ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

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DOE Review Release 09/16/2009

Document Title:

Los Alamos National Laboratory 

Bioassay Repository Database

Document Number: ORAUT-OTIB-0063

Revision: 00

Effective Date: 08/24/2009

Type of Document OTIB

Supersedes: None

Subject Expert(s): James M. O’Brien, Robert E. Burns, Jr.

Site Expert(s): N/A

Approval: Signature on File Approval Date: 08/20/2009

Robert E. Burns, Jr., Document Owner

Concurrence: Signature on File Concurrence Date: 08/20/2009

John M. Byrne, Objective 1 Manager

Concurrence: Keith A. McCartney Signature on File for Concurrence Date: 08/20/2009

Edward F. Maher, Objective 3 Manager

Concurrence: Signature on File Concurrence Date: 08/21/2009

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 08/24/2009

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-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 2 of 37

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

08/24/2009 00 Approved new technical information bulletin for Los Alamos National 

Laboratory Bioassay Data Project. Incorporates formal internal and 

NIOSH review comments. Training required: As determined by the 

Objective Manager. Initiated by Robert E. Burns, Jr.

Trademark Information

Microsoft®, Excel®, and AccessTM, are trademarks or registered trademarks of Microsoft Corporation in 

the United States and/or other countries. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 3 of 37

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

6

1.0 Introduction ...............................................................................................................................7

2.0 Purpose ....................................................................................................................................7

3.0 Background...............................................................................................................................7

4.0 In Vivo Data ..............................................................................................................................8

4.1 In Vivo Data Incorporated into the Bioassay Database .................................................. 8

4.2 Other Sources of In Vivo Data ..................................................................................... 10

5.0 In Vitro Data............................................................................................................................ 10

5.1 Pre-1991 In Vitro Data for Plutonium and Americium................................................... 10

5.2 Pre-1991 In Vitro Data for TUPo.................................................................................. 11

5.2.1 Pre-1991 Tritium Data...................................................................................... 14

5.2.1.1 Tritium Reporting Units ................................................................... 14

5.2.1.2 Tritium Sample Type Codes ........................................................... 15

5.2.1.3 Tritium Analysis Type Codes .......................................................... 15

5.2.1.4 Tritium MDCs.................................................................................. 15

5.2.1.5 Tritium Uncertainty.......................................................................... 15

5.2.2 Pre-1991 Uranium Data ................................................................................... 15

5.2.2.1 Uranium Reporting Units................................................................. 17

5.2.2.2 Uranium Sample Type Codes......................................................... 17

5.2.2.3 Uranium Analysis Type Codes........................................................ 17

5.2.2.4 Uranium MDCs ............................................................................... 18

5.2.2.5 Uranium Uncertainty....................................................................... 18

5.2.3 Pre-1991 Polonium Data.................................................................................. 19

5.2.3.1 Polonium Reporting Units and Unit Conversion .............................. 19

5.2.3.2 Polonium Sample Type Codes........................................................ 20

5.2.3.3 Polonium Analysis Type Codes ...................................................... 20

5.2.3.4 Polonium MDCs and Uncertainty.................................................... 20

5.3 POST-1991 In Vitro Data............................................................................................. 21

5.3.1 Post-1991 In Vitro Data for Tritium................................................................... 23

5.3.2 Post-1991 In Vitro Data for Polonium............................................................... 23

5.3.3 Post-1991 In Vitro Data for Thorium................................................................. 24

5.3.4 Post-1991 In Vitro Data for Uranium ................................................................ 24

5.3.5 Post-1991 In Vitro Data for Plutonium.............................................................. 25

5.3.5.1 Post-1991 In Vitro Data for 238Pu .................................................... 25

5.3.5.2 Post-1991 In Vitro Data for 239Pu .................................................... 26

5.3.5.3 Post-1991 In Vitro Data for 240Pu .................................................... 27

5.3.5.4 Post-1991 In Vitro Data for 239Pu+240Pu .......................................... 28

5.3.6 Post-1991 In Vitro Data for 241Am..................................................................... 28

6.0 Validation of TUPo Data Against Laboratory Notebooks ......................................................... 29

6.1 Validation of Tritium Records....................................................................................... 29

6.2 Validation of Uranium Records .................................................................................... 30

6.3 Validation of Polonium Records................................................................................... 33
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6.4 Review of Laboratory Notebooks for In Vitro Monitoring Data for Other 

Radionuclides.............................................................................................................. 33

7.0 Attributions and Annotations ................................................................................................... 34

References .........................................................................................................................................35

ATTACHMENT A, URANIUM NEUTRON ACTIVATION ANALYSIS .................................................. 36
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LIST OF TABLES

TABLE TITLE

4-1 Analytes listed for in vivo counting records in the ORAU Team’s database..............................

PAGE

8

5-1 Definition of fields in AccessTM database ................................................................................. 12

5-2 In vitro records for tritium, uranium and polonium in the pre-1991 data table.......................... 13

5-3 Analysis type codes for pre-1991 TUPo records .................................................................... 14

5-4 Data files with tritium records ................................................................................................. 14

5-5 Tritium data file field...............................................................................................................14

5-6 MDC values for tritium bioassay records in the ORAU database........................................... 15

5-7 Uncertainties for tritium bioassay records............................................................................... 15

5-8 Data files with “235U” records .................................................................................................. 16

5-9 Data files with “238U” records .................................................................................................. 16

5-10 “

235U” data file fields ............................................................................................................... 16

5-11 “

238U” data file fields ............................................................................................................... 17

5-12 Uranium analysis type codes ................................................................................................. 18

5-13 MDC values for uranium bioassay records in the ORAU database......................................... 18

5-14 Uncertainties for uranium bioassay records ........................................................................... 19

5-15 Polonium records data file...................................................................................................... 19

5-16 Polonium data file fields ......................................................................................................... 19

5-17 MDCs for polonium bioassay records..................................................................................... 20

5-18 Polonium uncertainty..............................................................................................................20

5-19 MDC values for polonium bioassay records in the ORAU database ....................................... 21

5-20 In vitro records in the post-1991 table of the ORAU database................................................ 21

5-21 Duplicate records in the post-1991 in vitro data table of the ORAU database......................... 22

5-22 Breakdown of kit types for post-1991 in vitro records ............................................................. 22

5-23 Analysis type codes for post-1991 in vitro records.................................................................. 23

5-24 Summary for uranium records in the post-1991 in vitro data .................................................. 24

5-25 Non-null results for routine uranium analyses in the post-1991 in vitro data ........................... 24

5-26 Distribution of plutonium records per sample in the post-1991 in vitro data ............................ 25

5-27 Summary for 238Pu records in the post-1991 in vitro data ....................................................... 26

5-28 Non-null results for routine 238Pu analyses in the post-1991 in vitro data................................ 26

5-29 Summary for 239Pu records in the post-1991 in vitro data ....................................................... 26

5-30 Non-null results for routine 239Pu analyses in the post-1991 in vitro data................................ 27

5-31 Summary for 240Pu records in the post-1991 in vitro data ....................................................... 27

5-32 Non-null results for routine 240Pu analyses in the post-1991 in vitro data................................ 27

5-33 Summary for 239Pu+240Pu records in the post-1991 in vitro data............................................. 28

5-34 Summary for 241Am records in the post-1991 in vitro data ...................................................... 28

5-35 Non-null results for routine 241Am analyses in the post-1991 in vitro data............................... 28

6-1 Data validation summary for TUPo records............................................................................ 29

6-2 Laboratory notebooks used to validate in vitro analytical results for tritium............................. 30

6-3 Tritium data validation summary............................................................................................. 30

6-4 Laboratory notebooks used to validate in vitro analytical results for uranium.......................... 30

6-5 Uranium data validation summary.......................................................................................... 33

6-6 Laboratory notebooks used to validate in vitro analytical results for polonium........................ 33

6-7 Polonium data validation summary......................................................................................... 33

A-1 MDCs for UNAA urinalysis at LANL ....................................................................................... 36
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ACRONYMS AND ABBREVIATIONS

BEST Bioassay Enrollment Scheduling and Tracking (System)

cpm counts per minute

d day

DOE U.S. Department of Energy

dpm disintegrations per minute

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

g gram

HPC Health Physics Checklist

hr hour

IVML In-Vivo Measurements Laboratory System

LANL Los Alamos National Laboratory

L liter

MDA minimum detectable activity

MDC minimum detectable concentration

min minute

ml milliliter

nCi nanocurie

NDA nondetectable activity

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

pCi picocurie

RaLa radioactive lanthanum

STEXT Standard Text

TIB technical information bulletin

TUPo tritium, uranium, polonium

UNAA Uranium Neutron Activation Analysis

U.S.C. United States Code

VAX Virtual Address Extension

μCi microcurie

μg microgram

§ section or sections
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 7 of 37

1.0

Technical information bulletins (TIBs) 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). TIBs may be used to assist NIOSH staff in the completion of 

individual dose reconstructions.

INTRODUCTION

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 of 2000 [42 U.S.C. § 7384l(5) and (12)].

2.0

The purpose of this TIB is to describe the information contained in the repository database created for 

Los Alamos National Laboratory (LANL) bioassay data. The repository database was created through 

a collaborative effort between the Oak Ridge Associated Universities (ORAU) Team and LANL staff to 

function as a repository for current and historical bioassay data for LANL workers. It is hosted and 

maintained by LANL. The ORAU Team has a subset (snapshot) of this database on its network for 

use in dose reconstruction, coworker studies, or other needs. The focus of this document is the 

contents of the database used by the ORAU Team and the sources of this information.

PURPOSE

3.0

Much of the historical bioassay data for LANL workers were archived from legacy computer systems 

that are no longer used. These obsolete formats made retrieval of this information impracticable, 

which was an impediment for the LANL staff in its efforts to respond to requests for internal monitoring 

data to support dose reconstruction under EEOICPA. In particular, bioassay data from before 1991 

were either essentially unavailable due to storage on obsolete archival systems, or were stored 

across numerous ad hoc systems that made them impracticable to retrieve. Given these difficulties, a 

joint effort was carried out between the ORAU Team and LANL staff to create and populate a single 

database for historical bioassay data for LANL workers. 

BACKGROUND

Based on a reconnaissance of the various databases and datasets that existed at LANL, it was 

decided to create the bioassay database by modifying LANL’s existing Bioassay Enrollment, 

Scheduling, and Tracking (BEST) system. This system already contained bioassay data from 

approximately 1991 to the present. Modification and adaptation of the BEST system was an iterative 

process that was carried out in parallel with the retrieval and evaluation of historical bioassay data. 

This TIB does not describe the modification of the BEST system. Its focus is the historical worker 

bioassay data incorporated into the database and related information pertinent to internal monitoring 

of LANL workers.

Beyond that already in the BEST system, the additional data incorporated into the database were 

derived from three principal sources:

• In vivo data from existing and historical databases,

• In vitro data for americium and plutonium from a standalone database, and

• In vitro data for tritium, uranium, and polonium (TUPo) from an obsolete electronic archive 

format.
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 8 of 37

Laboratory notebooks that contained historical bioassay data were also identified and retrieved. 

These notebooks were used to validate a number of the historical TUPo records, and also to search 

for data for other analytes of interest such as 90Sr and mixed fission products. 

4.0

4.1 IN VIVO DATA INCORPORATED INTO THE BIOASSAY DATABASE

IN VIVO DATA

Initially, in vivo counting data were in two databases maintained by the LANL In-Vivo Measurements 

Laboratory (IVML). One of them held data from the 1960s through 2003, and the other held data from 

2003 to the present. These two IVML databases were incorporated into the LANL bioassay database, 

from which the ORAU Team’s database was derived. 

The older IVML database did not report minimum detectable activity (MDA) values and contained 

count data only for positive results, i.e., if a count had not indicated positive activity then the record 

contained only the associated administrative information. The newer IVML database included MDA 

information from more recent counts. Both of the IVML databases contained records that showed 

“NDA” (nondetectable activity) or similar annotations, with no corresponding MDA value. It was 

common practice at LANL to count an individual and then manually look at the spectrum to see if any 

peaks were present. If peaks were noted, the nuclide was identified and an activity was established. 

If no peaks were seen it was simply annotated that way (i.e., as NDA). 

By far, the majority of the in vivo counting records in the ORAU Team’s database are counts for 241Am 

or 239Pu. Of the 106,950 in vivo records, 44,653 (41%) are counts for 241Am and 43,648 (41%) are for 

239Pu. The next largest contributors to the total number of in vivo records are 235U and 234Th. These 

analytes represent 5,685 and 5,680 records, respectively (5% each). The in vivo records in the LANL 

bioassay database specify 81 different analytes. These include specific radionuclides and other 

descriptors such as “mixed fission products” or “unidentified.” The analytes are shown in Table 4-1 

along with the corresponding total number of records, the number of non-null results, if any; and the

count date range. The in vivo records report a result or a MDA, but not both, i.e., the two are mutually 

exclusive. Thus, the non-null results are those where something other than a non-detection was 

reported. There were 28,514 non-null results, i.e., records that reported a value rather than a MDA,

among the 106,950 in vivo records (27%). Of these, 8,859 were less than zero and 1,123 were zero. 

It is not clear what was meant by reporting a non-null result for the “Unidentified” analyte or how the 

count data were converted to activity. The same can be said for the non-null results for “Fission

Prods” and “Tungsten.” All non-null in vivo results and MDAs in the database are reported in nCi. 

Table 4-1. Analytes listed for in vivo counting records in the ORAU Team’s 

database.

Analyte

Total 

records

Non-null 

records

Count date range

From To

AM-241 44653 7651 1/1/1969 2/11/2009

AS-72 3 3 9/14/1988 10/6/1989

BA-140 48 48 6/25/2008 2/2/2009

BE-7 934 186 5/12/1970 2/10/2009

BI-213 14 14 12/22/2004 2/10/2005

BI-214 6 6 1/5/1993 5/10/1993

BR-76 12 5 9/2/1980 11/16/1998

BR-77 17 10 9/2/1980 11/16/1998

C11N13 1308 143 5/12/1970 12/23/2003

CD-109 19 12 10/20/1976 11/16/1998

CE-141 8 1 9/2/1980 11/16/1998

CF-249 9 9 8/1/1979 2/24/1986

CM-244 1 0 3/6/2003 3/6/2003
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 9 of 37

Analyte

Total 

records

Non-null 

records

Count date range

From To

CO-56 1 1 9/16/1982 9/16/1982

CO-57 8 8 3/26/1982 12/7/1989

CO57CO58 1 1 5/23/1979 5/23/1979

CO-58 121 121 9/16/1982 2/10/2009

CO-60 76 63 8/6/1970 9/18/2007

CR-51 1 1 5/16/1985 5/16/1985

CS-134 128 115 8/6/1970 12/4/2006

CS-137 495 482 7/9/1969 2/2/2009

CU-64 1 1 2/9/1990 2/9/1990

CU-67 1 1 1/14/1983 1/14/1983

EU-152 451 27 9/7/1979 12/23/2003

FE-59 1 1 5/24/1985 5/24/1985

Fission prods 1 1 12/13/1972 12/13/1972

GD-146 115 115 12/4/2006 2/10/2009

GD-153 114 114 6/25/2008 2/10/2009

GE67GA67 1 1 12/2/1987 12/2/1987

GE68GA68 5 5 7/1/1985 11/25/1987

HF-173 3 1 3/13/1997 5/14/1999

HF-175 120 120 11/22/2005 2/10/2009

HG-195M 8 1 9/2/1980 11/16/1998

HG-197 154 147 9/2/1980 2/10/2009

HG-197M 8 1 9/2/1980 11/16/1998

HG-203 25 18 9/2/1980 11/16/1998

I-123 2 2 10/4/1984 10/4/1984

I-125 159 159 4/20/1976 5/22/1995

I-131 13 13 1/15/1970 4/3/1985

I-132 1 1 12/21/1989 12/21/1989

LA-140 48 48 6/25/2008 2/2/2009

LU-172 115 115 12/4/2006 2/10/2009

LU-173 114 114 6/25/2008 2/10/2009

Mixed activation products 7 0 3/5/1963 9/20/1963

Mixed fission products 7 0 3/5/1963 9/20/1963

MN-54 774 26 5/12/1970 12/4/2006

NA-22 1178 17 9/20/1979 12/23/2003

NA-24 6 2 5/12/1970 8/15/1975

NB-95 48 48 6/25/2008 2/2/2009

ND-147 8 1 9/2/1980 11/16/1998

OS-185 11 4 9/2/1980 11/16/1998

P-32 2 2 6/13/1972 6/13/1972

PB-212 15 15 3/6/1984 2/10/2005

PB-214 14 14 12/22/2004 2/10/2005

PU-238 110 110 7/17/1969 2/7/2007

PU238PU239 2 2 1/25/1982 2/1/1983

PU-239 43648 6646 1/1/1969 2/11/2009

RA-226 4 4 9/14/1970 10/25/2005

RB-83 13 6 9/2/1980 11/16/1998

RB-84 11 4 9/2/1980 11/16/1998

SB-124 11 4 9/2/1980 11/16/1998

SC-46 8 8 9/16/1982 7/14/1987

SE72AS72 1 1 10/12/1988 10/12/1988

SE-75 32 25 9/2/1980 11/16/1998

SM-145 8 1 9/2/1980 11/16/1998

TA-179 9 2 9/2/1980 11/16/1998

TA-182 114 114 6/25/2008 2/10/2009
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 10 of 37

Analyte

Total 

records

Non-null 

records

Count date range

From To

TE-132 1 1 12/21/1989 12/21/1989

TH-234 5680 5680 1/12/2004 2/11/2009

TL-201 11 4 9/2/1980 11/16/1998

TL-202 14 7 9/2/1980 11/16/1998

Tungsten 1 1 10/8/1993 10/8/1993

U-235 5685 5685 4/9/1975 2/11/2009

U-237 7 7 7/2/1975 2/1/1979

U-238 3 3 10/22/1979 6/21/2000

Unidentified 2 2 1/7/1975 4/6/1976

V-48 4 4 9/16/1982 9/13/1984

YB-169 115 115 12/4/2006 2/10/2009

ZN-65 11 11 7/30/1970 2/9/1990

ZR-95 49 49 10/26/1972 2/2/2009

ZR95NB95 3 3 12/5/1985 1/13/1986

4.2 OTHER SOURCES OF IN VIVO DATA

There are in vivo measurement data available at LANL in addition to those from the two IVML 

databases. Data exist from the pre-1960 period, but these counts were not considered to have been 

routine measurements and therefore were not included with the information in the IVML databases. In 

addition, some paper records exist, such as beige cards and white cards, that contain analyst 

comments on how radionuclide activities were calculated for individuals and physiological information 

such as chest wall thickness. This supplemental information was not included in the LANL bioassay 

database. 

5.0

The in vitro monitoring data consolidated into the LANL bioassay database came from four principal 

sources: (1) the existing BEST system, (2) a database of plutonium and americium results back to 

1944, (3) an electronic archive of TUPo data, and (4) LANL laboratory notebooks. 

IN VITRO DATA

The BEST system already contained in vitro (urinalysis and fecal) monitoring data for plutonium, 

americium, tritium, and uranium. These data, from both LANL and vendor laboratories, were believed 

to be complete back to approximately 1991. These more recent data served as a template for the 

other sources of in vitro monitoring data during the modification of the BEST system to create the 

LANL bioassay database. 

The in vitro data in the ORAU Team’s LANL bioassay database is stored in two tables: one for “pre1991” data and one for “post-1991.” The 1991 demarcation date is not absolute, as there are some 

post-1991 data in the pre-1991 table and vice versa. The data fields differ between the two tables, 

reflecting differences in how LANL recorded and managed bioassay data as its program evolved. 

5.1 PRE-1991 IN VITRO DATA FOR PLUTONIUM AND AMERICIUM

A large number of historical in vitro bioassay records for plutonium and americium had already been 

entered into a modern database. These records, which covered the period from 1943 through 1990, 

had been compiled for use in statistical studies and included urine, fecal, tissue (from autopsy), and 

associated incident-related data. The data were used along with modern data for the statistical 

assessments. 

The historical plutonium and americium records had some overlap with the existing BEST data, so 

they were checked for duplication before being incorporated into the LANL bioassay database. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 11 of 37

Information pertaining to incidents associated with specific bioassay records was included so the 

LANL database could serve as a consolidated source of historical plutonium and americium data. 

The ORAU Team’s version of the LANL bioassay database contains analysis results for 241Am, 238Pu, 

and 239Pu in its pre-1991 data table. 

The pre-1991 data table contains 58 records for 241Am. The collection dates for these range from 

2/17/1975 to 9/1/2000. All were analyzed by radiometric alpha spectrometry, denoted by the analysis 

type code RAS. 48 of the 58 results are tissue analysis data from the LANL human tissue program. 

Of the 10 non-tissue analyses, 7 are spot fecal and 3 are simulated 24-hour urine. The collection 

dates for these range from 6/23/1998 to 9/1/2000. The analysis results are reported in pCi/g. All of 

the urinalysis results are 0 pCi/g. For the fecal analyses, two of the results are negative and one is 

zero. No MDCs are given. 

The pre-1991 table contains 47,349 records for 238Pu covering a date range from 12/14/1967 to 

4/9/2000. 47,287 of the records (99.9%) are urinalyses, 55 are tissue analyses, and 7 are fecal 

analyses. The collection dates for the 7 fecal analyses match those for the 241Am records.

The collection dates for the 238Pu urinalyses range from 12/14/1967 to 7/4/1992. All results are in 

pCi/24 hours. 18,006 (38%) of the urinalysis results are negative and 8,582 (18%) are zero. No 

MDCs are given. For the analysis type the user is referred to (Clark 2005). 

The pre-1991 data table contains 91,445 records for 239Pu covering a date range from 8/1/1944 to 

4/9/2000. 91,375 (99.9%) of the records are urinalyses, 63 are tissue analyses, and 7 are spot fecal. 

The collection dates for the 7 spot fecal samples match those for the 241Am and 238Pu analyses. 

The collection dates for the 239Pu urinalyses range from 8/1/1944 to 5/13/1998. All results are in 

pCi/24 hours. 25,315 (28%) of the results are negative and 20,249 (22%) are zero. No MDCs are 

given. For all but 15 of the 239Pu urinalyses the user is referred to (Clark 2005) for the analysis type. 

The other 15 show analysis by RAS. 

5.2 PRE-1991 IN VITRO DATA FOR TUPO

Historical bioassay data for TUPo had been archived from a Digital Equipment Corporation Virtual 

Address Extension (VAX) computer system to a series of Standard Text (STEXT) files as described 

by Lawrence (1991). There were four groups of files that contained data for tritium, polonium, 235U, 

and 238U. The STEXT files had been transferred to LANL’s modern file server, but could not be used 

to generate data to support dose reconstruction because of the obsolete formats. Before migrating 

the information in these files to the bioassay database, legacy conversion software had to be used to 

extract the data and write them to spreadsheets. The spreadsheets were then imported into a 

Microsoft® AccessTM database as an interim step in preparing the data for upload to the new database. 

This interim AccessTM database used to manage and consolidate the TUPo data extracted from the 

VAX files. It should not be confused with the AccessTM database used by the ORAU Team. 

Documentation for the VAX file data fields was not found. Extracting the data into spreadsheets 

allowed delineation and definition of the data fields through discussions with LANL staff and 

examination of laboratory notebooks. The data fields varied from nuclide to nuclide and from file to 

file. It was necessary to work with each file individually to determine what data were provided and 

their format. The data field definitions that were determined for each file are presented in subsequent 

sections that address individual nuclides. 

Once the data fields were defined, an interim AccessTM database was created to contain the 147,690 

records from the archived VAX files. Additional fields were defined to capture any revisions made to 

the data while preserving the original. These included a “Data_Comments” field to incorporate 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 12 of 37

comments to explain changes, questions, or other issues associated with the original data. Table 5-1 

shows the data fields for the interim AccessTM database.

Table 5-1. Definition of fields in AccessTM database.

Field name Data type Description Comment

Name Text Employee name

Z_Num Text Employee number Not all VAX data in this field were true 

Z (employee) numbers. In some 

cases V (visitor) numbers were still 

present. In others an alphanumeric 

identification number was used.

GrpEmp Text Employer and group identification

S_Date Double Original bioassay sample date

Rev_S_Date Double Revised bioassay sample date Revised or corrected date.

S_Type Text Bioassay sample type code

S_Res Double Original bioassay sample result

S_Units Text Original bioassay reporting units

Rev_S_Res Double Revised bioassay sample results Revised or corrected results.

Rev_S_Units Text Revised bioassay reporting units Revised or corrected reporting units.

Report_Res Double Reported bioassay results In some cases bioassay results were 

converted to and reported in different 

units than the original data.

Report_Units Text Reported bioassay units

Uncert Single Estimate of measurement uncertainty 

Uncert_Units Text Uncertainty units

Uncert_Code Text Uncertainty code Specifies the level of confidence in the 

uncertainty estimate.

S_MDA Double Bioassay sample MDC

Rev_MDA Double Revised bioassay sample MDC Revised or corrected MDC.

MDA_Units Text MDC reporting units

S_Size Text Bioassay sample size Sample size was rarely reported. 

Bioassay results were typically 

normalized to sample volume.

Size_Units Text Bioassay sample size units

Book Text LANL Notebook number Provided notebook and page 

reference for bioassay results 

recorded in VAX data files.

Page Double Notebook page reference

Rev_Book Text Revised notebook number Revised or corrected notebook 

reference.

Rev_Page Double Revised page reference Revised or corrected page reference.

Analyst Text Laboratory technician ID (usually 

initials)

A_Type Text Code specifying analytical method

Book_Comments Text Original comments from laboratory 

notebook

Limited data field space restricted 

frequent incorporation of laboratory 

notebook comments. When these 

comments were found in the VAX files, 

they were preserved in this field. 

Nuclide Text Radionuclide Specifies H3, U235, U238, or Po.

Data_Comments Memo Data review comments

XLS_Date Date/time S_Date in Excel® date format S_Date and Rev_S_Date are provided 

in Excel® date format to allow sorting 

by date and time.

Rev_XLS_Date Date/time Rev_S_Date in Excel® date format

Data_File Text VAX data file reference VAX data file name for original 

electronic data.

Validated Yes/no Logical flag used to indicate 

validated data record
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 13 of 37

LANL staff indicated that a substantial effort had been made to address inconsistencies in the 

personnel information contained in the VAX files. Particular attention was paid to correcting employee

numbers (“Z_Num”), which were not recorded in some of the early laboratory notebooks. LANL 

attempted to assign Z numbers where possible, but there were approximately 2,000 records with no 

value in the Z_Num field. Some of the records (311) contained a V number that LANL used at one 

time for visitors. Other early records (341) contained an alphanumeric identification code.

Minimum detectable concentrations (MDCs) were reported for some, but not all, data. During early 

LANL operations (before 1970), it was not uncommon for the Laboratory to record only positive 

bioassay results and not report MDC values. In most cases, “0.00” was reported. The ORAU Team’s 

AccessTM database (derived from the primary bioassay database) contains a “MDA” field. The data in 

this field are a mixture of recording levels and analytical MDA values inferred from procedures or 

laboratory notes. These values are discussed in the following sections that address the individual 

nuclides.

Uncertainty estimates were not present in the historical TUPo data. In some cases it was possible to 

state uncertainties for a specific period based on procedures or laboratory notes. In other cases it 

was not possible to provide an estimated uncertainty. Uncertainties are discussed for each nuclide in 

the following sections.

A cursory comparison between the data from the VAX files and that from the laboratory notebooks 

from which they originated suggested a rather high rate of disagreement (~20%). This prompted an 

effort to validate a portion of the TUPo data from the VAX files to better gauge its reliability. 

Approximately 10% of the VAX records were validated against the LANL notebooks from which they 

originated. This validation process is described in Section 6.0. 

The pre-1991 in vitro data table in the ORAU Team’s database contains a total of 144,624 records for 

tritium, uranium, and polonium. Table 5-2 shows the number of records and collection date range for 

each analyte. 

Table 5-2. In vitro records for tritium, uranium and 

polonium in the pre-1991 data table.

Analyte Number of records Collection date range

H-3 49,218 6/23/1950–12/31/1990

U-235 43,545 4/6/1955–12/31/1990

U-238 46,662 11/18/1949–12/31/1990

Po 5,199 3/11/1947–3/24/1965

The data fields for the pre-1991 in vitro data include the “kit type”, i.e., the collection protocol; and the 

sample type. All but 46 of the 144,624 pre-1991 TUPo records are for urinalyses. All but 14 of the 

urinalyses were spot samples. The remainder were simulated 24 hour collections. The 46 non-urine 

TUPo records consist of 40 records for spot fecal analyses and 6 for intravenous blood analyses. All 

46 of the non-urinalyses records are analyses for polonium. 

The analysis type codes for the pre-1991 TUPo records in the ORAU database are shown in Table 

5-3. All of the codes are specific to one radioelement or radioisotope. 

The T3R analysis type in Table 5-3 includes liquid scintillation counting, used from 1969 forward, and 

use of an internal GM counter prior to that time (Clark 2005). 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 14 of 37

Table 5-3. Analysis type codes for pre-1991 TUPo records.

Code Analysis type

GB gross alpha/beta (polonium only)

POR polonium radiometric (polonium only)

T3R tritium radiometric (tritium only)

UF uranium fluorophotometric (238U only)

UNAA delayed neutron activation analysis (235U and 238U only)

UR uranium radiometric (235U only)

5.2.1

50,107 tritium bioassay result records were extracted from the VAX files. These records, covering a 

period from June 23, 1950 to December 31, 1990, included some analyses for non-LANL workers. 

These were removed from the ORAU Team’s AccessTM database. The ORAU database therefore 

contains 49,218 tritium records. These records cover the same date range as the VAX records, i.e., 

from June 23, 1950 to December 31, 1990.

Pre-1991 Tritium Data

Tritium records were extracted from the six VAX data files shown in Table 5-4. Table 5-5 lists the 

original data fields identified in the six tritium data files.

Table 5-4. Data files with tritium records.

File name

Number of 

records Comments

seza5063 17,737 Contains tritium records for 6/23/50 to 12/31/63

seza6475 9,932 Contains tritium records for 1/2/64 to 12/31/74

seza7583 9,961 Contains tritium records for 1/3/75 to 12/30/83

seza8488 8,099 Contains tritium records for 1/3/84 to 12/30/88

st389 1,989 Contains tritium records for 1/3/89 to 12/28/89

st390 2,389 Contains tritium records for 1/2/90 to 12/31/90

Table 5-5. Tritium data file field.

Field

File names

seza5063

seza6475

seza7583

seza8488 st389 st390

Field columns

Employee Name 2–18 2–18 2–19

Z-Number 19–25 19–24 20–25

Employee Code 26–31 25–34 26–31

Birth Year 32–33 Not used 32–33

Sample Date 36–41 35–40 36–41

Sample Type Code Not used 41–42 Not used

Results 42–51 43–50 42–51

LANL Notebook ID Not used 51–57 Not used

LANL Notebook Page Not used 58–60 Not used

Analyst ID Not used 61–66 Not used

Analysis Type Code Not used 67–69 Not used

Sequential Record ID Not used 70–75 Not used

5.2.1.1 Tritium Reporting Units

In the VAX files, all tritium results were reported using the units code “UL”, indicating microcuries per 

liter. Tritium results were never corrected for void time. Because historical documentation indicated 

that all tritium results were calculated in terms of microcuries per liter, any results for which units were 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 15 of 37

missing were updated to reflect these units. Thus, all of the tritium results in the ORAU database are 

in units of μCi/L. 

5.2.1.2 Tritium Sample Type Codes

Tritium sample type codes were not always recorded in the VAX files. However, those records for 

which a sample type code was given always showed “U1”, indicating a spot urine sample. Thus, all of 

the tritium records in the ORAU database are spot urine samples. 

5.2.1.3 Tritium Analysis Type Codes

The tritium VAX files contained the analysis type codes “H3R”, “T3R”, “33”, “H3”, “T#R”, and “T3”. 

There were 242 records for which no analysis type code was entered. Although two different 

analytical techniques were used for tritium analysis (Clark 2005), it appears that codes “H3R” and 

“T3R” were used interchangeably and did not distinguish between the two different techniques. Thus, 

the analysis type codes “H3R”, “33”, “H3”, “T#R”, and “T3” were all changed to T3R for consistency. 

All of the tritium records in the ORAU database therefore show T3R as the analysis type code. 

5.2.1.4 Tritium MDCs

The recording of MDCs in the VAX files varied over time. Early data contained no MDC information, 

with nondetections being reported as “0.00.” Later data indicated MDC values by using an “L” as a 

prefix (e.g., “L1.00” meant less than 1.00). To present MDC information consistently in the new 

database, all results below MDC were reported as “0.00” in the sample result field. 

Unlike the other TUPo records, all of the tritium records in the ORAU database have a value in the 

“MDA” field. (“MDA” is the name of the field in the ORAU database that contains MDC values.) 

These values are shown in Table 5-6. These MDC values should be regarded as recording levels. 

Table 5-6. MDC values for tritium bioassay 

records in the ORAU database.

Period MDC Value

6/23/1950–12/9/1987 1.0 μCi/L

12/11/1987–12/31/1990 0.1 μCi/L

5.2.1.5 Tritium Uncertainty

Uncertainty information was not recorded in the VAX files. Reviews of laboratory procedures, 

notebooks, and memoranda provided some information for uncertainty estimates. This information is 

summarized in Table 5-7.

Table 5-7. Uncertainties for tritium bioassay records.

Period Analytical method Uncertainty statement Reference

ca. 1954 Internal Geiger-Mϋller ±5% between the range of 1 to 250 μCi/L McClelland et al. 

(1955, Ch. 26, p. 140)

1958–1967 Internal Geiger-Mϋller 1 to 2 μCi/L at 1 μCi/L

9.5 to 10.5 μCi/L at 10 μCi/L

99 to 101 μCi/L at 100 μCi/L

Lawrence (1958)

1968–1990 Liquid scintillation ±5% (1-sigma) at 1 μCi/L Lawrence (1987)

5.2.2

Uranium bioassay records were extracted from the VAX data files listed in Table 5-8 and 5-9 for “235U” 

and “238U”, respectively. It is important to note that LANL used “235U” to refer to enriched uranium and 

Pre-1991 Uranium Data
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 16 of 37

“

238U” to refer to depleted or normal uranium. The use of “235U” or “238U” in bioassay results did not 

imply that radionuclide-specific analyses were performed. 

Table 5-8. Data files with “

235U” records.

File name Records Comments

sag5574 8,953 Contains U-235 records for last names A to G for 

4/08/55 to 12/20/74.

shn5574 7,352 Contains U-235 records for last names H to N for 

4/11/55 to 12/20/74.

soz5574 10,151 Contains U-235 records for last names O to Z for 

4/06/55 to 12/20/74

su57581 11,594 Contains U-235 records for 1/03/75 to 12/25/81.

su235a-z.1982-88 4,929 Contains U-235 records for dates 12/25/81 to 2/19/88. 

Also includes two records dated 7/09/62 that are of 

questionable value based on examination of notebook 

data.

su5o89 272 Contains U-235 records for 1/03/89 to 12/18/89

su5o90 400 Contains U-235 records for 1/02/90 to 12/31/90

Table 5-9. Data files with “

238U” records.

File name

Number 

of records Comments

su238a 9,889 Contains U-238 records for last names A to G for 

11/18/49 to 12/13/74.

su238b 9,699 Contains U-238 records for last names H to N for 

11/18/49 to 12/13/74.

su238c 10,014 Contains U-238 records for last names O to Z for 

11/18/49 to 12/13/74.

su87581 11,830 Contains U-238 records for 1/03/75 to 12/25/81. 

su238a-z.1982-88 5,159 Contains U-238 records for 2/19/81 to 12/21/88.

su8o89 604 Contains U-238 records for 1/03/89 to 12/19/89.

su8o90 959 Contains U-238 records for 1/02/90 to 12/31/90.

sPOL4765.dat 6 These records were found in the polonium data files. 

The original data fields identified in the uranium data files are listed in Tables 5-10 and 5-11 for the 

“

235U” and “238U” records, respectively.

Table 5-10. “235U” data file fields.

Field

File names

sag5574

shn5574

soz5574

su57581

su235a-z.1982-88

su5o89

su5o90

Field columns

Employee Name 2–19 2–19 1–18

Z-Number 20–24 20–24 19–23

Employer Code 25–34 25–34 24–33

Sample Date 35–40 35–40 34–39

Sample Type Code 41–42 41–42 Not used

Results 43–50 43–50 40–47

Result Units 51–52 51–52 48–49

LANL Notebook ID 53–57 53–57 Not used

LANL Notebook Page 58–60 58–60 Not used

Analyst ID 61–67 61–67 Not used

Analysis Type Code 68–69 68–72 52–55

Nuclide ID Not used 73–76 57–60
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 17 of 37

Table 5-11. “238U” data file fields.

Field

File names

su238a

su238b

su238c

su87581

su238a-z.1982-88

su8o89

su8o90

Field columns

Employee Name 2–19 2–19 1–18

Z-Number 20–24 20–24 19–23

Employer Code 25–34 25–34 24–33

Sample Date 35–40 35–40 34–39

Sample Type Code 41–42 41–42 Not used

Results 43–50 43–50 40–47

Result Units 51–52 51–52 48–49

LANL Notebook ID 53–57 53–57 Not used

LANL Notebook Page 58–60 58–60 Not used

Analyst ID 61–67 61–67 Not used

Analysis Type Code 68–69 68–72 52–55

Notebook Comments 70–85 Not used Not used

Nuclide ID 86–90 73–76 57–60

Sequential Record ID 93–97 Not used Not used

5.2.2.1 Uranium Reporting Units

From 1955 through 1976 urinalysis results for the “235U” records in the VAX files were reported with a 

unit code of “DM” for disintegrations per minute per liter. Starting in 1977, the “

235U” unit code became 

“PL” for picocuries per liter. “

238U” bioassay results in the VAX files were reported using the unit code 

“UL” for micrograms per liter. In the ORAU database, all of the 235U results are reported in units of 

picocuries per liter. All 238U results are reported in micrograms per liter. 

5.2.2.2 Uranium Sample Type Codes

The uranium sample type codes found in the VAX files were “U1”, “U4”, “U5”, “U6”, and “U8”. One 

record indicated a sample type code of “U1Y”, which was assumed to be an error and changed to 

“U1”.

The “U1” sample type code specified a spot urine sample. Sample type code “U5” indicated a fourbottle kit that was collected as a true 24-hour collection. The code "U6” was only used for 2 “235U” 

results and 20 “238U” results.

In the ORAU database, all but 14 of the 235U records are spot urine samples. The other 14 records 

are simulated 24 hour urine samples collected in August and September of 1969. All of the 238U 

records are spot urine samples. 

5.2.2.3 Uranium Analysis Type Codes

The uranium analysis type codes found in the VAX files are listed in Table 5-12. Of these, only three 

(“UF”, “UNAA”, and “UR”) appeared to reflect analysis types that were routinely used in a given era. 

The remaining analysis type codes were treated as ad hoc designations or transcription errors 

because of the few times they occurred. These were changed to UF, UNAA, or UR, as appropriate, 

based on analyte and analysis date. Uranium neutron activation analysis (UNAA) is discussed in 

Attachment A. 

In the ORAU database, all of the 235U records have an analysis type of either UR or UNAA. All of the 

238U records are either UF or UNAA. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 18 of 37

Table 5-12. Uranium analysis type codes.

Analysis 

code Meaning Record type

46 Meaning unknown–referenced once U-238

COLOR Meaning unknown–referenced 3 times U-238

CPMS Meaning unknown–referenced once U-238

U Meaning unknown–referenced 7 times U-238

U6 Meaning unknown–referenced once U-238

U6F Meaning unknown–referenced once U-238

U9 Meaning unknown–referenced 5 times U-235

UF Uranium fluorophotometric U-238

UNAA Delayed Neutron Activation Analysis U-235 and U-238

UR Uranium radiometric U-235

5.2.2.4 Uranium MDCs

MDC information was not provided in the VAX data until 1962 for “

235U” records and until 1968 for 

“

238U” records. The values in the “MDA” field of the ORAU database for the 235U and 238U records are 

shown in Table 5-13. Values are given by date range for the two analysis type codes used for each 

nuclide, and include information on records for which no MDC value is provided. For these records 

the MDC value is given as “null.” For the 235U records, all of the MDC values are in units of picocuries 

per liter. In cases where the “MDA” value in the database reflects a units conversion from its historical 

value, the historical value is shown in parentheses. In general the MDC values in the ORAU 

database, where given, should be regarded as recording levels. 

Table 5-13. MDC values for uranium bioassay records in the ORAU database.

Nuclide Analysis type Period “MDA” value

U-235

UR

(uranium radiometric)

4/6/1955–2/6/1981 null

7/31/1962–1/17/1964 3.15 pCi/L (7 dpm/L)

1/7/1977–11/24/1980 4.00 pCi/L

6/18/1976–12/17/1976 4.50 pCi/L (10 dpm/L)

3/19/1971–6/4/1976 5.41 pCi/L (12 dpm/L)

11/8, 11/12, & 11/22 1963 

(3 records)

6.76 pCi/L (15 dpm/L)

12/20/1974 (1 record) 7.00 pCi/L

UNAA

(delayed neutron activation analysis)

8/19/1977–8/29/1988* null

8/12/1977–12/31/1990* 4.00 pCi/L

U-238

UF

(uranium fluorophotometric)

11/18/1949–8/20/1982 null

3/1/1976–8/25/1978 1.00 μg/L

1/15/1968–8/20/1982 4.00 μg/L

9/3/1982 (1 record) 20.00 μg/L

UNAA

(delayed neutron activation analysis)

1/13/1978–12/19/1988 null

1/13/1978–6/25/1982 1.00 μg/L

7/6/1982–12/31/1990 4.00 μg/L

1/7/1983 (23 records) 11.00 μg/L

*There are two 235U records that show an analysis type of UNAA and a sample collection date of 7/9/1962. These are 

assumed to be an error either in the collection date or the analysis type. 

5.2.2.5 Uranium Uncertainty

Uncertainty information was not recorded in the VAX data files. Reviews of laboratory procedures, 

notebooks, and memoranda provided the information in Table 5-14.
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 19 of 37

Table 5-14. Uncertainties for uranium bioassay records.

Record 

type Period

Analytical 

method Uncertainty statement Reference

U-235

Uncertain Radiometric At spike levels of 32 and 64 

dpm/L recovery is 83% ±16%

LANL (1978, 

Section 13)

Starting 1978 Delayed neutron 

counting

±0.4 pCi/L at 5.2 pCi/L

±0.6 pCi/L at 13.9 pCi/L

±1.6 pCi/L at 26.1 pCi/L

overall: ±6% (1 sigma)

Gautier (1983); LANL 

(1983)

U-238

1949–1955 and 

perhaps up to 1978

Fluorophotometric ±10% McClelland et al. 

(1955, Ch. 27, p. 155)

In place in 1978 but 

possibly earlier

Fluorophotometric ±4% relative standard deviation 

at 20 μg/L

LANL (1978, 

Section 14)

Procedure effective 

date 10/1/82

Colorimetric Average recovery of standard is 

±8% at the 11 μg/50 cm3

concentration level

Gautier (1983); LANL 

(1983)

Starting 1978 Delayed neutron 

counting

±0.3 μg/L at 4.2 μg/L

±0.4 μg/L at 8.5 μg/L

±0.5 μg/L at 16.9 μg/L

Overall: ±8% (1 sigma)

Gautier (1983); LANL 

(1983)

5.2.3

Bioassay records for polonium were extracted from the VAX data files shown in Table 5-15. The 

original data fields identified for the polonium data files are given in Table 5-16.

Pre-1991 Polonium Data

Table 5-15. Polonium records data file.

File name No. of records Comments

sPOL4765.dat 5,676 3/11/47 to 3/24/65

Table 5-16. Polonium data file fields.

Field

File name

SPOL4765.dat

Field columns

Employee Name 2–19

Z-Number 20–24

Employer Code 25–34

Sample Date 35–40

Sample Type Code 41–42

Results 43–50

Result Units 51–52

LANL Notebook ID 53–57

LANL Notebook Page 58–60

Analyst ID 61–66

Analysis Type Code 67–69

5.2.3.1 Polonium Reporting Units and Unit Conversion

The polonium bioassay results in the VAX files were initially reported with a unit code of “CM” for

counts per minute per 24 hours. Starting in November of 1952 results began to be reported using a 

unit code of “DM” for disintegrations per minute per liter. A few results continued to be reported as 

“CM” through January of 1953. For consistency, the “DM” data were converted to picocuries per day 

by assuming a urine output of 1.4 L/d as follows:

dpm/L × 0.63 = pCi/d (1)
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 20 of 37

Counts per minute data were not converted because the counting efficiencies were unknown. 

In addition to routine urinalysis results, the polonium data included records for 6 blood and 40 fecal 

analyses. Blood analysis results were reported using the unit code “DM”, which in this case indicated 

disintegrations per minute per milliliter of blood. Fecal results were reported using the unit code “NCI” 

for nanocuries per gram. 

All of the polonium records in the ORAU database, including those for blood and fecal analyses, have 

results in units of either cpm per liter or picocuries per liter. The date ranges for these overlap: results 

in cpm/L occur from 3/11/1947 through 1/9/1953, and those in pCi/L occur from 2/10/1948 through 

3/24/1965. 

5.2.3.2 Polonium Sample Type Codes

Four sample type codes were present in the polonium data extracted from the VAX files: “U1”, “U6”, 

“B1”, and “F7”. The first two indicated urine samples, with “U1” signaling a spot sample and “U6”

specifying a “simulated” 24-hour sample. Sample type code “B1” was used for blood samples, and 

“F7” was used for fecal samples. 

Of the 5,199 polonium records in the ORAU database, 40 are spot fecal samples, 6 are intravenous 

blood samples, and the remainder are spot urine samples.

5.2.3.3 Polonium Analysis Type Codes

The polonium VAX files contained the analysis type codes “GB” or “POR”. “GB” indicated gross alpha

and beta and was used for only 13 polonium records. “POR” indicated polonium radiometric analysis. 

In the ORAU database, there are the 13 GB analyses and 5,186 POR results. The 13 GB analyses 

were performed for spot urine samples collected on 2/18/1960 (1 record), 2/19/1960 (8 records) , or 

2/23/1960 (10 records). The POR analyses were performed for spot urine, spot fecal, or intravenous

blood samples over the period 3/11/1947 through 3/24/1965. 

5.2.3.4 Polonium MDCs and Uncertainty

The polonium VAX files contained no information on MDCs or uncertainty. MDCs were inferred from 

procedures and reports. Gautier (1983, Procedure R160) describes the general method for polonium 

bioassay analysis and provides the MDC and uncertainty values given in Tables 5-17 and 5-18. 

Table 5-17. MDCs for polonium bioassay

records.

Period

Analytical 

method

Analytical 

MDC

Up to 1955 Radiometric 10 dpm/L

1955–1965 Radiometric 0.1 pCi/L

Table 5-18. Polonium uncertainty.

Period

Analytical 

method Uncertainty statement Reference

Effective 5/1/1955 Radiometric ±3% (±1 sigma) at the 

15-pCi concentration level

Gautier (1983, 

Procedure R160-1)

In the ORAU database, none of the 13 polonium records analyzed via gross alpha/beta counting 

(analysis type GB) have a MDC reported in the “MDA” field. The MDC values given for the 5,186 

records analyzed by polonium radiometric analysis are given in Table 5-19. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 21 of 37

Table 5-19. MDC values for polonium bioassay records in the ORAU

database.

Period Analysis Type ”MDA” Value

3/11/1947–3/24/1965 POR null

1/3/1955–12/14/1955 POR 0.1 pCi/L

1/11/1954–8/10/1955 POR 4.50 pCi/L (10 dpm/L)

5.3 POST-1991 IN VITRO DATA

The post-1991 in vitro data table in the ORAU Team’s database contains a total of 244,760 records 

covering a range of collection dates from 12/29/1973 to 2/9/2009. Table 5-20 shows the analytes, 

numbers of records, and collection dates for the post-1991 in vitro data. In many cases there are 

multiple records for a given bioassay sample, as some samples were subjected to more than one type 

of analysis. This is particularly true for plutonium analyses. Thus, the number of records exceeds the 

actual number of bioassays. For each record the analysis result (if any) is reported in one of three 

ways: activity in terms of normalized excretion or excretion rate, activity per sample, or activity per 

aliquot. Only one of the three result types is reported for a given record, though more than one result 

may be reported for a given sample and analyte. This is seen with the plutonium and americium 

analyses, where samples may be analyzed by more than one analysis technique depending on what 

the initial count showed. In these cases multiple analysis results can appear for the same sample and 

analyte, with the results reported either as the same type or on different bases (e.g., on a normalized 

excretion basis and per sample basis). There are also records for which no result of any type is 

reported. This occurs with nearly all of the in vitro analytes, but is especially prevalent for the 240Pu 

analyses, where approximately half of the records do not show a result. These null results for 240Pu 

reflect the use of mass spectrometry analysis. It is not clear why there appears to be a gap in the in 

vitro bioassay records for January through June of 1991. The gap exists for the 241Am and 238,239Pu

analyses in addition to tritium and uranium. 

Table 5-20. In vitro records in the post-1991 table of the ORAU database.

Analyte

Urinalysis 

records

Fecal analysis 

records Total records

Collection date range

From To

AM-241 2,456 201 2,657 12/29/1973 1/19/2009

H-3 28,246 0 28,246 6/17/1991 2/9/2009

PO-210 69 0 69 6/13/2007 10/3/2008

PU-238 57,000 252 57,252 12/29/1973 1/30/2009

PU-239 77,351 252 77,603 12/29/1973 1/30/2009

PU-239+PU-240 13,517 0 13,517 12/6/1996 1/30/2009

PU-240 12,487 0 12,487 1/26/1997 1/30/2009

TH-228 13 0 13 1/27/2005 5/28/2008

TH-229 13 0 13 1/27/2005 5/28/2008

TH-232 4 0 4 1/20/2008 5/28/2008

U-234 17,627 6 17,633 7/1/1991 1/21/2009

U-235 17,627 6 17,633 7/1/1991 1/21/2009

U-238 17,627 6 17,633 7/1/1991 1/21/2009

The post-1991 in vitro dataset received from LANL contained a number of duplicate records. 

Duplicates in this context means the same result being reported more than once for the same Sample 

ID. It does not refer to cases where there are different results reported for the same sample, 

reflecting different analysis types or reporting basis.

The number of duplicate records noted for each in vitro analyte are summarized in Table 5-21 for 

each of the three types of analysis result. Activity_PA and Activity_PS refer to the activity per analysis 

and per sample, respectively. Activity refers to activity in terms of excretion. These are the field 

headings used in the in vitro data table. An entry of n/a in Table 5-21 means there were no results of 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 22 of 37

that type in the dataset for that analyte. The numbers of duplicates are the same for the three 

uranium isotopes because all uranium samples are analyzed for all three nuclides. Likewise, there is 

a 239Pu result corresponding to each 238Pu result, though there can be additional 239Pu results for a 

given sample if follow-up analysis was performed. 

Table 5-21. Duplicate records in the post-1991 in vitro data table of 

the ORAU database.

Analyte

Number of duplicate records

Activity_PA Activity_PS Activity

AM-241 56 1 67

H-3 n/a n/a 28

PO-210 0 n/a n/a

PU-238 0 0 2

PU-239 0 0 2

PU-239+PU-240 n/a 0 n/a

PU-240 n/a 0 0

TH-228 0 n/a n/a

TH-229 0 n/a n/a

TH-232 0 n/a n/a

U-234 329 51 834

U-235 329 51 834

U-238 329 51 834

For all analytes except plutonium, the duplicate records were cases where the same results were 

reported with the same sample volume given in different units. Specifically, the duplicates occurred 

when the same result was reported twice: once with the sample volume stated in grams, and a 

second time with the same sample volume stated in volume units (liters or milliliters). For plutonium, 

there are only two samples (4 records) that were duplicated. These were cases where the same 

results were reported twice for the same samples, but showed different analysis types. Users should 

be aware of the possibility of duplicate records in the post-1991 in vitro dataset and confirm that there 

is not more than one instance of the same result for a given Sample ID. 

The data fields for the post-1991 in vitro data include the schedule type and the kit type. There are 

three possible values for the schedule type and six different kit types. The three schedule types and 

the corresponding fraction of the total post-1991 in vitro records are Prompt Action (1%), Special 

(14%) and Routine (85%). Thus, the post-1991 in vitro data are predominantly routine bioassays. 

The six kit types are 500 mL Sample, Simulated 24 Hour, Spot Fecal, Spot Sample, Timed Voidings, 

and True 24 Hour. The 500 mL Sample kit was used for uranium, 210Po, 228Th (1 record), and 229Th (1 

record). The Spot Sample was used only for tritium. 

Table 5-22 shows the breakdown of the post-1991 in vitro records by kit type for each of the three 

schedule types. 

Table 5-22. Breakdown of kit types for post-1991 in vitro records.

Schedule type Kit type Fraction

Prompt action

500 ml sample 1%

Simulated 24 hour 79%

Spot fecal 9%

Spot sample (tritium only) 1%

Timed voidings --

True 24 hour 10%

Special 500 ml sample 5%

Simulated 24 hour 89%
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 23 of 37

Schedule type Kit type Fraction

Spot fecal 0.2%

Spot sample (tritium only) 5%

Timed voidings 0.3%

True 24 hour 1%

Routine

500 ml sample 25%

Simulated 24 hour 63%

Spot fecal --

Spot sample 13%

Timed voidings --

True 24 hour 0% (13 records)

The Timed Voidings kit type was only associated with Special analyses. Spot fecal collections were 

not associated with any of the Routine sampling records. 

The analysis type codes seen in the post-1991 in vitro data are shown in Table 5-23. The PHW 

analysis type was only used for fecal samples, though not all fecal samples were counted by PHW. 

Most were counted by RAS. TIMS analysis is only used for plutonium analyses. 

Table 5-23. Analysis type codes for post-1991 in vitro records.

Code Analysis type

LS Liquid scintillation counting (tritium only)

PHW Phoswich detector

RAS Radiometric alpha spectrometry

RASLC Radiometric alpha spectrometry (unknown variant)

RASRC Radiometric alpha spectrometry (unknown variant)

RASSP Radiometric alpha spectrometry (unknown variant)

TIMS Thermal ionization mass spectrometry

5.3.1

The post-1991 in vitro data table in the ORAU Team’s database contains 28,246 records for tritium 

analyses. 26,667 (94%) of these were routine collections over the period 6/17/1991 to 2/9/2009. 16

of the tritium records were from prompt action collections over a three day span in August of 1996. 

The remaining 1,563 (6%) were special collections over the period 7/1/1991 to 1/8/2009. All tritium 

records show a spot sample collection protocol and analysis by liquid scintillation counting (analysis 

type code LS). 

Post-1991 In Vitro Data for Tritium

All but two of the 26,667 routine urinalysis records for tritium show a non-null result. All of the non-null 

results are reported in terms of excretion, i.e. none are on a per sample or per aliquot basis. Most of 

the results are reported in units of μCi per mL. 2 are reported in μCi per gram and 37 do not have 

units. 2,289 of the results are negative and 2,993 are zero. 

16,324 (61%) of the routine tritium urinalysis records have a MDC reported, though 5 of these show a 

MDC of zero. The units for the MDC values are primarily μCi/L. 32 records give a MDC value in 

pCi/L and 2 are in μCi/gram. Records that have a MDC reported include those where the results are 

negative or zero. The units for the MDC can sometimes differ from that for the corresponding result. 

5.3.2

The post-1991 in vitro data table contains 69 records for 210Po urinalyses. These samples were 

collected over a date range of 6/13/2007 to 10/3/2008. Two of them were denoted routine samples 

and the rest were special collections. The two routine samples were simulated 24 hour urine 

Post-1991 In Vitro Data for Polonium
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 24 of 37

samples. Of the 67 special collections, 2 were simulated 24 hour samples and the rest were 500 mL 

samples. 

A non-null result is reported for all of the 210Po samples. All of the results are on a per aliquot basis. 

There is one negative result, and no zero results. All results have a corresponding MDC given in 

pCi/aliquot. Sample volumes are given for all results, in grams. 

5.3.3

The post-1991 in vitro data table contains 13 records for 228Th, 13 records for 229Th, and 4 records for 

232Th. These 30 records correspond to 13 urinalysis samples: 9 analyzed for 228Th and 229Th only, 

and 4 analyzed for all three thorium isotopes. The analyses for 228Th and 229Th only occurred 

between 1/27/2005 and 1/23/2008. The analyses for all three isotopes occurred in January (3 

samples) and May (1 sample) of 2008. All analyses were by RAS. All 13 samples were special 

collections. Twelve (12) were simulated 24 hour samples and the other was a 500 mL sample. 

Results are reported for all 30 records in pCi per aliquot. All 30 records report MDCs, also in pCi per 

aliquot, and sample size in grams. 

Post-1991 In Vitro Data for Thorium

5.3.4

The post-1991 in vitro data table contains 52,899 records for uranium analyses, i.e., analyses for 234U, 

235U, or 238U. These records represent 17,633 samples, as each sample was analyzed for the three 

uranium isotopes. Overall the uranium samples cover a date range of 7/1/1991 to 1/21/2009. Table 

5-24 shows a summary of the post-1991 uranium records. 

Post-1991 In Vitro Data for Uranium

Table 5-24. Summary for uranium records in the post-1991 in vitro data.

Schedule type (no. records) Kit type (no. records) Collection date range

Prompt action (42) 500 mL sample (24) 10/5/1994–10/29/1998

Spot fecal (18) 3/7/2005–3/10/2005

Special (1,731) 500 mL sample (1,716) 8/2/1991–5/26/2008

Simulated 24 hour (15) 1/27/2005–2/1/2005

Routine (51,126) 500 mL sample (51,126) 7/1/1991–1/21/2009

The analysis type for all but 9 of the uranium records (3 samples) was RAS. The other 9 records 

showed an analysis type of RASSP. These 3 samples were special collections of 500 mL samples 

collected on 12/17/2007 and 12/18/2007. 

All but three of the 51,126 routine sample records (representing 17,042 uranium urinalyses) have a 

non-null result in the database. Thus, a result is given for all but 1 of the 17,042 samples. Results 

are reported for each of the three result types, as shown in Table 5-25.

Table 5-25. Non-null results for routine uranium analyses in the post-1991 in vitro data.

Result type No. non-null records

No. records less 

than zero No. records = zero

Per aliquot 15,264 

(5,088 samples) 1,792 459

Per sample 306 

(102 samples) 34 12

Excretion basis (pCi/L) 35,553 

(11,851 samples) 7,494 1,942

MDC values are given for 10,341 (29%) of the 35,553 non-null routine sample results reported in 

terms of excretion (pCi/L). The units for these are primarily in pCi/aliquot (48%) and pCi/sample 

(50%). Less than 2% are in consistent units with the excretion result. All of the per aliquot and per 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 25 of 37

sample results have a MDC reported. All of these are in consistent units, though the MDC for 3 of the 

per aliquot results is zero. 

Sample volumes are given for all of the per aliquot and per sample results, and for all but 3 of the 

excretion results. For the per aliquot and per sample results the sample volumes are given in grams 

or mL. For the excretion results they are given in grams or liters. 

5.3.5

There are 4 individual analytes in the post-1991 in vitro data for plutonium: 238Pu, 239Pu, 240Pu, and 

239Pu+240Pu. Overall, the post-1991 in vitro data table contains a total of 160,859 records for 

plutonium analyses covering a range of sample collection dates from 12/29/1973 to 1/30/2009. 80% 

of the plutonium records were routine analyses, 19% were special, and 2% were prompt action. 

Post-1991 In Vitro Data for Plutonium

Plutonium analyses account for two thirds of the post-1991 in vitro bioassay records. This is 

misleading, however, as a single plutonium sample can have up to 9 associated records (results). For 

a given plutonium sample, results may be reported reflecting different bases (e.g. excretion and per 

sample bases), different analysis techniques, and additional analytes; depending on the results from 

the initial analysis. Thus, the 160,859 plutonium records in the post-1991 in vitro dataset represent 

39,181 individual samples. Table 5-26 shows the distribution of plutonium records associated with 

individual plutonium samples. Each plutonium sample has at least two associated records since at a 

minimum each one is assayed for 238Pu and 239Pu. These two results become four when they are 

reported in terms of both activity per sample and on an excretion rate basis. Additional results are 

created for the same sample if a follow-up TIMS analysis is performed, which allows 239Pu and 240Pu 

to be differentiated. Results for these additional analytes may also be reported on both a per sample 

and excretion rate basis. 

Table 5-26. Distribution of plutonium 

records per sample in the post-1991 

in vitro data.

No. plutonium 

records per sample

Number of 

samples

2 14,681

3 1

4 13,233

5 4,174

6 95

7 2,855

8 141

9 4,001

71% of the plutonium analyses were performed via RAS. These include a small number of records 

analyzed via the RASLC (16 records) and RASRC (12 records) analysis types. A small number (172

out of 160,859) of analyses were performed using a phoswich detector (analysis type PHW). These 

were all fecal analyses, and each has a corresponding RAS count (i.e. there is a PHW count and a 

RAS count for each fecal analysis). The remainder (29%) were analyzed via TIMS, which LANL 

began using in late 1996. TIMS analysis allows 239Pu and 240Pu activity to be determined 

independently. TIMS analysis can be associated with all plutonium analytes except 238Pu. All 

239Pu+240Pu and 240Pu results are via TIMS analysis. 

5.3.5.1 Post-1991 In Vitro Data for 238Pu

The post-1991 in vitro data table contains 57,252 records for 238Pu analyses. These are summarized 

in Table 5-27.
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 26 of 37

Table 5-27. Summary for 238Pu records in the post-1991 in vitro data.

Collection 

requirement

Collection protocol 

(no. records)

Collection 

date range

Analysis types 

(no. records)

Prompt action

(1,148 records)

Simulated 24 hour (1,010) 2/12/1992–11/23/2008 RAS (935), PHW (73), RASLC (1), 

RASRC (1)

Spot fecal (43) 8/8/1989–3/10/2005 RAS (39), PHW (4)

True 24 hour (95) 1/21/1993–1/24/2007 RAS (88), PHW (7)

Special

(10,587 records)

Simulated 24 hour (10,426) 7/1/1991–1/30/2009 RAS (10,417), RASLC (6), RASRC 

(3)

Spot fecal (32) 12/29/1973–6/2/2006 RAS (30), PHW (2)

Timed voidings (23) 4/1/1992–4/3/2000 RAS (23)

True 24 hour (106) 9/16/1991–2/11/2008 RAS (106)

Routine

(45,517 records)

Simulated 24 hour (45,514) 4/8/1991–1/12/2009 RAS (45,511), RASLC (1), RASRC 

(2)

True 24 hour (3) 5/28/2003–6/22/2005 RAS (3)

All but 35 of the 45,517 routine urinalysis records for 238Pu have a non-null result in the database. 

Results are reported for two of the three result types, as shown in Table 5-28. There are no routine 

analysis results for 238Pu reported on a per aliquot basis. 

Table 5-28. Non-null results for routine 238Pu analyses in the post-1991 in vitro data.

Result type

No. non-null 

records

No. records

less than zero No. records = zero

Per aliquot 0 n/a n/a

Per sample 21,572 9,997 965

Excretion basis (pCi/24 hrs) 23,910 11,429 1,888

Sample volumes are reported for 60% of the non-null excretion results and for all but 107 of the per 

sample results. All sample volumes are given in grams. 61% of the excretion results have a MDC 

reported. Two of these MDC values are zero and 10 are negative. All are in units of pCi per sample. 

For the per sample results, all but 2 have a MDC reported. Two of these MDC values are zero and 16 

are negative. The units are also pCi per sample. 

5.3.5.2 Post-1991 In Vitro Data for 239Pu

The post-1991 in vitro data table contains 77,603 records for 239Pu analyses. These are summarized 

in Table 5-29.

Table 5-29. Summary for 239Pu records in the post-1991 in vitro data.

Collection 

requirement

Collection protocol 

(no. records) Collection date range

Analysis types 

(no. records)

Prompt action

(1,290 records)

Simulated 24 hour (1,102) 2/12/1992–11/23/2008 RAS (935), TIMS (92), PHW 

(73), RASLC (1), RASRC (1)

Spot fecal (46) 8/8/1989–3/10/2005 RAS (39), PHW (4), TIMS (3)

True 24 hour (142) 1/21/1993–1/24/2007 RAS (88), TIMS (47), PHW (7)

Special

(14,536 records)

Simulated 24 hour (14,318) 7/1/1991–1/30/2009 RAS (10,417), TIMS (3,892), 

RASLC (6), RASRC (3)

Spot fecal (32) 12/29/1973–6/2/2006 RAS (30), PHW (2)

Timed voidings (42) 4/1/1992–4/3/2000 RAS (23), TIMS (19)

True 24 hour (144) 9/16/1991–2/11/2008 RAS (106), TIMS (38)

Routine

(61,777 records)

Simulated 24 hour (61,771) 4/8/1991–1/12/2009 RAS (45,511), TIMS (16,257), 

RASRC (2), RASLC (1)

True 24 hour (6) 5/28/2003–6/22/2005 RAS (3), TIMS (3)
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 27 of 37

All but 143 of the 61,777 routine urinalysis records for 239Pu have a non-null result in the database. 

Results are reported for two of the three result types, as shown in Table 5-30. There are no routine 

analysis results for 239

Pu reported on a per aliquot basis. 30 of the excretion results are reported in 

units of pCi per sample. The remainder are in pCi per 24 hours. 

Table 5-30. Non-null results for routine 239Pu analyses in the post-1991 in vitro data.

Result type No. non-null records

No. records less 

than zero No. records = zero

Per aliquot 0 n/a n/a

Per sample 32,245 13,098 1,006

Excretion basis 29,389 11,832 2,283

Sample volumes are reported for 51% of the non-null excretion results and for 68% of the per sample 

results. All sample volumes are given in grams. 49% of the excretion results have a MDC reported. 

Two of these MDC values are zero and 10 are negative. All are in units of pCi per sample. For the 

per sample results, 67% have a MDC reported. Two of these MDC values are zero and 16 are 

negative. The units are also pCi per sample. 

5.3.5.3 Post-1991 In Vitro Data for 240Pu

The post-1991 in vitro data table contains 12,487 records for 240Pu analyses. These are summarized 

in Table 5-31. The analysis type for all 240Pu records is TIMS. 

Table 5-31. Summary for 240Pu records in the post-1991 in vitro data.

Collection 

requirement

Collection protocol 

(no. records) Collection date range

Prompt action

(79 records)

Simulated 24 hour (57) 7/23/1998–11/23/2008

Spot fecal (1) 3/6/1998

True 24 hour (21) 6/11/1997–3/27/2001

Special

(2,307 records)

Simulated 24 hour (2,267) 2/13/1997–1/30/2009

Timed voidings (15) 5/5/1997–6/26/1997

True 24 hour (25) 1/26/1997–2/11/2008

Routine

(10,101 records)

Simulated 24 hour (10,100) 2/10/1997–12/24/2008

True 24 hour (1) 6/9/2004

4,905 (49%) of the 10,101 routine urinalysis records for 240Pu have a non-null result in the database. 

Results are reported for two of the three result types, as shown in Table 5-32. There are no routine 

analysis results for 240Pu reported on a per aliquot basis. All of the 703 results in terms of excretion 

have a corresponding result on a per sample basis. 

Table 5-32. Non-null results for routine 240Pu analyses in the post-1991 in vitro

data.

Result type

No. non-null 

records

No. records

less than zero No. records = zero

Per aliquot 0 n/a n/a

Per sample 4,202 1,659 1

Excretion basis (pCi/24 hrs) 703 148 1

Sample volumes, in grams, are reported for 33 records for both the per sample results and the 

excretion results. MDC values are not provided for TIMS analyses. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 28 of 37

5.3.5.4 Post-1991 In Vitro Data for 239Pu+240Pu

The post-1991 in vitro data table contains 13,517 records for 239Pu+240Pu analyses. These are 

summarized in Table 5-33. The analysis type for all 239Pu+240Pu records is TIMS. 

Table 5-33. Summary for 239Pu+240Pu records in the post-1991 in vitro data.

Collection 

requirement

Collection protocol 

(no. records) Collection date range

Prompt action

(99 records)

Simulated 24 hour (53) 12/6/1996–11/23/2008

Spot fecal (3) 3/6/1998, 3/10/1998, 3/11/1998

True 24 hour (43) 12/20/1996–1/20/2007

Special

(2,596 records)

Simulated 24 hour (2,539) 12/22/1996–1/30/2009

Timed voidings (19) 5/5/1997–6/27/1997

True 24 hour (38) 12/20/1996–2/11/2008

Routine

(10,822 records)

Simulated 24 hour (10,819) 2/6/1997–12/24/2008

True 24 hour (3) 5/28/2003, 6/9/2004, 6/22/2005

10,714 (99%) of the 10,822 routine urinalysis records for 239Pu+240Pu have a non-null result in the 

database. All of the results are reported on a per sample basis. 2,485 of the results are negative and 

4 are zero. Sample volume, in grams, is provided for 605 (6%) of the results. MDCs are not provided 

for TIMS analyses. 

5.3.6

The post-1991 in vitro data table contains 2,657 records for 241Am analyses. These are summarized 

in Table 5-34. 

Post-1991 In Vitro Data for 241Am

Table 5-34. Summary for 241Am records in the post-1991 in vitro data.

Collection 

requirement

Collection protocol 

(no. records) Collection date range

Analysis types 

(no. records)

Prompt action

(228 records)

Simulated 24 hour (77) 3/30/1994–11/29/2008 RAS (60), PHW (17)

Spot fecal (151) 8/8/1989–3/10/2005 RAS (93), PHW (58)

Special (436 records)

Simulated 24 hour (417) 5/26/1991–12/14/2008 RAS (417)

Spot fecal (18) 12/29/1973–8/3/2005 RAS (18)

True 24 hour (1) 8/20/1997 RAS (1)

Routine (1,993 records) Simulated 24 hour (1,993) 5/9/1991–1/19/2009 RAS (1,993)

1,921 (96%) of the 1,993 routine urinalysis records for 241Am have a non-null result in the database. 

Results are reported for all three result types, as shown in Table 5-35. For the results given in terms 

of excretion, 18 are reported in units of pCi per sample. The rest are in pCi per 24 hours. 

Table 5-35. Non-null results for routine 241Am analyses in the post-1991 in 

vitro data.

Result type

No. non-null 

records

No. records less 

than zero No. records = zero

Per aliquot 882 521 2

Per sample 290 75 1

Excretion basis 749 346 3

Sample volumes are reported for 93% of the non-null per aliquot results, for 100% of the per sample 

results, and for 88% of the excretion results. Sample volumes are given primarily in grams, with some 

values given in mL. All of the per aliquot and per sample results have MDCs. MDCs are reported for 

88% of the excretion results, in units of either pCi per aliquot (53%) or pCi per sample (47%). None of 

the MDC values are zero or negative. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 29 of 37

6.0

The archived TUPo data had been entered from laboratory notebooks, which were the formal record 

for personnel bioassay results before about 1980. Laboratory notebooks were issued to individuals 

and were often used as journals rather than being dedicated to a specific process or procedure. 

Consequently, the original bioassay data are distributed across over 100 notebooks, where an 

individual notebook might contain several thousand records or only a few depending on how it was 

used by the assignee.

VALIDATION OF TUPO DATA AGAINST LABORATORY NOTEBOOKS

Many of the VAX data files included fields that identified the laboratory notebooks from which the 

bioassay data originated. A cursory comparison between the VAX data files and several of the 

notebooks suggested a rather high rate of disagreement (~20%). This prompted an effort to validate 

a larger fraction of the TUPo data to gain a better understanding of its reliability.

From the VAX data files, 120 laboratory notebooks were identified as containing TUPo data. Ninety of 

these were retrieved, which represented nearly 90% of the TUPo records. 

In reviewing the data, priority was placed on validating positive results and high values in particular. 

However, the review also included a considerable fraction of results for which no activity (i.e., 0.00) 

was reported. Errors were found in the reporting of sample results, sample dates, and notebook and 

page references. Ninety-six records were added to the database that had been omitted from the VAX 

files. 

Eleven percent (16,692 of 147,690) of the TUPo records were validated. Data comments were 

entered for 4,882 records, and 1,330 records were corrected in some way. The majority (83%) of the 

corrections were changes to notebook or page references. Beyond corrections, data comments were 

used to document information such as unresolved questions about a record or errors that were 

apparent but could not be corrected, such as an incorrect notebook reference where the correct 

notebook number could not be determined. Table 6-1 summarizes the validation results and the 

types of errors found. 

Table 6-1. Data validation summary for TUPo records.

Total 

records Validated records

Records 

added

Corrected fields

Data 

comments

Sample 

results

Sample 

date

Notebook

reference

Page

reference

147,690 16,692 102 209 12 578 531 4,882

Data validation issues specific to tritium, uranium, and polonium records are discussed in Sections 6.1 

through 6.3. Section 6.4 describes the review of the laboratory notebooks for bioassay data for other 

radionuclides. This was performed concurrently with the validation of the TUPo data. 

6.1 VALIDATION OF TRITIUM RECORDS

From the VAX files, 27 notebooks were identified as containing tritium bioassay data. Fifteen of these 

were obtained, which represented 35,267 tritium records or 70% of the total. A sixteenth notebook 

(number S4819) was retrieved, but it did not contain tritium bioassay information. There was a 

significant period (1958 to 1968) for which notebooks were either not found or could not be identified.

Therefore, none of the tritium bioassay data from this period have been validated. The fifteen 

notebooks that were used in the validation of tritium records from the VAX files are listed in Table 6-2. 

Approximately 10% (5,150 out of 50,141) of the tritium records were validated. These totals include 

34 records added to the database that were present in the notebooks but not in the VAX files. Data 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 30 of 37

Table 6-2. Laboratory notebooks used to validate in vitro analytical results for tritium.

Notebook 

number

Units 

used

Start 

date

End 

date

No of 

records

Percent 

validated Comments

3605 μCi/L 06/23/50 09/11/52 1,582 18 Contains earliest tritium data and calibration 

details on pages 1–8 from which some 

uncertainty information might be derived.

5481 μCi/L 09/11/52 09/19/54 5,148 6.6

6813 μCi/L 09/17/54 12/30/57 5,517 6.8 Contains memorandum in front that might 

help in determining uncertainty from 4/20/50 

to 01/66.

15722 μCi/L 01/03/69 01/24/72 3,495 4.6 On page 16 there is a change in reporting. 

Values reported as "<1" are now reported well 

below this value. The VAX files report results 

1% to 10% higher than reported in this 

notebook.

17487 μCi/L 01/25/72 11/08/74 2,283 7.4 Page 1 has some statements on accuracy 

and precision.

18519 μCi/L 11/07/74 08/27/76 1,772 19.5

20096 μCi/L 08/25/76 09/27/78 1,812 6.6

21536 μCi/L 09/26/78 04/02/80 2,069 7

22311 μCi/L 03/28/80 07/14/81 1,778 8.3

25285 μCi/L 10/29/82 03/05/85 1,353 10

24959 μCi/L 02/21/84 05/15/84 1,774 5.1

24906 μCi/L 05/28/85 12/10/87 2,496 8

R6066 μCi/L 12/11/86 01/28/88 1,933 8

R6074 μCi/L 01/19/88 07/07/89 2,232 6.2

R7709 μCi/L 12/21/90 06/24/91 23 100

comments were made for 3,564 records, and corrections were applied to 110 records. Validation of 

the tritium data is summarized in Table 6-3. 

Table 6-3. Tritium data validation summary.

Total 

records

Validated 

records

Records 

added

Corrected fields

Data 

comments

Sample 

results

Sample 

date

Notebook

reference

Page

reference

50,141 5,150 34 45 2 12 51 3,564

In comparing the data in the notebooks with that in the VAX files, it was evident that the bioassay 

results from notebook 15722 had been adjusted in some manner. In general, the values from the 

VAX files were 1% to 10% higher than those documented in the notebook. There were approximately 

3,460 affected records. This discrepancy was indicated in the data comment field. 

6.2 VALIDATION OF URANIUM RECORDS

From the VAX files, 83 notebooks were identified as possibly containing in vitro bioassay data for 

uranium. Sixty-four of these were retrieved, and 58 were determined to contain uranium bioassay 

data. The 58 notebooks contained 85,857 uranium records, representing 93% of the total. The 

notebooks are listed in Table 6-4. 

Table 6-4. Laboratory notebooks used to validate in vitro analytical results for uranium.

a

Notebook

Record type and 

units

Start 

date

End 

date

No. of 

records

Percent 

validated Comments

11246 U-235 (dpm/L) 08/16/63 04/15/65 4,353 2.8

13764 U-235 (dpm/L) 04/23/65 04/17/67 4,571 3.4

13833 U-235 (dpm/L) 04/17/67 11/18/68 3,579 3.5
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 31 of 37

Notebook

Record type and 

units

Start 

date

End 

date

No. of 

records

Percent 

validated Comments

15721 U-235 (dpm/L and 

counts per 50 

minutes)

11/22/68 09/08/70 3,683 3.5 Beginning with about p. 50, the results are 

reported in counts per 50 minutes. These 

were adjusted for efficiency, sample size, 

and count time to get dpm/L, the reporting 

units for the computer data files.

16283 U-235 (μg/L) 09/14/70 05/05/72 1,491 These results had been adjusted in some 

undetermined way between the notebook 

values and those in the VAX files. Since it 

was not clear how the values had been 

adjusted, validation of the data in this 

notebook was impracticable.

17494 U-235 (dpm/L) 05/19/72 10/19/73 1,706 6 These results were adjusted for efficiency, 

sample size, and count time to get dpm/L, 

the reporting units for the computer data 

files. (Size = 75 ml, Count time = 50 min, 

Recovery = 0.7, and Efficiency = 0.4)

18511 U-235 (dpm/L) 11/02/73 07/04/75 1,907 2 These results were adjusted for efficiency, 

sample size, and count time to get dpm/L, 

the reporting units for the computer data 

files. (Size = 75 ml, Count time = 50 min, 

Recovery = varies, and Efficiency = 0.4)

6654 U-235 678 Contains air samples, blood samples for 

toxic exposures, and U-235.

8949 U-235 (dpm/L) 07/16/62 08/16/63 1,714 4.2

9463 U-235 (dpm/L) 09/21/58 07/16/62 2,341 3.8

S2179 U-235 (dpm/L until 

1/77, then pCi/L)

07/18/75 09/13/77 2,128 4.9

S3436 U-235 (pCi/L) and 

U-238 (μg/L)

10/30/81 02/05/82 1,418 6.7

19947 U-235 (pCi/L) and 

U-238 (μg/L)

09/12/77 03/12/79 3,443 7.5

21533 U-235 (pCi/L) and 

U-238 (μg/L)

09/21/79 01/25/80 1,891 10

22314 U-235 (pCi/L) and 

U-238 (μg/L)

06/02/80 09/19/80 1,555 5.6

22316 U-235 (pCi/L) and 

U-238 (μg/L)

10/06/81 01/23/81 1,560 3

22318 U-235 (pCi/L) and 

U-238 (μg/L)

02/11/80 05/16/80 1,220 8.8

22319 U-235 (pCi/L) and 

U-238 (μg/L)

01/25/80 02/16/81 19 100

23145 U-235 (pCi/L) and 

U 238 (μg/L)

06/12/81 10/16/81 1,577 20

23148 U-235 (pCi/L) and 

U 238 (μg/L)

02/06/81 06/12/81 1,812 4.7

24082 U-235 (pCi/L) and 

U 238 (μg/L)

06/25/82 12/24/82 708 14

24907 U-235 (pCi/L) and 

U 238 (μg/L)

11/13/84 06/24/85 812 20

24912 U-235 (pCi/L) and 

U 238 (μg/L)

03/12/84 10/29/84 948 13

24951 U-235 (pCi/L) and 

U 238 (μg/L)

01/07/83 07/08/83 822 31

24955 U-235 (pCi/L) and 

U 238 (μg/L)

07/14/83 03/05/84 966 8.2

A1185 U-235 (pCi/L) and 

U 238 (μg/L)

06/24/85 02/18/86 797 38

R6063 U-235 (pCi/L) and 

U 238 (μg/L)

06/08/88 06/22/90 1,010 26

R6070 U-235 (pCi/L) and 

U 238 (μg/L)

09/29/86 06/08/87 786 17
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 32 of 37

Notebook

Record type and 

units

Start 

date

End 

date

No. of 

records

Percent 

validated Comments

R6574 U-235 (pCi/L) and 

U 238 (μg/L)

06/22/87 04/18/88 772 21.5

S2517 U-235 (pCi/L) and 

U 238 (μg/L)

03/23/79 09/07/79 2,820 2.4

S4412 U-235 (pCi/L) and 

U 238 (μg/L)

01/08/82 06/11/82 1,396 21

S9787 U-235 (pCi/L) and 

U 238 (μg/L)

03/03/86 09/15/86 656 38

17493 U-238 (μg/L) 02/01/77 10/31/77 20 100

18510 U-238 (μg/L) 11/09/73 10/19/76 1,682 These results had been adjusted in some 

undetermined way between the notebook 

values and those in the VAX files. Since it 

was not clear how the values had been 

adjusted, validation of the data in this 

notebook was impracticable.

3064 U-238 (μg/L) 11/18/49 04/22/50 248 68

3351 U-238 (μg/L) 03/24/50 09/09/50 400 54.5

3683 U-238 (μg/L) 07/29/50 09/05/59 714 16

3802 U-238 (μg/L) 08/16/59 01/06/51 574 56

3832 U-238 (μg/L) 09/25/50 02/06/52 118 23

4992 U-238 (μg/L) 01/14/52 02/16/53 953 16

5843 U-238 (μg/L) 01/19/53 06/05/53 911 13

6438 U-238 (μg/L) 10/13/53 04/07/54 1,101 7

6744 U-238 (μg/L) 04/12/53 08/19/54 1,181 8.4

6982 U-238 (μg/L) 08/20/54 01/10/55 1,136 5.9

R108 U-238 (μg/L) 01/07/55 02/17/56 2,473 4

S1068 U-238 (μg/L) 08/20/64 06/17/66 1,926 7

S1199 U-238 (μg/L) 02/02/76 05/30/78 2,276 5.4

S1214 U-238 (μg/L) 1,162

S1228 U-238 (μg/L) 07/15/66 11/13/67 1,735 4.6

S1474 U-238 (μg/L) 03/14/69 08//28/70 1,273 4.6

S1653 U-238 (μg/L) 09/16/70 12/02/70 1,084 6.7

S1790 U-238 (μg/L) 12/03/71 10/12/73 1,673 These results had been adjusted in some 

undetermined way between the notebook 

values and those in the VAX files. Since it 

was not clear how the values had been 

adjusted, validation of the data in this 

notebook was impracticable.

S2521 U-238 (μg/L) 06/19/78 02/22/80 569 44

S447 U-238 (μg/L) 03/15/57 08/14/58 1,525 3.6

S615 U-238 (μg/L) 08/22/58 02/05/60 1,675 11

S727 U-238 (μg/L) 02/18/60 03/17/61 1,062 3

S792 U-238 (μg/L) 04/07/61 08/03/62 1,392 8

S901 U-238 (μg/L) 08/15/62 08/07/64 1,855 4

a. LANL refers to enriched uranium as “U-235” and other forms, including normal uranium, as “U-238.” The use of “U-235” 

and “U-238” in this context does not imply isotope-specific analyses. 

There were 17 “

235U” and 9 “238U” records in the notebooks that did not appear in the VAX files. 

These were added to the database. In addition, six “

238U” records were found in the file 

“sPOL4765.dat” that had been cataloged as containing only polonium data. The fact that these six 

records were uranium rather than polonium assay results was verified through examination of the 

laboratory notebooks. These six 238U records were also added to the database.

Corrections were made to 122 235U records and comments were made for 76. For 238U, corrections 

were applied to 78 records and comments were made for 803. Validation of the uranium data is 

summarized in Table 6-5.
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 33 of 37

Table 6-5. Uranium data validation summary.

Nuclide Records

Validated

records

Records 

added

Corrected fields

Data 

comments

Sample 

results

Sample 

date

Notebook

reference

Page

reference

U-235 43,668 4,436 17 32 0 1 79 76

U-238 48,169 4,841 15 60 10 2 6 803

Total 91,837 9,277 32 92 10 3 85 879

6.3 VALIDATION OF POLONIUM RECORDS

The VAX files identified 13 notebooks with polonium bioassay data. Nine of these were retrieved of 

which three were determined to contain bioassay data for polonium. The three notebooks contained 

5,682 polonium records, which represented 99% of the total. The retrieved notebooks are listed in 

Table 6-6.

Table 6-6. Laboratory notebooks used to validate in vitro analytical results for polonium.

Notebook Start date End date Units codes used Number of records Percent validated

1794A 03/11/47 01/09/53 CM: cpm/24 hr

DM: dpm/L

2,957 33

3174 01/09/53 03/24/65 DM: dpm/L

NCI: nCi/g fecal

1,726 66

H5100 12/31/51 12/15/53 CM: cpm/24 hr

DM: dpm/L

986 10

Approximately 39% of the polonium records (2,245 of 5,712) were validated. There were 36 records 

that were added to the database that were present in the notebooks but not in the VAX files. 

Corrections and comments were made for 1,020 and 439 records, respectively. All but 72 of the 

1,020 corrections were for notebook or page reference issues. Validation of the polonium data is 

summarized in Table 6-7. 

Table 6-7. Polonium data validation summary.

Total 

records

Validated 

records

Records 

added

Corrected fields

Data 

comments

Sample 

results

Sample 

date

Notebook

reference

Page

reference

5,712 2,245 36 72 0 553 395 439

6.4 REVIEW OF LABORATORY NOTEBOOKS FOR IN VITRO MONITORING DATA FOR 

OTHER RADIONUCLIDES

In the process of validating the TUPo data against laboratory notebooks, around 100 to 200 bioassay 

records were identified where LANL had performed special analyses for other radionuclides, such as 

90Sr. These records were not included in the bioassay database because they were not part of 

LANL’s formal bioassay program and there was too much uncertainty about their origin or reliability. 

Review of the laboratory notebooks did not identify any bioassay data for LANL employees who 

worked with radioactive lanthanum (RaLa). Workers who handled RaLa or its waste streams had the 

potential for intakes of 90Sr, that was present as a contaminant. A small number of gross beta results 

for 90Sr were identified, but it did not appear there was ever a formal bioassay program for 90Sr. 

Review of the notebooks also identified isolated instances of in vitro bioassay for mixed fission 

products, but as in the 90Sr cases these data were not associated with a formal bioassay program. 

There are cases where in vivo counting was performed for mixed fission products. 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 34 of 37

7.0

All information requiring identification was addressed via references integrated into the reference 

section of this document.

ATTRIBUTIONS AND ANNOTATIONS
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 35 of 37

REFERENCES

Clark, J. M., 2005, History of LANL’s Bioassay Program from Inception to 1993, LA-UR-05-1942, Los 

Alamos National Laboratory, Los Alamos, New Mexico, April. [SRDB Ref ID: 17157]

Gautier, M. A., 1983, Manual of Analytical Methods for Radiobioassay, LA-9763-M, Los Alamos 

National Laboratory, Los Alamos, New Mexico, July. [SRDB Ref ID: 12890]

Ide, H. M., W. D. Moss, M. M. Minor, and E. E. Campbell, 1979, “Analysis of Uranium in Urine by 

Delayed Neutrons”, Health Physics, volume 37, number 3 (September), pp. 405–408.

LANL (Los Alamos National Laboratory), 1978, Analytical Methods Bioanalytical and Chemical 

Section Industrial Hygiene Health Division, Los Alamos National Laboratory, Los Alamos, New 

Mexico, September.

LANL (Los Alamos National Laboratory), 1983, Health and Environmental Chemistry, R250-1, Los 

Alamos National Laboratory, Los Alamos, New Mexico, July (revised May 1991).

Lawrence, J. N. P., 1958, Estimation of Whole Body Dose (rem) from Tritium in Body Water, LA-2163, 

University of California, Los Alamos Scientific Laboratory, Los Alamos, New Mexico, February

3. [SRDB Ref ID: 959]

Lawrence, J. N. P., 1987, “Tritium Bioassay Program Overview,” memorandum to file, Los Alamos 

National Laboratory, Los Alamos, New Mexico, October. [SRDB Ref ID: 71601]

Lawrence, J. N. P., 1991, “Archival Storage of Internal Dosimetry Records,” memorandum, HSE-1-91-

250, Los Alamos National Laboratory, Los Alamos, New Mexico, May 1. [SRDB Ref ID: 

71602]

McClelland, J., E. E. Campbell, B. C. Eutsler, B. Head, V. E. Johnson, M. F. Milligan, W. D. Moss, M. 

C. Robbins, and C. P. Skillern, 1955, Analytical Procedures of the Industrial Hygiene Group, 

LA-1858, Los Alamos National Laboratory, Los Alamos, New Mexico, August. [SRDB Ref ID: 

13981]
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 36 of 37

ATTACHMENT A

URANIUM NEUTRON ACTIVATION ANALYSIS

Page 1 of 2

Introduction

This attachment presents information about LANL’s UNAA urinalysis program. UNAA was one of the 

uranium analysis types encountered during the development of the LANL bioassay database. Use of 

UNAA was implemented in the late 1970s and ceased in 1990. (There is a single result in the 

database from 1962 that shows UNAA as the analysis type, but this is thought to be a data entry 

error.) UNAA involved irradiating a urine specimen in a thermal neutron beam and subsequently 

counting it for delayed neutrons from fission product precursors. 

UNAA Bioassay Program

As of 1978 UNAA was an element of LANL’s routine bioassay program. LANL’s experience with the 

UNAA method had shown that samples giving a neutron count greater than the detection limit of the 

neutron counting system (at 99% confidence) also showed positive uranium concentrations when 

analyzed by wet chemistry. The method therefore provided a way to screen a large number of 

samples, with subsequent wet chemistry analyses performed as needed to confirm high values or 

determine the 235U/238U ratio (Ide et al. 1979). 

Personnel were entered into the UNAA bioassay program based on information from their Health 

Physics Checklist (HPC). The HPC documented if an individual was going to be working with 235U 

(enriched uranium), 238U (depleted or normal uranium), or both. 

As of 1978 LANL’s action levels (which they called “concern levels,”) for uranium in urine were 

10 μg/L for depleted and natural uranium, and 4.5 pCi/L for enriched uranium (Ide et al. 1979). 

UNAA Calibration and Detection Limits

The counting method was calibrated by sending urine samples spiked with known quantities of 

uranium through the analysis process. Urine standards were prepared using depleted uranium (0.18 

atom percent 235U), normal uranium (0.72 atom percent 235U), and enriched uranium (93.16 atom 

percent 235U). Standards were prepared over a range of uranium concentrations for each enrichment: 

0 to 2,500μg/L for depleted uranium, 0 to 140 μg/L for normal uranium, and 0 to 1,000 pCi/L for 

enriched uranium (Ide et al. 1979). 

LANL determined that the irradiation of a 25 cm3 urine specimen containing 4.16 μg/L of depleted 

uranium (0.18 atom percent 235U) would give a gross neutron count of 100 counts, which was the 

detection limit of the counting system at 99% confidence. The 100-count detection limit was 

determined from counting statistics, using a background established from a series of urine control 

samples (Ide at al. 1979). The MDCs that corresponded to the 100-count detection limit for the UNAA 

method are given in Table A-1 for depleted, natural, and enriched uranium. 

Table A-1. MDCs for UNAA urinalysis at LANL (Ide et al. 1979).

Uranium enrichment MDC

Depleted uranium (0.18 atom percent 235U) 4.16 μg/L

Normal uranium (0.72 atom percent 235U) 1.04 μg/L

Enriched uranium (93.16 atom percent 235U) 1.5 pCi/L

UNAA Analyses and Reporting Units

Samples were collected from personnel by the LANL industrial hygiene group (H-5 at the time). 

Neutron irradiation and counting took place at the Omega West Reactor facility. Quality control 

samples and blanks were analyzed concurrently with the routine unknown samples to allow 

corrections to be made for changes in background or reactor power (Ide et al. 1979). 
Document No. ORAUT-OTIB-0063 Revision No. 00 Effective Date: 08/24/2009 Page 37 of 37

ATTACHMENT A

URANIUM NEUTRON ACTIVATION ANALYSIS

Page 2 of 2

The UNAA process involved irradiating 25 cm3 urine specimens in a thermal neutron beam for 

60 seconds and then counting them for delayed neutrons for a 55-second interval following a short 

decay period (Ide et al. 1979). The delayed neutron count was equated to uranium concentration 

using an assumed 235U fraction (i.e., enrichment) that reflected an individual’s exposure environment. 

(Delayed neutron assay methods cannot differentiate between fissile species or varying uranium 

enrichments, so one must have prior knowledge or use assumptions to quantify results.)

Results for depleted or normal uranium were denoted as “

238U” and reported in micrograms per liter. 

Results for enriched uranium were denoted as “235U” and reported in picocuries per liter.