate a significant increase in recorded neutron dose with the implementation of the 

Hanford TLD on January 1, 1972 compared with the previous measured neutron dose with NTA film.

The NP ratios identified by the committee for use in retrospective dose reconstruction for highly 

exposed workers (i.e., to view career dose compliance with the 5 (N-18) rem whole body dose limit) 

are shown in Table F-7. The analysis by the committee showed an expectation that the earlier NP 

ratios in the workplace would be lower. The basis for these NP ratios used to evaluate worker 

cumulative doses include:

Table F-7. 1972 AEC NP ratios used to reconstruct 

maximum worker dose.

Worker description

Neutron to gamma ratio

1961–72 1956–60 1948–55

Plutonium workers 2.01 1.36 1.23

Maintenance workers 1.60 1.09 1.00

• Recorded gamma radiation dose as measured by the film badge dosimeter is reasonably 

accurate for this type of radiation.

• The gamma radiation dose measured with TL and film dosimeters is comparable.

• For the period of 1961 through 1971, the ratio of the neutron to gamma radiation dose as 

measured by the TL dosimeter during the period of use, January 1, 1972 through June 30, 

1972, is reasonably representative of production conditions since introduction of heavy 

shielding materials (lead, lead glass, water walls). 

• For the period of 1956 through 1960, approximately one-third reduction in the neutron to 

gamma ratio is assumed when less shielding was in place primarily to reduce exposure from 

lower energy X and gamma radiation emitted by plutonium and plutonium compounds. On the 

average about one-third reduction in gamma dose was observed during the period following 

1960 when heavy shielding was installed and production was comparable.

• For the period of 1948 through 1955, another reduction of approximately 10 percent in the 

neutron to gamma ratio is assumed when essentially no shielding other than thin plastic hood 

windows was used in the process areas. It was estimated that low energy photons contributed 

about 10 percent of the penetrating gamma dose.

The analysis of the workplace measurements is complex because the NP ratio depends upon the 

workplace, work task, the distance of the measurement and the instrument used. The original 

workplace measurements were not taken with the understanding that these would be used to prepare 

a NP ratio to be used in dose reconstruction. As such, care must be taken in the selection of the data 

used to determine the NP ratio.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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A scatter plot of the 1,346 measured neutron and photon dose results is presented in Figure F-5 and 

a lognormal probability graph of the measured 1,419 NP ratio values (i.e., Bramson 1962 reference 

only provided measured NP ratios without measured neutron and photon doses) in Figure F-6. 

Figure F-5. Scatter plot of 1,346 measured neutron and photon doses.

Figure F-6. Lognormal probability plot of 1,419 measured NP values.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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These figures show a Pearson rank correlation between the neutron and photon measurements of 

0.76. The NP ratio best fits a lognormal distribution with a GM = 1.13, a GSD = 2.30 and the upper 

95th-percentile of 4.47.

Statistical lognormal distribution parameters for each category of workplace measurements are 

presented in Table F-8. It is evident in the tabled values that the TLD measurements are significantly 

less variable perhaps because the neutron and photon doses, respectively, are measured within a 

single device. The TLD data generally show a good lognormal distribution fit as noted in the last 

column of Table F-8. 

Table F-8. Statistical parameters for lognormal distribution for the respective selections of NP ratio 

measurement data.

Workplace measurements No. GM GSD 95th% Fita

All data: TLDs + instruments 1,419 1.13 2.30 4.47 0.18

TLD data–ALL 299 0.69 2.36 2.83 0.06

TLD data–2003 claims 186 0.73 2.10 2.47 0.09

TLD data–AEC study 113 0.63 2.77 3.37 0.06

Instrument data–all 1,120 1.29 2.17 4.64 0.22

Instrument data–radiation control reports 161 1.23 2.74 6.45 0.13

Instrument data–fluorination hoods 7A/9A & 7C/9B 71 1.68 2.57 7.94 0.19

Instrument data–hood 7A/9A 17 1.95 2.61 9.47 0.23

Instrument data–hood 7C/9B 54 1.60 2.57 7.56 0.20

Instrument data–technical reports 113 0.53 2.83 2.94 0.06

Instrument data–workplace surveys 846 1.47 1.80 3.85 0.23

Fluorination hoods instrument plus TLD worker measured 370 0.82 2.56 3.85 0.07

a. Kolmogorov–Smirnov test is used as a measure of goodness of fit to a lognormal distribution.

The highest quality instrument measurement data available for analysis of the NP ratio are the 

respective 1963 monthly and 1964–1976 (1st quarter only) quarterly reports prepared by PFP 

Radiation Protection staff. These measurements represent an average of daily and weekly 

measurements and are stated to be representative of worker exposures. This measurement data 

cover the period of weapons-grade plutonium prior to 1965 and primarily reactor-grade plutonium 

thereafter. The data are separated according to selected workplace categories (i.e., Plutonium 

processing, Plutonium Reclamation, Maintenance, 234-5Z Technical services, Button Line, 

Fluorination Hoods 7C-9B and 7A/9A). The RMA Line produced only oxides from 1968 on and the 

RMC Line mostly metal. Hanford Site personnel referred to the RMA Line as “the oxide line” and to 

the RMC Line as “the metal line” (DOE 2002). Three figures are provided for this data described as 

follows:

• Figures F-7 and F-8, respectively, contain graphs of instrument measured monthly neutron 

and photon dose rates with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button 

line and other line workplace locations during the period of 1963 to 1976. The dose results 

reported quarterly after 1963 were divided by 3 to obtain a monthly average to compare to the 

earlier reported monthly measurements. 

• Figure F-9 presents NP ratios calculated from the original data used to prepare Figures F-5 

and F-6. 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Instrument Measured Monthly Neutron Dose Rate 

0.01

0.10

1.00

10.00

100.00

Jan-50 Jan-55 Jan-60 Jan-65 Jan-70 Jan-75 Jan-80 Jan-85 Jan-90 Jan-95

Date

Neutron Dose Rate, mrem/hr

Fluorination Hoods, 7C/9B, 

Button Line Other Locations

Figure F-7. Radiation control report instrument measured monthly neutron dose rates 

with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, button line and other line 

workplace locations during the period of 1963 to 1976. 

Instrument Measured Photon Monthly Dose Rate 

0.01

0.10

1.00

10.00

100.00

Jan-50 Jan-55 Jan-60 Jan-65 Jan-70 Jan-75 Jan-80 Jan-85 Jan-90 Jan-95

Date

Photon Dose Rate, mR/hr

Button Line

Other Locations

Fluorination Hoods, 7C/9B, 7A/9A

Hoods 7A/9A

Hoods 7C/9B

Hoods 7A/9A

Figure F-8. Radiation control report instrument measured monthly photon 

dose rates with callouts for the PFP fluorination 7C/9B and 7A/9A hoods, 

button line and other line workplace locations during the period of 1963 to 

1976. 

These figures illustrate the comparatively greater NP ratio for the 7C/9B and 7A/9A fluorination hoods, 

and significantly, the comparatively greater photon (and neutron) dose rate compared to other 

locations along the process line. As such, assigning neutron doses prior to January 1, 1972 using the 

fluorination hood measured NP ratio multiplied times the measured photon dose will result in a 

favorable-to-claimant evaluation. The significance of worker exposures from the fluorination hoods 

was the basis for selecting this location to develop a workplace neutron dose calibration of the 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Instrument Measured NP Ratio Measurements

0.01

0.10

1.00

10.00

100.00

Jan-50 Jan-55 Jan-60 Jan-65 Jan-70 Jan-75 Jan-80 Jan-85 Jan-90 Jan-95

Date

NP Ratio

Fluorination Hoods, 

Button Line

Other Locations Fluorination Hoods 7A/9A

Figure F-9. NP ratios calculated from the data contained in Figures F-5 and F-6. 

Hanford TLD. In this process the PuF4 calibration source geometry in the Hanford Radiological 

Calibrations Facility 3745A was adjusted to arrive at an “equivalent workplace” neutron calibration

(SRDB 48446, 54554; Fix et al 1997b) based on workplace neutron dose and dosimeter 

measurements (i.e., dosimeter response calibrated to TEPC measured neutron dose). 

Personnel TLD measurements after 1971 are considered to be of comparatively good quality because 

the dosimeter measures the photon and neutron dose simultaneously in a single device, the 

dosimeter response has been verified with instrument workplace measurements on several occasions 

and the TLD tends to over-estimate, rather than under-estimate, the neutron dose in Hanford work 

locations. Two figures are presented as follows:

• Figure F-10. Correlation of TLD measured neutron and photon doses. 

• Figure F-11. Lognormal Probability Plot for TLD measured neutron-photon ratios. 

These figures show a Pearson rank correlation between the neutron and photon measurements of 

0.69. As noted in Table F-8, the TLD data NP ratio best fits a lognormal distribution with a GM = 0.69, 

a GSD = 2.36 and the upper 95th-percentile of 2.83. 

Fluorination 7C/9B and 7A/9A hoods instrument measurements plus the personnel TLD results after 

1971 are shown in Figure F-12. As noted in Table F-8, the NP ratio best fits a lognormal distribution 

with a GM = 0.82, a GSD = 2.56 and the upper 95th-percentile of 3.85. In Figure F-12, it does appear 

as though the instrument measured NP ratio prior to 1972 is greater than the personnel TLD 

measurements after 1971. As such, the instrument measurements for the fluorination hoods 7A/9A 

and 7C/9B were selected as representing the bounding workplace. As noted in Table F-8, the 

fluorination hood instrument measured NP ratio best fits a lognormal distribution (KolmogorovSmirnov fit = 0.1) with a GM = 1.68, a GSD = 2.57 and the upper 95th-percentile of 7.94. This is also 

the workplace with the highest measured photon (and neutron) dose rates.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Figure F-10. Correlation of TLD measured neutron and photon doses. 

Figure F-11. Lognormal probability plot for TLD measured neutron-photon ratios. 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Fluorination Hoods Instrument and TLD Worker Measurements

0.01

0.10

1.00

10.00

100.00

Jan-50 Jan-55 Jan-60 Jan-65 Jan-70 Jan-75 Jan-80 Jan-85 Jan-90 Jan-95

Date

NP Ratio

TLD

Figure F-12. Fluorination 7C/9B and 7A/9A hoods instrument and worker TLD NP ratio 

measurements.

F7.6 RECOMMENDED NP RATIOS

Workplace instrument and thermoluminescent dosimeter measurements were obtained from the 

extensive DOE Richland archives of historical documentation. A summary of the analysis of the 1,419 

NP ratio measurements is presented in Table F-8 for each of the major categories of measurement 

data.

The recommended favorable-to-claimant NP ratios are:

• For glovebox workers, the guidance in OCAS-TIB-010 for plutonium glovebox workers must be 

applied.

• Consistent with OCAS-IG-001 (2007) guidance, the measured and assigned neutron doses 

must incorporate the ICRP 60 weighting factors for the respective neutron energy categories in 

Hanford plutonium workplaces (ORAUT-OTIB-0055) (i.e., < 0.01 MeV = 2.13, 0.01-0.1 MeV = 

1.86, 0.1–2.0 MeV = 1.91). 

Worker GM GSD 95th-percentile Basis

Non-glovebox worker 1.1 2.3 4.5 Lognormal statistical parameters for 1,419 

instrument and TLD measurements

Glovebox worker 1.7 2.6 7.9 Lognormal statistical parameters for Fluorination 

Hoods 7C/9B, 7A/9A instrument measurements

F7.7 ILLUSTRATION OF THE APPLICATION OF NP RATIO

An illustration of the significant assignment of neutron dose using a NP ratio multiplied times the 

recorded photon dose is presented in Table F-9 using the dose record for a single higher exposed 

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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worker. For this worker, the record of recorded doses after 1972 with the Hanford TLD is also 

included in Table F-9 for comparison. For this worker, the film dosimeter measured WB dose (i.e., 

photon plus neutron) from 1958 through 1971 is 33 rem. The assigned WB dose using the 95thpercentile NP ratio (7.9) results in an assigned WB dose, during the period of film dosimeter use prior 

to 1972, of 219 rem. Applying guidance in TIB-010 for a lower abdominal organ results in an 

assigned organ dose of 480 rem assuming the organ dose conversion factor is 1.0. The TLD 

measured doses from 1972 through 1987 are considered to be reasonably accurate. For this worker 

employed from 1958 through 1987, there is a recorded Hanford career WB dose (photon and neutron 

dose) of 60 rem, and assigned WB dose of 246 rem, and for a lower abdominal organ an assigned 

organ dose of 539 rem assuming the organ dose conversion factor is 1.0. These values are 

illustrated in Table F-9.

Table F-9. Illustration of assigned dose to long-term PFP worker.

Year

Recorded dose components Assigned WB dose

Shallow Deep Neutron X-ray Recordeda NP ratiob TIB-010c

Hanford film/NTA dosimeter

1/1/58 2,520 2,520 60 440 2,734 23,799 52,119

1/1/59 2,170 1,990 120 330 2,226 18,739 41,038

1/1/60 1,370 1,370 340 70 1,735 12,411 27,180

1/1/61 1,460 1,460 1,110 200 2,640 13,617 29,821

1/1/62 1,080 930 1,880 300 2,915 9,212 20,173

1/1/63 2,010 1,470 800 360 2,396 14,204 31,108

1/1/64 1,830 1,730 1,060 290 2,892 16,300 35,698

1/1/65 2,100 2,100 570 530 2,856 20,341 44,547

1/1/66 640 640 120 250 848 6,475 14,180

1/1/67 2,080 1,880 250 310 2,239 17,698 38,758

1/1/68 1,780 1,400 840 310 2,349 13,426 29,402

1/1/69 1,760 1,670 370 820 2,327 17,417 38,144

1/1/70 1,430 1,400 270 610 1,884 14,360 31,449

1/1/71 2,180 2,180 710 520 3,072 21,022 46,038

Film subtotals 24,410 22,740 8,500 5,340 33,109 219,020 479,654

Hanford TLD

1/1/72 2,240 1,540 2,360 0 3,900 3,900 8,541

1/1/73 3,120 2,260 1,990 0 4,250 4,250 9,308

1/1/74 1,600 1,110 630 0 1,740 1,740 3,811

1/1/75 1,570 1,210 420 0 1,630 1,630 3,570

1/1/76 1,500 1,220 220 0 1,440 1,440 3,154

1/1/77 1,390 1,180 60 0 1,240 1,240 2,716

1/1/78 700 520 220 0 740 740 1,621

1/1/79 810 570 330 0 900 900 1,971

1/1/80 1,110 790 420 0 1,210 1,210 2,650

1/1/81 1,250 920 680 0 1,600 1,600 3,504

1/1/82 1,180 970 210 0 1,180 1,180 2,584

1/1/83 1,350 1,130 610 0 1,740 1,740 3,811

1/1/84 1,010 890 510 0 1,400 1,400 3,066

1/1/85 1,520 1,050 770 0 1,820 1,820 3,986

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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Year

Recorded dose components Assigned WB dose

Shallow Deep Neutron X-ray Recordeda NP ratiob TIB-010c

1/1/86 1,450 1,030 480 0 1,510 1,510 3,307

1/1/87 460 490 190 0 680 680 1,489

TLD subtotals 22,260 16,880 10,100 0 26,980 26,980 59,086

Career totals 46,670 39,620 18,600 5,340 60,089 246,000 538,740

a. Hanford WB Dose = Deep + Neutron + 0.35 * X-ray.

b. NP 95th-percentile = 7.9

c. Lower abdomen organ dose only geometry correction, GM = 2.19.

ATTACHMENT F

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE 

AT 200 AREA PLUTONIUM FACILITY OPERATIONS AT THE HANFORD SITE

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TABLE OF CONTENTS

SECTION TITLE PAGE

G1. Executive Summary .............................................................................................................251

G2. Introduction ..........................................................................................................................251

G3. History..................................................................................................................................255

G3.1 Hanford 300 Area Plutonium and Site Miscellaneous Facilities................................. 255

G3.1.1 Test Reactor Facilities............................................................................. 255

G3.1.2 Critical Mass Laboratory Facilities ........................................................... 256

G3.1.3 Radiological Calibration Laboratory Facilities .......................................... 257

G3.1.4 300 Area Laboratory Facilities................................................................. 257

G3.2 Facilities Operational in the 1940s............................................................................ 257

G3.3 Facilities Operational in the 1950s............................................................................ 258

G3.4 Facilities Operational in the 1960s............................................................................ 258

G4. Radiation Protection.............................................................................................................258

G5. Methods ...............................................................................................................................259

G5.1 Site Expert Interviews............................................................................................... 259

G5.2 NTA Results Database ............................................................................................. 259

G5.3 Data Identification..................................................................................................... 259

G5.4 Data Capture............................................................................................................ 259

G6. Results.................................................................................................................................260

G6.1 Site Expert Interviews............................................................................................... 260

G6.2 NTA Processing Files ............................................................................................... 261

G6.3 Workplace Measurements of Neutron Radiation....................................................... 262

G7. Technical Reports ................................................................................................................262

G8. Radiation Survey Data .........................................................................................................263

G8.1 Analysis of Neutron to Photon Dose Ratio................................................................ 265

G9. Summary .............................................................................................................................265

LIST OF TABLES

G-1 AEC 1972 Committee N:P ratio recommendations............................................................... 253

G-2 300 Area and Hanford NTA processing results .................................................................... 262

G-3 N:P Ratio determined from 1971 Workplace Study of Neutron Dose 

Measurements ..................................................................................................................... 263

G-4 Summary of 1981 Hanford workplace neutron dose measurements .................................... 264

G-5 Summary of 1982 Hanford workplace neutron dose measurements .................................... 264

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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G1. EXECUTIVE SUMMARY

The Hanford 300 Area Reactor and plutonium research, development and testing facilities, the 300 

Area Radiological Calibrations facilities, and the site critical mass laboratory facilities did involve 

neutron radiation exposure of workers as evidenced by (1) the types of operations, (2) routine 

assignment of nuclear track emulsion (i.e., NTA) film, and (3) information in the routine radiation 

monitoring periodic reports. Operations in these facilities supported the much larger 100 Area reactor 

and 200 Area chemical processing and plutonium chemical-metallurgical facilities. Extensive 

radiation surveys were taken of these facilities because Hanford radiation safety standards applied to 

all facilities in the 100, 200 and 300 Area facilities. Workers in the 300 Area would often travel to the 

100 and 200 Areas. A feasible neutron dose reconstruction option is to apply favorable-to-claimant 

NP ratios determined for the Hanford 100 Area single-pass cooling production reactor (Taulbee et al. 

2008) and Hanford 200 Area plutonium (Attachment F) facilities to 300 Area workers according to 

their work activities. In this approach, NP ratios determined from workplace measurements in the 100 

Area reactor and 200 Area plutonium facilities would be applied to workers in the 300 Area reactor 

and plutonium facilities, respectively, based on a favorable-to-claimant judgment by the dose 

reconstructor. Neutron exposures in the 120 Building and 209-E critical mass laboratories to workers 

did occur but were relatively insignificant for routine operations because of the significant shielding 

and remote operation. Under all circumstances, there was substantial photon radiation that was 

reasonably accurately measured in all facilities and for all periods that accompanied the neutron 

radiation.

Dose reconstruction would involve:

• TLD-measured neutron dose be used from January 1972 to date for all workers and Hanford 

facilities. 

• Prior to 1972, the measured (and missed) photon dose is multiplied by an NP dose ratio to 

arrive at an assigned neutron dose. The selection of NP dose ratio distribution parameters 

should be based on comparison with the extensive measured dose rates in Hanford singlepass cooling (Taulbee et al. 2008), Hanford N Reactor (Attachment E), and Hanford 200 Area 

Plutonium Facilities (Attachment F).

The estimated neutron dose calculated using NP ratios and the measured photon dose must be 

adjusted to incorporate the ICRP Publication 60 weighting factors (ICRP 1991). The assumed 

neutron energy IREP input category is assumed to be 0.1 to 2 MeV.

G2. INTRODUCTION

The focus of this attachment concerns a technical basis for neutron dose reconstruction for workers at 

Hanford 300 Area plutonium, reactor, and radiological research and development laboratory facilities 

and Hanford Site critical mass laboratories during the periods of operation of these facilities. A 

technical basis for neutron dose reconstruction for several Hanford facilities is provided as follows:

• Hanford single-pass cooling plutonium production reactors (B, C, D, DR, F, H, KE, and KW) 

constructed during the period from 1943 through 1954 that operated from 1944 through 1971 

(Taulbee et al. 2008).

ATTACHMENT G

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• Hanford 100 Area N Reactor operations during the period from December 1963 through 

January 1987 (Attachment E).

• Hanford 200 Area Plutonium Facilities operations during the period from about 1944 through 

the 1990s (Attachment F).

Hanford 300 Area research and development facilities were used to test and evaluate processes to be 

incorporated into the much larger 100 Area Reactor and 200 Area Chemical Processing and 

Metallurgical production facilities. Hanford critical mass laboratories used to test process methods 

and tolerances were located in typically isolated facilities in the 100, 200 and 300 Areas. The 300 

Area did have the primary roles to fabricate fuel for the Hanford Reactors and to provide site-wide 

radiological calibrations, radiation instruments and dosimetry capabilities. Because of the research 

nature of Hanford 300 Area and Miscellaneous Facilities a wide range of nuclear science activities 

occurred. Activities with some potential for significant neutron exposure to workers can be generally 

categorized as: 

• Prototypes of reactor testing, research and development facilities

• Plutonium research and development laboratory processes 

• Critical Mass Laboratories

• Nuclear Science Research and Development 

• Hanford site-wide technical support involving radiological research, calibrations, instrument 

development and dosimetry capabilities. 

As noted in the Hanford Site Profile External Radiation Technical Basis Document ORAUT-TKBS0006-6 prepared originally in 2003, neutron radiation exposures to workers in Hanford facilities were 

not accurately measured using personnel film NTA dosimeters prior to implementation of the Hanford 

thermoluminescent personnel dosimeter (TLD) on January 1, 1972. Prior to January 1, 1972, Hanford 

used four general methods (Wilson 1987) to measure and control neutron exposure to workers as 

follows:

• Method #1. Eastman Kodak Nuclear Track Emulsion, Type A, (NTA) personnel neutron film

beginning in 1950 with three different Hanford neutron personnel dosimeter designs (i.e., TwoElement, 1958 multielement and 1962 multielement).

• Method #2. Pocket ionization chambers (PICs) with a boron liner [examples, HEW (1947–

1949, 1949–1952)].

• Method #3. Workplace surveys using portable neutron radiation responsive instrument and 

time-keeping.

• Method #4. Measurement and control of worker photon exposure to Hanford Operational dose 

limits with the expectation that the total WB dose (photon plus neutron) would be less than 

MED/AEC officially identified dose limits. 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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These methods were used jointly to measure and control worker radiation exposures because 

dosimeters in method #1 do not provide capabilities for effective workplace exposure control. 

Dosimeters are exchanged on a routine weekly, biweekly, monthly, or quarterly schedule with dose 

results received long after radiation exposures have been received. There are records of dose 

assessments with methods #2 and #3 but it is not certain that the neutron doses were incorporated 

into the official Hanford radiological records. This could be important if neutron doses determined 

from these methods were greater than the NTA film measured doses. Method #4 was incorporated in 

1954 into Hanford Operational Radiation Protection Standards as discussed under Radiation 

Protection Standards in this document. This method has an implied bound on the ratio of the NP 

dose (i.e., 5 rem/3 R = 1.7) which was adopted to ensure Hanford workers did not exceed annual 

dose protection limits. Based on the recorded neutron dose record for the Hanford Worker Health and 

Mortality Study (Buschbom and Gilbert 1993) which includes essentially all Hanford workers 

employed with a primary Hanford contractor for a period longer than six months there is no recorded 

neutron dose prior to 1950. The judgment in ORAUT-TKBS-0006-6 that the neutron dose is 

underestimated for workers at Hanford plutonium facilities prior to 1972 is consistent with findings of 

an AEC/HQ technical committee investigation conducted in 1972 involving dosimetry experts from 

other AEC sites and Hanford (Biles 1972). This investigation was conducted because of the 

significant increase in measured neutron dose with the TLD compared to the NTA film (Fix et al. 

1997). 

Recommendations developed in 1972 

The recommended neutron to gamma ratios identified by the committee in 1972 are shown in 

Table G-1.

Table G-1. AEC 1972 Committee NP ratio 

recommendations.

Worker description

Neutron to gamma ratio

1961–72 1956–60 1948–55

Plutonium workers 2.01 1.36 1.23

Maintenance workers 1.60 1.09 1.00

The stated reasons for these recommended NP ratios include:

• Recorded gamma radiation dose as measured by the film badge dosimeter is reasonably 

accurate for this type of radiation.

• The gamma radiation dose measured by TL and film dosimeters is comparable.

• The ratio of the neutron to gamma radiation dose as measured by the TL dosimeter during the 

period of use, January 1, 1972 through June 30, 1972, is reasonably representative of 

production conditions since introduction of heavy shielding materials (lead, lead glass, water 

walls).

• Approximately one-third reduction in the neutron to gamma ratio is assumed for the period 

from 1956 through 1960 when less shielding was in place primarily to reduce exposure from 

lower energy X-ray and gamma radiation emitted by plutonium and plutonium compounds. On 

the average about one-third reduction in gamma dose was observed during the period 

following 1960 when heavy shielding was installed and production was comparable.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

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• Another reduction of approximately 10 percent in the neutron to gamma ratio is assumed for 

the period from 1948 through 1955 when essentially no shielding other than thin plastic hood 

windows was used in the process areas. It was estimated that low energy photons contributed 

about 10 percent of the penetrating gamma dose.

There is a set of spreadsheets that contain NTA processing results for Hanford workers according to 

Hanford Operating Areas during the period from 1950 through 1961 (Yamauchi, 2006) and additional 

years of records are available in DOE-RL record archives in the Seattle Federal Record Center. 

Technically, neutron radiation is easy to detect but determination of the spectra and dose to workers 

is complex. The AEC/DOE has attempted to address the complexities of Personnel Neutron 

Dosimetry in a series of workshops organized to share technology among sites beginning in 1969 

(Vallario, Hankins, and Unruh 1969). Even in the present time, personnel neutron dosimeter 

performance is not equivalent to the accuracy and reliability of photon (X-ray and gamma) dosimeter 

performance. There are portable instruments available since approximately the mid-1950s that do 

provide reasonably accurate measurements of the neutron dose. The TLD-measured neutron dose is 

considered to be reasonably accurate with a significant potential to overestimate rather than to 

underestimate the actual neutron dose. A timeline of significant events at Hanford associated with 

radiation protection of 300 Area workers is presented in Attachment D, Table D-2. A detailed timeline 

of Hanford operations and processes is presented in RHO-HS-ST-10 Vol. 1 ATT (RHC 1987).

The option to retrospectively estimate a neutron dose to workers in these facilities by multiplying the 

measured photon dose by a NP (NP) ratio avoids significant issues concerning:

• NTA neutron dosimeters might not have been assigned to all Hanford workers in these 300 

Area facilities prior to the TLD implemented January 1, 1972, 

• The assigned NTA dosimeters did not reliably provide a reasonably accurate estimate of the 

actual neutron dose for Hanford workers. 

Certainly, the challenge in this approach is the determination of the NP ratio (i.e., distribution of values 

to select GM, GSD, 95th-percentile) for use in neutron dose reconstruction and in estimating the 

uncertainty.

2003 Site Profile Neutron Dose Recommendation 

The Hanford Site Profile External Radiation Technical Basis Manual prepared originally during 2003 

recommends reconstruction of the neutron dose as follows:

• Use TLD measured neutron dose from January 1972 to date along with the missed neutron 

dose using OCAS-IG-001 External Dose IG Guidance (NIOSH 2007b).

• Prior to 1972, multiply the neutron-to-photon NP dose ratio times the measured and missed 

(using OCAS-IG-001 guidance) photon dose using ratios determined for Hanford 100 Area 

reactor and 200 Area plutonium facilities based on evaluation of similar workplace fields (i.e., 

305 reactor would utilize 100 Area single-pass cooling NP ratio and 308 Building would utilize 

200 Area plutonium facility NP ratio).

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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G3. HISTORY

The history of Hanford 300 Area Plutonium and Miscellaneous 100 and 200 Critical Mass facilities

was centered around testing of various processes being considered for incorporation into the much 

larger 100 Area Reactor and 200 Area Chemical and Chemical/Metallurgical Production facilities. 

Notable historical documents include the following:

• Ballinger, M. Y., and R. B. Hall, 1991, A History of Major Hanford Facilities and Processes 

Involving Radioactive Material, PNL-6964 HEDR, Pacific Northwest Laboratory, Richland, 

Washington, March. 

• Gerber, M. S., 1993a, Multiple Missions: The 300 Area in Hanford Site History; M. S. Gerber, 

PhD, WHC-MR-0440, Westinghouse Hanford Company, Hanford Site, Richland, Washington, 

September.

• Gerber, M. S., 1992, Past Practices Technical Characterization Study – 300 Area – Hanford 

Site, WHC-MR-0388, Westinghouse Hanford Company, Hanford Site, Richland, Washington, 

December.

• DOE (U.S. Department of Energy), 1997, Linking Legacies: Connecting the Cold War Nuclear 

Weapons Production Processes to Their Environmental Consequences, DOE/EM-0319, Office 

of Environmental Management, Washington, D.C., January.

During the period from 1944-49, all research and development (R&D) work at Hanford was in support 

of plutonium production (Ballinger and Hall 1991). The principal R&D activity was the cold semiworks 

activities in the 321 Building, where pilot-plant scale work was conducted for the REDOX Plant, and, 

later, the PUREX Plant. Because radioactive contamination in this facility was limited to uranium, 

which represented a much smaller radiation hazard than plutonium, radiation dose rates were 

comparably low. REDOX and PUREX operating crews were trained here. In the 1950s, facilities in 

the 300 Area were greatly expanded, including construction of the Plutonium Fuels Pilot Plant (PFPP) 

and the 309 Bldg Plutonium Recycle Test Reactor (PRTR), where work was directed toward 

developing peaceful uses for plutonium. 

G3.1 HANFORD 300 AREA PLUTONIUM AND SITE MISCELLANEOUS FACILITIES

G3.1.1 Tes t Reactor Facilities

As described in ORAUT-TKBS-0006-2, the Hanford 300 Area was the location of several test reactors 

(ORAUT 2007c). The 305 Building housed a small reactor for testing samples of graphite, uranium 

and other materials used in the construction of the large 100 Area plutonium production reactors. The 

Physical Constants Test Reactor and the Thermal Test Reactor were also located in the 305 Building. 

Other 300 Area Test Reactors included the 309 Building Plutonium Recycle Test Reactor (PRTR) and 

the 318 Building High Temperature Lattice Test Reactor (HTLTR). A brief description of these test 

reactors all built and operated prior to the use of the TLD follow:

305 Building Hanford Test Reactor. The HTR operated at a low power level (usually less than 50 

Watts) from 1943 until 1972 to test samples of each lot of graphite, uranium, aluminum tubes, 

aluminum canning material (for fuel rod jackets), and other materials to be used in the Hanford 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

Page 6 of 16
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production reactors. Instrumentation for the 100 Area reactors including counter tubes, gas 

chambers, thermopiles, shim-stock chambers and neutron and gamma radiation chambers were also 

tested in the 305 Test Reactor. The reactor consisted of a graphite pile and was air-cooled. The pile 

was removed from the 305 Building during 1976-77. There was undoubtedly some external radiation 

exposure to Hanford workers from operations at this facility.

305 Building Physical Constants Test Reactor (PCTR). The 800 Watt PCTR operated from 1954 

to 1970 for the purpose of measuring reactor changes as a result of use of different reactor fuels. 

External radiation exposures to workers were negligible because the reactor was located in a shielded 

underground room and operated remotely. 

305 Building Thermal Test Reactor (TTR). The 1000 Watt TTR operated from 1954 through 1978 

for the purpose of measuring thermal dependence of various material fission cross-sections. External 

radiation exposures to workers were minimal because the reactor was operated remotely.

309 Building Plutonium Recycle Test Reactor (PRTR). The heavy water cooled and moderated 

PRTR began operating in November 1960 and reached full power of 70 MW in July 1961. The 

reactor operated through 1969 for the purpose of testing mixed oxide reactor fuels using various 

methods of manufacture. External radiation exposure to personnel was minimized because of 

shielding and remote operation. The Plutonium Recycle Critical Facility (PRCF) also operated in the 

309 Building from 1962 through 1976 for the purpose of testing geometric arrangements of fissionable 

materials in a reactor.

318 Building High Temperature Lattice Test Reactor (HTLTR). The 2 MW HTLTR operated from 

1968 to 1971 to test advanced reactor physics technology. Six different cores were used in the 

reactor. External radiation exposure was negligible during operation because the reactor was heavily 

shielded and operated remotely. This building and the shielded reactor room were modified in the 

early 1980s and used thereafter as the Hanford Radiation Calibration Facility replacing operations 

originally conducted at the 3745A Building. 

G3.1.2 Critical Mas s Laboratory Facilities

Hanford critical mass laboratories were operated at the 120 Building near the 100-F Area and later in 

the 209-E building in the 200 East Area. A brief description of the Hanford critical mass laboratory 

facilities follows:

120 Critical Mass Laboratory. The 120 Bldg Critical Mass Laboratory started in 1950 conducting 

nuclear physics research and development studies of plutonium solutions and solids with the objective 

to avoid a criticality accident in an operating facility. During a critical mass study on November 16, 

1951 the reactor suddenly went out of control. The primary and secondary safety systems 

automatically shut down the reactor promptly. However, all six workers in the P-11 area at the time 

were overexposed to gamma and neutron radiation. Total WB dose estimates ranged from 300 to 

600 mrem [see Attachment D, Table D-2, November 16, 1951, for more details (Adams 1951)].

209-E Critical Mass Laboratory. The 209-E Critical Mass Laboratory was placed into operation 

during July 1961 and shut down in 1986. The building located in the central 200 East Area contained 

a critical assembly room with a minimum wall thickness of 3 ft, a mixing room with gloveboxes and a 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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mixing hood, and a control room from which experiments could be remotely conducted. Because of 

the shielding external radiation exposure to personnel is considered to have been minimal.

G3.1.3 Radiological Calibration Laboratory Facilities

3745 Radiological Calibrations and Standards Laboratory. Operations at this laboratory began in 

October 1944 using various beta, gamma and neutron radiation sources, and X-ray systems, to test 

and calibrate Hanford Site dosimetry and instrument capabilities. A supporting facility, 3745-A, was 

built in 1950 to house a 2 MeV negative ion Van de Graff accelerator. A similar supporting facility, 

3745-B, was built in about 1955 to house a 4-MeV Van de Graff positive ion accelerator. These 

accelerator facilities were used to perform fast neutron radiation calibrations of Hanford instruments 

and dosimeters. The process of testing and calibration of Hanford portable radiation detection 

instruments and personnel dosimeters does involve radiation exposure to the workers. Operations in 

this facility were moved to the 318 Building in 1983.

318 Hanford Radiological Calibrations Facility. The 318 Building was originally built in 1967 to 

house the High Temperature Lattice Test Reactor (HTLTR). In the early 1980s, the reactor was 

removed and the facility converted to house Hanford Radiological Calibrations capabilities from the 

3745 Building. The process of calibration and testing Hanford portable radiation detection instruments 

and personnel dosimeters does involve radiation exposure to the workers.

G3.1.4 300 Area Laboratory Facilities

G3.2 FACILITIES OPERATIONAL IN THE 1940S

3706 Radiochemistry Laboratory. Radiochemistry activities in the 300 Area began in 1944 in the 

3706 building, where work was limited to low-level radioactivity handled in hoods. Chemistry 

performed included support for fuel fabrication and REDOX process development, which was 

occurring in the 321 Building. There was plutonium contamination of some laboratory rooms within 

this facility (Gerber 1992) that required use of protective clothing, time limitations and other SWP 

protective actions.

3708 Radiation Measurements Building. The 3708 Radiation Measurements Building was built in 

1948 to process personnel dosimeters and pencils. This function was relocated to the 3705 building 

in 1963. The 3708 building was later renovated as a fuel fabrication facility in the early 1960s. In the 

early 1970s, the north end of the 3708 Building was used for experimental canning of americium oxide 

and curium oxide fuel blends (Gerber 1992).

321 Building Semi-Works Facility. The 321 Building was constructed in the 1940s as a cold “semiworks,” or pilot scale plant for testing chemical “process improvements” for the 200 Area chemical 

processing facilities using unirradiated or low-activity substances. A series of cells and tanks were 

located in the building.

326 Pile Physics Technology and Metallurgical Facility. The mission of the 326 Pile Physics 

Technology and Metallurgical Facility was to conduct the exponential pile physics development work 

necessary to achieve continuity of operations for the production reactors. The facility began in 1953 

and continued developmental work originally performed in the 120 Building Critical Mass Laboratory 

(i.e., P-11 Facility) and later in 189-D. The earliest and most intense radioactive work in the 326 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

Page 8 of 16
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Building was the operation of the exponential piles in the basement beginning in about 1953. Piles 

shielded only by lead bricks using PoBe and RaBe neutron sources emitting 108 n/s were used to 

irradiate Co, Cu and other metallic foils. Some of this work was transferred to the 209-E facility when 

it became operational in 1961. In 1983, the 326 Building became the “Chemical Science Building.” 

The facility is still in operation.

G3.3 Facilities Operational IN THE 1950s

325 Radiochemistry Laboratory. The 325 Building Laboratory began operations in 1953 to permit 

multicurie level chemical development work to be done in support of production and process 

improvement analyses. There were three large hot cells for isotope research activities involving 

selected fission and plutonium nuclides. Radiochemistry performed in these cells included 

radionuclide separation and concentration for special programs, which included promethium-147, 

plutonium-238, plutonium-239, americium-241, cesium-137, and strontium-90. Radiochemistry was 

also performed in support of the solidification of high-level waste in conjunction with the 324 Building.

327 Radiometallurgy Laboratory Facility. The 327 Radiometallurgy Laboratory was built in 1953 

and provided shielded cells for the destructive examination of irradiated materials including fuels. 

Activities in the 12 shielded cells were standard for metallurgical examination except that sectioning, 

grinding, polishing, and microphotography were performed by manipulators and other remote handling 

devices (Ballenger and Hall 1991). The 327 Building was renamed the “Post Irradiation Testing 

Laboratory” in the 1980s. The facility was deactivated in 1987.

G3.4 FACILITIES OPERATIONAL IN THE 1960S

308 Plutonium Fuels Pilot Plant. This facility became operational in 1960 to perform research and 

development of fuels used in the PRTR and subsequently fuels used in the liquid breeder reactor 

program including the Fast Flux Test Reactor. In the mid-1960s, the PRTR fuel work was terminated. 

In the late 1960s, neptunium-aluminum alloy fuel target elements were produced for use in N Reactor 

for a 238Pu production run. This facility was used from 1977 to 1991 for production of FFTF fuel 

elements. The 308-A annex was added in 1979 to accommodate additional plutonium fuels work. A 

250-kW Training Research Isotopes, General Atomics (TRIGA) reactor was installed in the annex in 

the late 1970s to perform neutron radiography. The 308 facilities were deactivated in 1990.

324 Building Chemical and Materials Engineering Laboratory. This laboratory began operations 

in 1966 to provide research and development studies in support of PRTR operations. The laboratory 

was used first as a fuel recycle pilot plant by housing chemical reprocessing and metallurgical 

examination capabilities used for PRTR fuel elements. Two groups of large shielded cells were used 

for radiochemical and metallurgical studies. The chemistry cells were connected to an air lock where 

studies of high-level liquid waste were performed. A special underground liquid waste pipe line 

connected the hot cells in 324 and 325-Annex. Because the majority of work was performed in hot 

cells, external and internal exposures were minimal.

G4. RADIATION PROTECTION

A description of Hanford radiation protection standards, procedures and practices is provided in 

Attachment D along with a historical timeline of radiation associated events in Table D-2.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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G5. METHODS

Monitoring of radiation exposure to workers in the Hanford 300 Area operations was done using the 

same capabilities and procedures used for workers at the 100 Area production reactor and 200 Area 

facilities. Similar practices were used for workplace surveys, SWPs and exposure controls. 

G5.1 SITE EXPERT INTERVIEWS

Interviews with Site Experts were conducted and documented regarding their assessment of the 

potential for significant neutron exposure of Hanford 300 Area plutonium facility and Miscellaneous 

Facility work areas and work tasks with potential neutron exposure. Tours of the Hanford 200 Area 

234-5 facility and the 231-Z facility with known significant neutron exposures of workers were made 

during June and November 2008 with persons with expert knowledge of Hanford plutonium facility 

design and operation. The site experts were asked to provide information concerning:

• Their knowledge of workplace neutron radiation levels at Hanford facilities supporting 200 

Area plutonium production particularly information concerning significant neutron exposure.

• Their knowledge concerning changes in 200 Area and other facility construction and/or 

operations important to understanding the applicability of statistical parameters determined 

from TLD-measured doses to the pre-1972 period.

• Their knowledge concerning performance of workplace surveys and particularly feasibility of 

access to the documented surveys, access to the facility worker measured doses, and 

specifically access to the measured TLD-measured neutron and photon doses during the 

period from 1972 through 1987.

• Their knowledge concerning any other information that might be relevant to the reconstruction 

of neutron dose to Hanford 300 Area and Miscellaneous facility workers prior to 1972.

G5.2 NTA RESULTS DATABASE

The spreadsheet containing NTA processing results during the period from 1950 through 1961 

(Yamauchi 2006) was examined to determine which 100 Area and 300 Area facilities might have been 

considered to have a significant neutron exposure potential. 

G5.3 DATA IDENTIFICATION

Data searches of the various DOE Hanford archive record systems were done using numerous 

combinations of keywords or abbreviations “survey,” “control,” “neut,” “NTA,” “A-film,” repetitive, etc., 

associated with neutron radiation or monitoring surveys, neutrons, NTA film, A-film, and R&R surveys. 

Prior to the data collection trips, record indexes were received from DOE-RL and used in the 

prioritization of records of interest for workplace photon and neutron fields.

G5.4 DATA CAPTURE

Data capture trips to DOE-RL with the expressed objective to obtain detailed monitoring data occurred 

during: October 9-15, 2007; December 2-7, 2007; June 2-6, 2008; July 7-15, 2008; September 22-26, 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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2008; October 13-17, 2008; and November 17-24, 2008. Substantial efforts were made by a team of 

health physicists to find actual original records of instrument measured photon and neutron doses 

done at the same time and location (i.e., paired data). A large number of boxes and documents were 

identified that potentially contained relevant records. The contents of these boxes and documents 

were reviewed during the data collection trips.

G6. RESULTS

G6.1 SITE EXPERT INTERVIEWS

Several of the site experts interviewed for the 100 and 200 Area facilities were actually located in 300 

Area facilities because the site-wide radiological technical support staff; instrument development, 

maintenance and calibration; and site-wide dosimetry processing and record capabilities were in 300 

Area facilities. The 300 Area R&D facilities were much smaller than the 100 and 200 Area production 

facilities. Questionnaires were developed in conjunction with the interviews and used in the interview 

documentation. The documented interviews were submitted to DOE for classification review. 

Abbreviated results from the interviews are described in the following: 

Site Expert 1 (Fix 2008c). Documented interview with retired Hanford Site expert hired in 1959 

located for many years in the 300 Area. Person worked in the 308 Building making and performing 

quality assurance measurements on plutonium-aluminum coextruded fuel elements. Site Expert later 

analyzed nuclear fuel burnup data as part of the Plutonium Utilization Program. Site Expert 

participated in investigations of exposure issues associated with processing of Hanford higher 

exposure plutonium and the increase in the gamma dose rate with plutonium isotopic composition, 

age since separation, and glovebox through-put. Site Expert performed neutron dose and spectra 

measurements at several Hanford and other DOE laboratory workplaces and was a lead author of a 

DOE complex report on personnel neutron dosimetry in DOE facilities. 

Site Expert 2 (Fix 2007b). Documented interview with retired Hanford Site expert hired in 1956 

located in the 300 Area originally working in reactor physics. Site Expert spent substantial time in 

various 300 Area research activities such as in the 326 Bldg Exponential Pile Laboratory working with 

radiation sources such as PuBe-238, developing neutron spectrometer capabilities, which were very 

crude in the beginning, and performing work to characterize the NTA energy response. This person 

was very involved in the effort to develop the Hanford thermoluminescent dosimeter (TLD) systems. 

Expert had several non-Hanford project roles including a multiyear U.S. Nuclear Regulatory 

Commission Project to measure neutron spectra and dose in U.S. commercial nuclear reactors which 

is described in several NUREG reports. 

Site Expert 3 (Fix 2008g). Documented interview with Hanford Site Expert hired at Hanford in 1948 

who worked with technical function tests, calibration and distribution of health physics instruments to 

the 100, 200, and 300 Areas. The results of these tests were documented. Site Expert mentioned 

that the calibration technicians were actually receiving significant exposures (see also HW-28532) and 

steps were taken to build a Well calibration facility whereby the technicians were not directly exposed 

to the calibrating source. Site Expert was directly involved in 234-5Z Building radiation exposure 

measurements and efforts to resolve radiation exposure problems that existed in the 234-5Z and 231-

Z buildings. Site Expert recalled being involved in "time and motion studies," to determine the length 

of time required to do specific tasks. Site Expert authored many Hanford technical reports and 

subsequently was involved in national and international measurements of radiation.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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Site Expert 4 (Fix 2007b,g). Documented interviews with Hanford Site Expert involved in radiological 

physics issues throughout Hanford career, handling issues such as personnel dosimeter performance, 

calibration and, in particular, performing neutron radiation measurements using, for example, the 

DePanger Precision Long Counter developed at Hanford. The Long Counter was used to evaluate 

the neutron fluence when health physics dosimeters or health physics instruments were irradiated. 

The DePanger double moderator instrument was invented for monitoring neutron dose in the 

workplace. The instrument could measure a ratio that could be applied to the measurement to get the 

correct neutron dose as a function of neutron energy. Expert spent significant time in various 100 

Area reactors (i.e., B, D, KE, KW, N and perhaps F), 200 Area plutonium facilities, and 300 Area 

accelerator facilities, which were used to evaluate all Hanford neutron instrument and dosimeter 

systems. Site Expert stated that the original values to reconstruct 234-5Z worker exposures in the 

1972 AEC investigation depend on the method used to determine the ratios from the TLD data. For 

example, the calibration with the TLD dosimeter implemented in 1972 involved consideration of the 

combined phantom and dosimeter neutron response because of the so-called albedo effect. The 

TEPC was used to evaluate the TLD response on-phantom at 234-5Z workplaces and to use this in 

the development of the routine neutron calibration. Fundamentally, the distance of the mid-point of 

the phantom from the Hanford calibration source was used in routine calibration exposures and not 

the distance from the dosimeter mounted on the phantom to the source.

Site Expert 5 (Scalsky 2007b). Documented interview with Hanford Site Expert involved in the 

Hanford personnel dosimetry program beginning in the mid-1950s. Site Expert had numerous 

radiation safety individual contributor and management roles in the centralized Hanford radiological 

services organization involving calibrations, radiation standards and engineering, and radiological 

records and also in AEC/DOE Headquarter health physics programs.

Site Expert 6 (Scalsky 2007a)). Documented interview with Hanford Site Expert hired for work at 

Hanford plutonium facilities in 1947. Expert worked in all Hanford areas during his career at Hanford, 

participated in activities associated with the AEC 1972 Investigation of the increase in TLD-measured 

worker neutron doses in comparison with the NTA measured doses. Expert authored numerous 

technical reports including historical reviews of the Hanford radiation dosimetry program.

Site Expert 7 (Fix 2007e). Documented interview with Hanford Site Expert hired at Hanford in 1950 

for work in radiation protection with primary responsibilities in the 200 and 300 Areas, and also as the 

HP assigned to 100 Area biology operations. Later, this Site Expert assumed responsibilities for 

Hanford site-wide compliance with AEC/DOE Health and Safety (H&S) orders, directives, etc., as a 

senior health physicist.

G6.2 NTA PROCESSING FILES

Examination of the spreadsheet of Hanford NTA dosimeter processing during the period from 1950 

through 1961 (Yamauchi, 2006) shows dosimeter results for 300 Area located personnel beginning in 

1950. The number of 300 Area and the Hanford Site Total NTA processing results, respectively, for 

each of the files is shown in Table G-2. These results imply that Hanford radiation protection staff 

were aware of circumstances in 300 Area facilities with potential for neutron exposures. 

Unfortunately, the processing records shown in the Excel file do not identify the specific facility.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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G6.3 WORKPLACE MEASUREMENTS OF NEUTRON RADIATION 

The priority of data collection from the DOE-RL archival records concerned exotic chemicals at 

Hanford and neutron radiation surveys at the 100 Area reactors and the 200 Area plutonium facilities. 

Undoubtedly, radiation survey data for the 300 Area facilities is available from the federal repository in 

Seattle. Technical reports in which data have been gathered and analyzed are particularly helpful and 

tend to minimize uncertainty in the overall analysis. 

Table G-2. 300 Area and Hanford NTA processing results.

File name

Processing dates NTA resultsa

Start End Hanford total 300 Area

Person1.xls 3/13/1950 1/06/1953 13,535 63

Person2.xls 12/30/1952 4/3/1955 15,525 993

Person3.xls 4/4/1955 12/25/1955 7,139 599

Person4.xls 12/15/1955 6/17/1957 16,322 930

Person5.xls 6/17/1957 6/27/1958 13,738 400

Person6.xls 6/17/1958 5/26/1959 13,619 312

Person7.xls 5/27/1959 12/30/1959 9,109 38

Person8.xls 12/28/1959 11/14/60 16,330 187

Person9.xls 12/27/1960 6/27/1961 9,680 1,130

Person10.xls 7/14/1961 12/26/1961 9,776 1,739

a. Some test irradiation dosimeters included in totals.

G7. TECHNICAL REPORTS

Hanford documents identified that contained relevant 300 Area information concerning worker neutron 

exposure conditions follow:

• Operating standards (DuPont 1943–1946) that describe 300 level procedures in early 1944 to 

load, operate and calibrate the 305 Test reactor with specific safety notes that exposure to 

workers is a concern, there is a need to leave the immediate area and that boron lined 

proportional counters must be available to monitor potential exposures (i.e., neutron) to 

workers. 

• HW-32643, Monthly report, Class II Incident, neutron exposure 326 Building

• HW-32571, Monthly report, neutron exposure 326 Building

• BNWL-B-127 (Nichols et al. 1972) that provides dose results from parallel field tests of the 

TLD in the 308 Building along with the Hanford beta/photon film and, for some workers, NTA 

film. Information from this document is presented in Table G-3 because it illustrates one 

approach to determining a NP ratio. In Table G-3 the NP ratios for the 308 Bldg were 

calculated based on the photon and neutron instrument and TLD dose measurements shown 

in the original document.

Attachment D, Table D-2 provides a chronological listing of a large number of technical references 

along with brief summaries of those with particularly relevant information.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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Table G-3. NP Ratio determined from 1971 Workplace Study of Neutron Dose Measurements

(Nichols et al. 1972)a

Bldg. Location

Exp 

time 

(hrs)

Instrument

NP 

ratio TLD (mrem)

NP 

ratio

Snoopy CP TEPC Derma Pen SN FN

234-5 228-17DC 72.4 200 150 1.33 210 150 — 200 1.33

192-194 72.7 950 150 6.33 210 140 138 1360 10.70

228-H611 2.34 330 60 5.50 80 80 18 650 8.35

228-958 72.5 360 510 0.71 450 450 135 730 1.92

228-H618BS 72.5 360 510 0.71 100 100 6 170 1.76

194 2.75 550 90 6.11 60 60 9 390 6.65

221-Center 73 660 1,460 0.45 1,470 1,470 18 940 0.65

221-N 73 1,310 2,480 0.53 16,40 1,640 24 1,060 0.66

105-

KE

X-1 60 270 57 530

Top #23 1,400 1,700 141 4,100

Mon 0 0 <3 60

Front face 50 900 7 250

308 Room 208 2,000 2,700 84 3,700

Corr #7 4,200 14,100 390 11,100

Vent room 30 30 3 0

Room C 70 730 18 870

234-5 17DC 340 6 100

HC-11 280 12 180

9b top stairs 410 11 440

9B Under stairs 280 18 450

Room 221 410 790 18 460

Room 192 510 620 66 490

Room 192-C 150 230 6 240

Room 193 380 500 36 600

2731-Z 200 <3 50

a. Dosimeters mounted on carboys in workplace for designated exposure duration.

Another type of examination regarding the accuracy of TLD neutron dose measurements is made of 

summaries of field measurements published in 1981 and 1982 (Fix et al. 1981, 1982) which are 

presented in Tables G-4 and G-5, respectively. Measurements were done at the 308, 324 and 209-E 

buildings. These tables do not include a photon dose measurement, only a comparison of different 

methods to measure the workplace neutron dose. The measurements in these reports were 

performed with the objective to identify Hanford work areas in which analysis of the Hanford TLD 

could result in incorrect dose estimates to personnel. The studies included examination of workplace 

energy spectra and radiation type as well as a comparison of the neutron dose between several 

techniques of measuring neutron dose. The Tissue Equivalent Proportional Counter (TEPC) method 

is generally accepted as provided the best estimate of the actual neutron dose. As noted in these 

reports, the TLD tended to overestimate the instrument measured neutron dose on average. The TLD 

albedo dosimetry method is well known to overestimate the actual neutron dose in well shielded work 

areas because of its significant response to lower energy neutrons.

G8. RADIATION SURVEY DATA

As a component of the examination at DOE Hanford archive records containing workplace radiation 

survey sheets the team of health physicists was also attempting to identify potential documents 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 264 of 265

Table G-4. Summary of 1981 Hanford workplace neutron dose measurements (Fix et al. 1981).

Bldg Location

Energy

keVa

Neutron dose (mrem/hr) according to 

measurement methodb

MS Snoopy Rascal TEPC TLD TLD*

308 Pu storage vault 576 1.2 17.7

Above fuel storage pit 530 0.9 0.54 0.96

Above pit storage pit 1,100 0.8 2.0 1.3 1.2

0.46*

Fuel pin storage boxes on wall 660 4.1

Bare fuel subassembly 1,500 17.6 11

234-5Z HA-9A glovebox 395 4.4 4 4.7 1.7 0.9

HC-9B glovebox 390 12.1 11.5 12.7 14 7.4

18.7 9.8

2736-Z Vault 3 3EE-3FE 300 26.9 26 23.4 1.5 0.6

3.7 1.6

Vault 3 3CE-3DE 346 69.3 65 71.9

Vault 4 4ED-4FD 290 41.8 40 39.0

Vault 4 4GE-4NE 290 46.9 45 47.8 50.7 21.1

60.2 25.1

Hallway 146 1.3 0.8 1.0

Nuclear criticality detector 374 27.1 40

a. Average energy of neutron spectra

b. Measurement method: MS=multisphere, TEPC=Tissue Equivalent Proportional Counter, TLD=Hanford multipurpose 

dosimeter using normal algorithm, TLD* using alternate algorithm.

Table G-5. Summary of 1982 Hanford workplace neutron dose measurements (Fix et 

al. 1982).

Bldg Location

Measurement methoda

MS TEPC PTEPC He-3 Rascal Snoopy TLD

324 Pu storage vault 2.8 4.6 5.1 2.1 — 5.0 6.5

FFTF Location 8 3.8 5.6 — 14.7 13.0 18.0 29.1

Location 10 1.9 1.2 — 4.1 5.3 12.0 12.3

209-E Location 13 — 3.1 3.8 — — 2.0 1.8

Location 17 — — 0.6 — — 0.4 0.5

234-5

Maintenance office — 0.4 0.4 — — 0.5 0.4

Duct level, Col. 16 — — 1.6 — — 0.8 0.6

Duct level, under 52 — — 1.7 — — <0.1b 2.7

Duct level, over HA23 — — 2.6 — — 0.1b 5.1

Pu hood, top 2.8 14.7 12.3b 3.2 — 10.5c —

Pu hood, side — — 7.2 — — 7.0 —

General background — — 1.2 — — 1.5 —

a. MS–Multisphere, TEPC=Tissue Equivalent Proportional Counter, PTEPC=Portable Tissue Equivalent 

Proportional Counter, He-3=Helium-3 counter, TLD=Hanford multipurpose dosimeter.

b. These Snoopy readings are suspect due to geometry differences.

c. Average of four readings shown in table. 

concerning 300 Area facilities. Although undoubtedly extensive radiation surveys of 300 Area 

facilities were done, substantial records of these surveys for 300 Area facilities have not been 

collected to date likely because of the priority for the data collections for the single-pass cooling 

reactors, 100-N reactor, and Hanford 200 Area plutonium facilities. An example of workplace 

measurements obtained for 300 Area 305, 308 and 3745 facilities was obtained (BNL 1969–1970) 

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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Document No. ORAUT-TKBS-0006-6 Revision No. 04 Effective Date: 01/07/2010 Page 265 of 265

and there is a 1953 examination of 3745 facility calibration staff exposures (Unruh 1953). However, at 

this time, there is insufficient workplace survey data for the facilities to be included in an analysis.

G8.1 ANALYSIS OF NEUTRON TO PHOTON DOSE RATIO

An analysis file to be used in the analysis of workplace instrument measured NP dose ratio has not 

been prepared because currently there is only one file (BNL 1969–1970) with 300 Area facility data.

G9. SUMMARY

The Hanford 300 Area Reactor and Plutonium research, development and testing facilities, the 300 

Area Radiological Calibrations facilities, and the site critical mass facilities did involve neutron 

radiation exposure of workers as evidenced by: 1) the types of operations, 2) routine assignment of 

nuclear track emulsion (i.e., NTA) film, and 3) information in the routine radiation monitoring periodic 

reports. The operations in the 300 Area facilities supported the much larger 100 Area reactor and 200 

Area chemical processing and plutonium chemical-metallurgical facilities. Undoubtedly, extensive 

radiation surveys were taken of the 300 Area facilities because Hanford radiation safety standards 

applied to all facilities in the 100 Area, 200 Area and 300 Area facilities. Workers in the 300 Area 

would often travel to the 100 and 200 Areas. Additional data collection is necessary to determine a 

NP dose (NP) ratio for each of the facilities based on measured instrument results. Until this is done 

however, a feasible option is to adopt the dose reconstruction recommendation in the main body of 

this document to apply favorable-to-claimant NP ratios determined for the Hanford 100 Area singlepass cooling production reactors (Taulbee et al. 2008), Hanford 100 Area N Reactor (Attachment E) 

and Hanford 200 Area plutonium facilities (Attachment F) to workers according to their 300 Area work 

experience (i.e., apply NP ratios respectively for 100 Area reactor facilities and 200 Area plutonium 

facilities to 300 Area reactor and plutonium facilities) based on judgment by the dose reconstructor. 

Neutron exposures in the 120 Building and 209-E critical mass laboratories to workers did occur but 

were relatively insignificant because of the significant shielding and remote operation. Under all 

circumstances there was substantial photon radiation that was reasonably accurately measured in all 

facilities and for all periods that accompanied the neutron radiation.

As noted in this attachment, dose reconstruction would involve:

• TLD-measured neutron dose be used from January 1972 to date for all workers and Hanford 

facilities. 

• Prior to 1972, the measured (and missed) photon dose is multiplied by a NP dose ratio to 

arrive at an assigned neutron dose. The parameters of the NP dose distribution are taken 

from recommendations in the main document based on extensive measurements at the 

Hanford 100 Area single-pass cooling reactors and the 200 Area plutonium facilities.

The NP ratios must be adjusted to incorporate the ICRP Publication 60 weighting factors, which for 

the neutron categories in Hanford workplaces less than 2 MeV is a factor of about 2 (ICRP 1991). It is 

evident that using this approach will result in significant assigned neutron dose for the period prior to 

January 1, 1972.

ATTACHMENT G

A BOUNDING ESTIMATE OF NEUTRON DOSE BASED ON MEASURED PHOTON DOSE AT 

HANFORD 300 AREA AND MISCELLANEOUS FACILITY OPERATIONS AT THE HANFORD SITE 

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