NUREG-1640, Vol. 2

Radiological Assessments for

Clearance of Materials from

Nuclear Facilities

Appendices A through E 

U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research

Washington, DC 20555-0001
 

 NUREG-1640, Vol. 2

 

Radiological Assessments for

Clearance of Materials from

Nuclear Facilities

Appendices A through E

Manuscript Completed: May 2004

Date Published: October 2004

Prepared by

R. Anigstein*, H.J. Chmelynski*, D.A. Loomis*,

S.F. Marschke**, J.J. Mauro*, R.H. Olsher*,

W.C. Thurber*, R.A. Meck

*SC&A, Inc.

6858 Old Dominion Drive

Suite 301

McLean, VA 22101

**Gemini Consulting Company

19 River Run Way

Oak Ridge, TN 37830

R.A. Meck, NRC Project Manager

Prepared for

Division of Systems Analysis and Regulatory Effectiveness

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

NRC Job Code Number Y6407

Abstract

iii NUREG-1640

ABSTRACT

This report provides a complete description of calculations and their results estimating potential

annual doses, normalized to a unit concentration, to an individual following the clearance of

specific materials. These materials are scrap iron and steel, copper, aluminum, and concrete

rubble from licensed nuclear facilities. Clearance means the removal of radiological controls by

the licensing authority. The estimated potential doses are calculated probabilistically to account

for a large number of possible variations in each of the 86 scenarios. These scenarios encompass

the full range of realistic situations likely to yield the greatest normalized doses. Each scenario

was analyzed with the 115 radionuclides considered most likely to be associated with materials

from licensed nuclear facilities. The design basis of the analyses is to realistically model current

processes, to identify critical groups on a nuclide-by-nuclide basis, and to enable the conversion

of a dose criterion to a concentration. 

Material for recycle or disposal was evaluated using material flow models and dose assessment

models. Both models are based on probabilistic methods. This resulted in distributions of

nuclide-by-nuclide normalized doses from one year of exposure per mass- or surface-based

concentrations. The means and the 5th, 50th, 90th, and 95th percentiles are reported. These

percentiles can be used to generically evaluate the likelihood that the derived mean concentration

would correspond to a particular dose criterion. Additionally, they can be used to quantify the

confidence that a safety goal is not exceeded.

Contents

v NUREG-1640

CONTENTS

Appendices

A Inventory of Materials from NRC and Agreement State Licensees

B Parameter Values

C External Exposure Dose Coefficients

D Mixing of Cleared Materials

E Ingrowth of Radioactive Progeny
APPENDIX A

INVENTORY OF MATERIALS FROM 

NRC AND AGREEMENT STATE LICENSEES

Appendix A Inventory of Materials

A-iii NUREG-1640

CONTENTS

Page

Appendix A Inventory of Materials from NRC and Agreement State Licensees . . . . . . . . . A-1

A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1

A.1.1 Types of Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-2

A.1.2 Scope of Licensed Community . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-2

A.2 Commercial Nuclear Power Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-3

A.2.1 Decommissioning Policies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-3

A.2.2 Scaling Factors for Commercial Nuclear Power Reactors . . . . . . . . . . . . . . . A-4

A.2.3 Mass of Materials in Reference BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-5

A.2.3.1 General BWR Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-5

A.2.3.2 Ferrous Metals in Reference BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-7

A.2.3.3 Concrete in the Reference BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-10

A.2.3.4 Copper and Aluminum in the Reference BWR . . . . . . . . . . . . . . . . . . . A-12

A.2.3.5 Reference BWR Mass Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-13

A.2.4 Mass of Materials in Reference PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-15

A.2.4.1 General Description of Reference PWR . . . . . . . . . . . . . . . . . . . . . . . . A-15

A.2.4.2 Mass of Systems and Components in Reference PWR . . . . . . . . . . . . . A-17

A.2.4.3 Concrete in Reference PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-19

A.2.4.4 Reference PWR Mass Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-22

A.2.4.4.1 Ferrous Metals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-22

A.2.4.4.2 Copper . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-24

A.2.4.4.3 Aluminum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-24

A.2.5 Materials Inventories of Operating Nuclear Power Plants . . . . . . . . . . . . . . A-25

A.3 NRC Fuel Cycle Facility Licensees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-25

A.3.1 Uranium Mills . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-25

A.3.2 Uranium Hexafluoride Production Facilities . . . . . . . . . . . . . . . . . . . . . . . . . A-26

A.3.2.1 Reference UF6 Production Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-26

A.3.2.2 Inventory Summary - UF6 Production Facilities . . . . . . . . . . . . . . . . . . A-28

A.3.3 Fuel Fabrication Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-29

A.3.3.1 Reference Fuel Fabrication Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-30

A.3.3.2 Inventory Summary – Fuel Fabrication Facilities . . . . . . . . . . . . . . . . . A-30

A.3.4 Uranium Enrichment Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-33

A.3.5 Spent Fuel Storage Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-34

A.3.5.1 Concrete Casks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-36

A.3.5.2 Horizontal Modular Storage (NUHOMS) . . . . . . . . . . . . . . . . . . . . . . . A-38

A.3.5.3 Metal Casks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-40

A.3.5.4 Modular Vault Dry Store . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-42

A.3.5.5 Pool (Wet) Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-43

A.3.5.6 Inventory Summary—Spent Fuel Storage Facilities . . . . . . . . . . . . . . . A-44
Inventory of Materials Appendix A

NUREG-1640 A-iv

Contents (continued)

Page

A.4 Non-Power Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-45

A.4.1 Reference Non-Power Reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-46

A.4.2 Scaling Factors for Non-Power Reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . A-46

A.4.3 Inventory Summary—Non-Power Reactors . . . . . . . . . . . . . . . . . . . . . . . . . A-49

A.5 Non-Fuel-Cycle Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-50

A.6 Estimates of Mass-to-Surface Area Ratios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-51

A.6.1 Ferrous Metals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-51

A.6.1.1 Reinforcing Steel (Rebar) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-51

A.6.1.2 Structural Steel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-52

A.6.1.3 Pipe Hangers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-53

A.6.1.4 Miscellaneous Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-54

A.6.1.5 Mass-to-Surface Ratios of Ferrous Metals . . . . . . . . . . . . . . . . . . . . . . . A-55

A.6.2 Concrete . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-56

A.6.2.1 Concrete in Reference PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-56

A.6.2.2 Concrete in BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-56

A.6.3 Copper . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-56

A.6.4 Aluminum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-57

A.7 Total Mass of Potentially Cleared Materials from Licensed Facilities . . . . . . . . . . A-57

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-60
Appendix A Inventory of Materials

A-v NUREG-1640

Tables

Page

A.1 Nuclear power reactor scaling factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-5

A.2 Estimated quantities of structural materials in the reference BWR facility . . . . . . . . . . A-7

A.3 Summary of ferrous metals in reference BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-8

A.4 Neutron-activated ferrous metal components in reference BWR . . . . . . . . . . . . . . . . . A-9

A.5 Mass of components with activities on internal surfaces in reference BWR . . . . . . . A-11

A.6 MARSSIM classification of rebar and structural steel in reference BWR . . . . . . . . . A-12

A.7 Estimated mass (kg) and total activity (Ci) of aluminum piping in reference BWR . . A-13

A.8 Mass summary for reference BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-13

A.9 Estimates of metals used to construct a 1,000-MWe PWR facility . . . . . . . . . . . . . . . A-15

A.10 Breakdown of materials used in PWR plant structures and reactor systems (t) . . . . . A-16

A.11 Trojan PWR system characterization data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-18

A.12 Expected categories of Trojan systems and components not sampled . . . . . . . . . . . . A-20

A.13 Volume and activity of Trojan structural concrete components . . . . . . . . . . . . . . . . . A-21

A.14 Summary of activity levels of ferrous metals in 1,000-MWe generic PWR . . . . . . . . A-23

A.15 Mass summary for reference PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-24

A.16 Licensed uranium hexafluoride production facilities . . . . . . . . . . . . . . . . . . . . . . . . . A-26

A.17 Mass of steel in equipment of UF6 production facility . . . . . . . . . . . . . . . . . . . . . . . . A-27

A.18 Mass of structural steel in UF6 production facility buildings . . . . . . . . . . . . . . . . . . . A-27

A.19 Activity levels of equipment in UF6 production facility (piping not included) . . . . . . A-28

A.20 Licensed uranium fuel fabrication facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-29

A.21 Mass of steel in fuel fabrication equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-31

A.22 Mass of structural steel in buildings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-31

A.23 Activity levels on equipment in reference fuel fabrication facility . . . . . . . . . . . . . . . A-32

A.24 Scaling factors for uranium fuel fabrication facilities . . . . . . . . . . . . . . . . . . . . . . . . . A-33

A.25 Spent fuel storage system designs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-34

A.26 Licensed dry spent fuel storage facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-35

A.27 Mass of principal VSC-24 concrete cask components . . . . . . . . . . . . . . . . . . . . . . . . A-36

A.28 Dimensions of principal components of VSC-24 concrete cask . . . . . . . . . . . . . . . . . A-37

A.29 Mass of principal NUHOMS components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-39

A.30 Dimensions of principal components of NUHOMS system . . . . . . . . . . . . . . . . . . . . A-40

A.31 Principal CASTOR metal cask components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-41

A.32 Dimensions of principal components of CASTOR metal cask . . . . . . . . . . . . . . . . . . A-41

A.33 Licensed non-power reactors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-47

A.34 Estimated quantities of structural material in reference NPR . . . . . . . . . . . . . . . . . . . A-48

A.35 Waste generated during decommissioning of non-power reactors . . . . . . . . . . . . . . . A-48

A.36 Ferrous metal components used in mass-to-surface ratio analysis . . . . . . . . . . . . . . . A-51

A.37 Reinforcing steel (rebar) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-53

A.38 Typical pipe clamp data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-54

A.39 PWR pipe hanger data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-55

A.40 Mass of potentially cleared materials from decommissioning of licensed facilities . . A-59
Inventory of Materials Appendix A

NUREG-1640 A-vi

Figures

Page

A.1 VSC-24 concrete cask storage system (BNFL 2000b) . . . . . . . . . . . . . . . . . . . . . . . . . A-37

A.2 NUHOMS spent fuel storage system (TNW 2000) . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-38

A.3 Modular vault dry storage facility (Raddatz and Waters 1996) . . . . . . . . . . . . . . . . . . . A-42

A.4 Pool (wet) storage facility (GE Nuclear Energy 2000) . . . . . . . . . . . . . . . . . . . . . . . . . A-43

A.5 Mass of decommissioning radwaste generated from non-power reactors . . . . . . . . . . . A-48
Appendix A Inventory of Materials

1

 “Potentially cleared” refers to materials with very low levels of residual radioactivity that are likely candidates for

clearance. 

2

 As of August 2003.

A-1 NUREG-1640

A INVENTORY OF MATERIALS FROM NRC AND AGREEMENT

STATE LICENSEES

A.1 Introduction

This appendix presents an analysis of inventories of materials associated with the dismantlement

of nuclear facilities licensed by the NRC and Agreement States. Inventories from commercial

nuclear power reactors, non-power reactors, nuclear fuel cycle facilities (e.g., fuel fabrication

plants, UF6 conversion plants, independent spent fuel storage facilities, and uranium mills), and

non-fuel-cycle materials licensees (e.g., sealed source manufacturers, R&D laboratories, and

hospitals) are developed to the extent that information on quantities of materials and activity

levels was obtainable during the course of the present study. Detailed information is not

available for each licensee. However, for some types of facilities, the NRC has published

decommissioning studies on generic or reference facilities which facilitate an inventory analysis. 

To the degree possible, quantities of material associated with various activity levels are

developed for each reference facility. In the case of nuclear reactors, scaling factors are used to

account for differences in reactor size. Scaling approaches are also developed for some other

categories of licensees.

Decommissioned commercial nuclear power reactors would be the major source of potentially

cleared materials1

 from dismantlement of licensed facilities. A total of 69 pressurized water

reactors (PWRs) and 35 boiling water reactors (BWRs) are currently licensed to operate by the

NRC.2 A typical PWR contains about 36,000 t of ferrous metals, 700 t of copper, 20 t of

aluminum, and 180,000 t of concrete. Approximately 18% of the ferrous metals is neutronactivated or has significant surficial radioactivity; the balance is clean or could be potentially

cleared. About one-third of this material is rebar in the concrete structures. BWRs typically

generate more radioactive materials because of the nature of the reactor design. It is estimated

that about 35% of the ferrous metals in a typical BWR is radioactive. 

The analysis includes estimates of the mass of ferrous metals and concrete that would be

generated during the decommissioning of fuel cycle facilities, including 2 uranium hexafluoride

conversion plants, 7 fuel fabrication plants, and 20 independent spent fuel storage installations. 

Materials inventories from the decommissioning of uranium milling operations, including both

NRC and Agreement State licensees, are described qualitatively. These facilities would not be

significant future sources of materials, since most are currently undergoing decommissioning

and dismantlement that will be completed in the near future. Information on copper and

aluminum that would be generated by fuel cycle facilities is lacking, but these metals are

expected to constitute a small fraction of the scrap metal inventory, which is dominated by

ferrous metals. 
Inventory of Materials Appendix A

3

 Non-impacted areas have no reasonable possibility (extremely low probability) for residual radioactivity in excess

of natural background or fallout from the worldwide testing of nuclear weapons (NRC 2000e).

NUREG-1640 A-2

The NRC currently licenses 36 non-power reactors. There are 25.2 t of structural steel and 88 t

of rebar in the reference 1,100 kW non-power reactor. The total mass of activated steel and

aluminum is 1.6 t. Components with significant surficial activity include the aluminum reactor

vessel, with a mass of 900 kg, and various steel components with a total mass of about 45 t. The

mass of concrete in the reference non-power reactor is 1,925 t, of which about 90% is clean.

As discussed in Section 1.1 of the main report, mass-to-surface ratios of cleared materials are

used to relate normalized mass-based doses to normalized surficial doses. These ratios are in

turn based on the mass-to-surface ratios of individual components. The mean mass-to-surface

ratio of potentially cleared ferrous metals from nuclear power plants is about 5 g/cm2

. 

A.1.1 Types of Material

The emphasis of the materials inventory analysis is on ferrous metals, copper, aluminum, and

concrete, since these materials constitute most of the mass of potentially cleared materials. To

the extent that data are available in the published literature, the total mass of each these four

types of materials is sub-divided into four broad categories based on expected activity levels as

follows:

• Radioactive – systems, subsystems, components, and structures with significant levels of

radioactivity. Neutron-activated items are included in this category. Typically, these

materials are so radioactive that cleanup to clearance levels is not technically and/or

economically practicable.

• Suspect – subsystems or components not specifically identified as radioactive but which are

parts of radioactive systems.

• Clean – materials generated from non-impacted areas of a nuclear facility, as defined in

“Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)” (NRC

2000e).3

 Such material is also referred to as non-impacted material.

• Potentially cleared – the balance of materials in the facility. For nuclear power reactors,

this is the largest category of materials and is the focus of this appendix.

A.1.2 Scope of Licensed Community

As reported in the June 2003 “Information Digest” (NRC 2003b), facilities licensed by NRC

include:

• Commercial nuclear power reactors (as of December 2002) . . . . . . . . . . . . . . . . . . . . . . . . 104
Appendix A Inventory of Materials

4

 Since 1958, 73 licensed non-power reactors have been decommissioned. 

5

 NRC 2003a. Does not include numerous Agreement State licensees nor two sites under general license to DOE

for long-term care.

A-3 NUREG-1640

• Non-power nuclear reactors4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36

• Fuel cycle facilities

- Uranium fuel fabrication plants (6 licensed to operate plus 1 in decommissioning) . . . . 7

- Uranium hexafluoride production plant (1 licensed plus 1 in decommissioning) .......2

- Gaseous diffusion plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

- Uranium mills and leaching operations5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22

- Independent spent fuel storage facilities (Keegan 2003) . . . . . . . . . . . . . . . . . . . . . . . . . 28

- By-product materials storage site ...........................................1

• Materials licensees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . approximately 4,800

In addition, there are approximately 16,600 materials licenses issued by 32 Agreement States

(NRC 2003b). Some of the materials licenses issued by the NRC to other government agencies

(i.e., Department of the Air Force, Department of the Navy, and Department of Agriculture) are

Master Materials Licenses. Numerous permits or sub-licenses are issued by the master licensee

under these Master Licenses. 

The number of licenses cited here was the number as of 2002–2003; however, this number is in a

constant state of flux. In addition, the dates of license termination are subject to change, as

licenses are terminated early or renewed for an additional period. For example, some

commercial nuclear power reactors have received license renewals for an additional 20 years

beyond the 40-year span of the original operating licenses. A number of other renewal

applications are pending.

A.2 Commercial Nuclear Power Reactors

This section presents analyses of material inventories for a reference BWR and a reference PWR. 

Section A.2.1 summarizes regulatory decommissioning options. Section A.2.2 discusses scaling

factors used to adjust the materials inventories of the reference reactors to other reactor sizes. 

Sections A.2.3 and A.2.4 describe a reference BWR and a reference PWR in terms of materials

inventories and expected activity levels. Section A.2.5 presents anecdotal data on clearance.

A.2.1 Decommissioning Policies

With the publication of the NRC's Decommissioning Rule in June 1988 (NRC 1988), owners

and/or operators of licensed nuclear power plants were required to prepare and submit plans and

cost estimates for decommissioning their facilities to the NRC for review. Decommissioning, as

defined in the rule, means to remove nuclear facilities safely from service, and to reduce
Inventory of Materials Appendix A

NUREG-1640 A-4

radioactivity to a level that permits release of the property for restricted and unrestricted use and

termination of the license. The decommissioning rule applies to the site, buildings, and contents

and equipment.

Historically, the NRC has established three classifications for the decommissioning of nuclear

facilities (NRC 2000b):

• DECON is the alternative in which “the equipment, structures, and portions of a facility and

site that contain radioactive contaminants are removed or decontaminated to a level that

permits termination of the license after cessation of operations.”

• SAFSTOR is the alternative in which “the facility is placed in a safe, stable condition and

maintained in that state until it is subsequently decontaminated and dismantled to levels that

permit license termination. During SAFSTOR, a facility is left intact, but the fuel has been

removed from the reactor vessel and radioactive liquids are drained from systems and

components and then processed. Radioactive decay occurs during the SAFSTOR period,

thus reducing the levels of radioactivity in and on the material, and potentially the quantity of

material that must be disposed of during decommissioning and dismantlement.” Activities

under the SAFSTOR alternative must be completed within 60 years after shutdown. 

• ENTOMB is the alternative in which radioactive structures, systems, and components are

encased in a structurally long-lived substance, such as concrete. “The entombed structure is

appropriately maintained and continued surveillance is carried out until the radioactivity

decays to a level that permits termination of the license.”

A.2.2 Scaling Factors for Commercial Nuclear Power Reactors

The methodology used to develop the scaling factors is described by Anigstein et al. (2001,

Section A.5.2.1), as cited below:

It is reasonable to assume a correlation between a plant's power rating and its material

inventory. By this means, data on reference PWRs and BWRs can be utilized to estimate

inventories for the industry at large. In reports prepared for the DOE, Argonne National

Laboratory (ANL) employed a scaling method based on the mass of PWR and BWR pressure

vessels . . . . ANL assumed that all metal inventories for both PWRs and BWRs can be

calculated from those at the corresponding reference plant based on the design power, as

follows:

M = mass of metal (e.g., carbon steel) in actual reactor

Mr = mass of same metal in reference reactor

P = power rating of actual reactor (MWe)
Appendix A Inventory of Materials

6

 Now the Northwest Energy Columbia Generating Station.

A-5 NUREG-1640

Pr = power rating of reference reactor

The quantity is referred to as the scaling factor for nuclear power reactors.

A complete listing of U.S. operating commercial nuclear power reactors, together with the

shutdown date established by their operating license, is included in NRC 2003b. We apply

scaling factors to adjust the quantities of materials expected in reactors with various design

power levels. 

NRC 2003b also lists commercial nuclear power reactors that were formerly licensed but have

been shut down. Reactors whose owners have chosen the ENTOMB decommissioning

alternative and those with the DECON alternative that have largely completed decommissioning

are excluded from the present analysis. The three non-light-water reactors in SAFSTOR are

included with BWRs in the present analysis.

Pertinent information on scaling factors presented by Anigstein et al. (2001) is summarized in

Table A.1. 

A.2.3 Mass of Materials in Reference BWR

As of December 2001, there were 35 BWRs with NRC operating licenses (NRC 2003b). In

addition, the NRC lists 9 BWRs formerly licensed to operate; many of these are low-power units

(i.e., < 200 MWt).

Table A.1 Nuclear power reactor scaling factors

Reactor type No. of reactors Cumulative scaling factor

Operating PWRs 69 65.86

Shutdown PWRs 8 6.09

Operating BWRs 35 32.33

Shutdown BWRs 9 1.92

A.2.3.1 General BWR Description

In the late 1970s and early 1980s, the NRC commissioned a series of studies on the technology

and costs of decommissioning several types of nuclear facilities. A generic or reference design

was selected for each facility studied. Designs for both a reference PWR and a reference BWR

were developed. The reference BWR is based primarily on the description of the 3,320 MWt

(1,155 MWe) Washington Public Power Supply System (WPPSS) Washington Nuclear Project 2

presented by Oak et al. (1980a, 1980b) and Smith et al. (1994a, 1994b).6
Inventory of Materials Appendix A

NUREG-1640 A-6

The primary purpose of the revised analysis by Smith et al. (1994a, 1994b) was to reevaluate

estimated costs and schedules for license termination of the reference BWR. This re-evaluation

was designed, in part, to reflect the requirement that spent fuel must be cooled in the reactor pool

for about 5 years before being accepted by DOE for dry storage (Smith et al. 1994a). For

reactors where DECON was the selected decommissioning alternative, the following schedule

was assumed:

• Pre-shutdown planning–engineering and regulatory reviews – 2.5 years

• Plant deactivation, chemical decontamination, removal of reactor pressure vessel internals, and

systems lay-up – 1.2 years

• Safe storage of laid-up plant, spent fuel pool storage operations, preparation for active

decommissioning activities — 3.4 years

• Plant dismantlement – 1.7 years

The reference BWR consists of three principal buildings with radioactive systems or

components: the Reactor Building, the Turbine Generator Building, and the Radwaste and

Control Building (Oak et al. 1980a, pp. 7-6 to 7-9). Several additional buildings make up the

reference BWR complex. These include the Diesel Generator Building, Service Building,

Circulating Water Pump House, Spray Pond Complex, Makeup Water Pump House, the yard,

and other buildings (i.e., Office Building, Warehouse, Guard House, and Gas Bottle Storage

Building). These buildings are assumed to be non-impacted. 

Oak et al. (1980a and 1980b) assume that the reference BWR would be decontaminated prior to

dismantlement, but do not assume clearance of any residually radioactive materials. All major

components, including the turbines and condenser, are assumed to be buried as LLRW.

The reports on the reference BWR do not address all the materials in the plant. Consequently,

we need to construct a summary of such materials from information scattered throughout the two

reports addressing the reference BWR (Oak et al. 1980a , 1980b, and Smith et al. 1994a, 1994b). 

These reports contain considerable information on ferrous metals, some information on concrete,

limited information on aluminum, and no specific information on copper.

Summary information on the structural materials used in the reference BWR, including concrete,

structural steel, and rebar, is provided by Oak et al. (1980b, Table C.2-1) and is presented in

Table A.2 of the present report. Smith et al. (1994a, Appendix H) present related information. 

While the latter data are similar to those of Oak et al. (1980b), some differences exist. The data

of Oak et al. (1980b) are used here, since that data set is more complete.
Appendix A Inventory of Materials

A-7 NUREG-1640

Table A.2 Estimated quantities of structural materials in the reference BWR facility

Structure Concrete (m3

) Rebar (t) Structural steel (t) 

Reactor Building 42,804 8,608 902

Primary Containment 1,225 187 693

Turbine Generator Building 46,672 4,717 742

Radwaste and Control Building 26,697 2,746 372

Diesel Generator Building 2,964 408 0

Service Building 2,359 151 395

Circulating Water Pump House 2,963 321 112

Spray Pond Complex 8,321 789 0

Makeup Water Pump House 1,278 163 0

Yard and Other Buildings 12,825 247 91

Totala 147,880 18,351 3,307

Source: Oak et al 1980a, Table C.2-1

a Total concrete and rebar as listed by Oak et al. (1980a) does not correspond to sum of masses listed in table.

In the present analysis, only the Reactor Building (including primary containment), the Turbine

Generator Building, and the Radwaste and Control Building are assumed to contain radioactive

systems or components (Oak et al. 1980a, Table 7.3-3).

A.2.3.2 Ferrous Metals in Reference BWR

A summary of the ferrous metals in the reference BWR is presented in Table A.3, based on

information on the reference BWR (Oak 1980a , 1980b, and Smith et al. 1994a , 1994b).

Masses of most of the systems in Table A.3 are listed by Anigstein et al. (2001, Tables A.32 –

A.64). These data were primarily derived from data listed by Smith et al. (1994b, Table C.5). 

Some of the data presented by Anigstein et al. have been adjusted in the course of the present

analysis.

Table A.3 shows that about 34 kt of components and systems composed of ferrous metals have

been identified in the reference BWR.

Neutron-Activated Ferrous Metals in Reference BWR

The masses of the neutron-activated ferrous metal (carbon and stainless steel) components are

summarized in Table A.4. 
Inventory of Materials Appendix A

NUREG-1640 A-8

Table A.3 Summary of ferrous metals in reference BWR

Location System System mass (kg) 

Reactor

Building

Containment instrument air 6,996

Control rod drive 219,442

Equipment drain processing 52,631

Fuel pool cooling & cleanup 343,121

High pressure core spray 46,295

HVAC components 58,162

Low pressure core spray 20,799

Main steama 3,894,143

Main steam leakage control 2,125

Misc. Items from partial system 67,399

Closed cooling water 42,321

Equipment & floor drains 9,943

Reactor core isolation cooling 21,554

Reactor water cleanup 47,520

Residual heat removal 306,401

Misc. drains 7,650

Piping (non-primary containment) 348,122

Piping (primary containment) 838,180

Primary containment 693,000

Steam dryer 41,277

Steam separator 33,929

Steam separator (highly radioactive segment) 15,436

Core shroud 37,694

Top fuel guide 5,429

Jet pumps 5,683

Support ring 2,359

Core support plate 9,298

Orificed fuel supports 5,366

Control room guides 9,549

Limiters, housings 43,967

Shroud support 44,906

RPV upper flange 55,221

RPV upper head 29,602

RPV lower flange 54,514

Non-activated RPV wall 255,111

Activated RPV wall 161,210

Lower head 110,922

Nozzles 59,139

Studs & nuts 31,481

Skirt, base ring, & collar 61,350

Sacrificial shield, steel only 77,364

Subtotal 8,176,611
Appendix A Inventory of Materials

Table A.3 Summary of ferrous metals in reference BWR

Location System System mass (kg) 

A-9 NUREG-1640

Radwaste

Building

Chemical waste processing 59,803

Condensate demineralizers 89,783

HVAC components 102,751

Radioactive floor drain processing 31,237

Building drains 3,897

Standby gas treatment 40,588

Sample systems 1,148

Piping 165,927

Subtotal 495,134

Turbine

Building

Feed & condensate 1,592,118

Extraction steam 115,710

Heater vents & drains 198,775

HVAC components 76,393

Offgas (augmented) 64,483

Recirculation 120,536

Building drains 4,730

Piping 1,176,074

Subtotal 3,348,819

Total Plant

Small pipe hangersb 282,366

Large pipe hangersb 802,872

Rebar 18,351,000

Structural steel (less primary containment) 2,614,000

Subtotal 22,050,238

Grand Total 34,070,802

a

 Some Main Steam System components in Turbine Building

b

 Bierschbach 1996

Table A.4 Neutron-activated ferrous metal components in reference BWR

Component Mass (kg)

Steam separator 15,436

Core shroud 37,694

Top fuel guide 5,429

Jet pumps 5,683

Core support plate 9,298

Orifice fuel supports 5,366

Control rod guides 9,549

Activated RPV wall–cladding 161,210

Sacrificial shield (steel only) 77,364

Total 327,029

Source: Smith et al. 1994b, Table E.4 
Inventory of Materials Appendix A

NUREG-1640 A-10

Ferrous Metal Equipment and Piping with Activity on Internal Surfaces

Activities will be present on internal surfaces of piping and components in the reactor system,

particularly those exposed to reactor cooling water. Oak et al. (1980b, Tables E.2-6 and E.2-7)

used the following methodology to develop the activity estimates for these items: 

• The surface area of components expected to have internal surface activity was estimated.

• Activity deposition levels were developed, based on operational exposure.

• Five deposition levels, ranging from 5 Ci/m2 (18.5 MBq/cm2) for tanks and equipment

containing concentrated waste to 5 ×10-4 Ci/m2 (185 Bq/cm2) for the turbine, were selected

by the authors as representative of the range of expected activity levels.

• Total deposited activity was calculated as the product of the surface area and the assumed

deposition level.

A summary of identified components with internal surface activity is presented in Table A.5. 

The total mass of the components in the table is about 3 kt less than the amount in Table A.3 for

those systems with identified internal activity, due to lack of sufficient information to enable us

to associate mass with activity for all listed components and systems.

Many of the systems and components in Table A.5 will also have activities on external surfaces. 

The activity on external surfaces is about 1% of the activity on internal surfaces (Oak et al.

1980b, Table E.2-10).

Ferrous Metals with No Detectable Levels of Residual Radioactivity 

A large fraction of the total ferrous metals in the reference BWR are assumed to have no

detectable levels of residual radioactivity. The structural metals and rebar from Table A.2 are

classified according to MARSSIM screening classifications (NRC 2000e), based on the

engineering judgment of the present authors (see Table A.6).

A.2.3.3 Concrete in the Reference BWR

As indicated in Table A.2, the reference BWR contains about 148,000 m3

 of concrete. Assuming

a density of 2.4 g/cm3

, the concrete mass is estimated to be 355 kt. Of this material, 79% is

associated with the Reactor Building (including primary containment), the Turbine Building, and

the Radwaste and Control Building, with the balance (30,710 m3

 ) being distributed over nonimpacted support buildings. 
Appendix A Inventory of Materials

A-11 NUREG-1640

Table A.5 Mass of components with activities on internal surfaces in reference BWR

Location System Component Mass (kg)

Reactor

Building

Equipment drain processing

Spent Resin Tank 657

Waste Collector Tank 10,229

Waste Surge Tank 18,282

Waste Sample Tanks 13,920

Fuel pool cooling & cleanup Fuel Pool HX 4,076

Skimmer Surge Tanks 10,708

Main steam

Turbine Bypass Valve Assembly 5,266

Moisture Separator Reheaters 416,772

Steam Evaporator 26,944

Gland Steam Condenser 1,816

Main Condenser 1,570,000

Main Turbine 1,338,372

Closed cooling water RBCCW Heat Exchangers 22,380

Reactor water cleanup

RWCU Non-Regenerative HX 8,172

RWCU Regenerative HX 12,394

Cleanup Phase Separator Tanks 4,086

Residual heat removal RHR HX 58,380

Pressure vessel and internals All items with surficial activity 823,778

Radwaste

Building

Chemical waste processing

Distillate Tanks 10,048

Decon Solution Concentrator Tanks 1,422

Detergent Drain Tanks 3,668

Chemical Waste Tanks 10,048

Decon Solution Concentrators 6,810

Condensate demineralizers Condensate Backwash Receiver Tank 6,912

Condensate Phase Separator Tanks 6,356

Radioactive floor drain processing

Floor Drain Collector Tank 10,229

Floor Drain Sample Tank 6,960

Waste Sludge Phase Separation Tank 5,490

Feed & condensate

Condensate Storage Tanks 100,950

High & Low Pressure Feed Water Heaters 883,896

Air Ejector Condensers 13,228

Heater vents & drains

Moisture Separator Drain Tanks 3,430

Reheater Drain Tanks 29,632

Steam Evaporator Drain Tanks 1,796

Piping Piping <60 mm o.d. 68,289

Piping >60 mm o.d. 2,460,014

Total 7,975,410

Oak et al. (1980a , 1980b) and Smith et al. (1994a, 1994b) assume that all concrete surfaces

(except those expected to be neutron-activated) will be vacuumed after shutdown to remove any

loose radioactive debris. The surfaces will be surveyed to detect any significant radioactivity. 

Areas with detectable activity will then be washed using high-pressure water jets and resurveyed
Inventory of Materials Appendix A

NUREG-1640 A-12

to identify regions that are still radioactive. Such areas will then be scabbled to a nominal depth

of 1 inch to remove this surface activity. Smith et al. (1994a, Table 3.20) estimate that the

following volumes of concrete would be removed by scabbling:

• Reactor Building ................ 36.9 m3

• Turbine Generator Building . . . . . . . 3.50 m3

• Radwaste and Control Building . . . . 11.0 m3

Table A.6 MARSSIM classification of rebar and structural steel in reference BWR

Facility Rebar Structural steel

Mass (t) Classificationa Mass (t) Classificationa

Reactor Bldg. 8,608 Class 3 902 Class 2

Primary Containment 187 Class 2 693 Class 2

Turbine Generator Bldg. 4,717 Class 3 742 Class 3

Radwaste & Control Bldg. 2,746 Class 3 372 Class 2

Diesel Generator Bldg. 408 Non-impacted 0 Non-impacted

Service Bldg. 151 Non-impacted 395 Non-impacted

Circ. Water Pump House 321 Non-impacted 112 Non-impacted

Spray Pond Complex 789 Non-impacted 0 Non-impacted

Makeup Water Pump House 163 Non-impacted 0 Non-impacted

Yard & Other Bldg. 247 Non-impacted 91 Non-impacted

Total 18,351b 3,307

a

 Assumed MARSSIM classification

b

 Total rebar as listed by Oak et al. 1980a does not correspond to sum of masses listed in table.

Oak et al. (1980a, Table 7.3-3) assumed that about 700 m3 of concrete rubble would be

generated. Detailed support for these estimates is provided by Oak et al. (1980b, Appendix D) . 

Oak et al. (1980a) assumed that concrete would be scabbled to a depth of 2 in (0.051 m). The

more recent results of Smith et al. (1994a) are used here for estimating scabbled masses.

The neutron-activated reinforced concrete in the sacrificial shield (biological shield) has an

estimated volume of 73.3 m3

 (Oak et al. 1980b, Table E.1-6). This is a small fraction of the total

of 1,225 m3

 concrete in the Primary Containment (see Table A.2). 

Because of the nature and the levels of activity, all of these scabbled or neutron-activated

materials will be buried as LLRW. However, most of the concrete could be potentially cleared. 

A.2.3.4 Copper and Aluminum in the Reference BWR

No substantive information on the quantity of copper in the reference BWR was located during

this study. Limited anecdotal information is provided in Section A.2.3.5. Consequently, the

total quantity of copper in the reference BWR is assumed to be 694 t, the same as in the

reference PWR (see Table A.10). The amounts of clean and potentially cleared copper are also

assumed to be the same as in the reference PWR.
Appendix A Inventory of Materials

A-13 NUREG-1640

The only aluminum components specifically identified in the reference BWR are piping (Oak et

al. 1980b, Tables C.3-7, C.3-9, and C.3-10). The mass of this piping is summarized in

Table A.7.

Table A.7 Estimated mass (kg) and total activity (Ci) of aluminum piping in reference BWR

Quantity Outside diameter (mm)

< 60 73 – 254 305 – 406

Mass in Reactor Building — 1,020 —

Mass in Turbine Building 1,712 23,449 12,716

Mass in Radwaste Building 288 17,841 920

Total mass 2,000 42,310 13,636

Total activitya 0.4 3.54 0.7

a

 Source: Oak et al. 1980b, Table E.2-5

This table indicates that about 4.6 Ci (170 GBq) of activity is associated with about 58 t of

aluminum piping. Based on this activity level, the material in Table A.7 is assumed to be

disposed of as LLRW.

Since no additional details on the quantities of aluminum in the reference BWR were found

during the course of the present study, we assume that the masses of clean and potentially

cleared aluminum are the same as in the reference PWR (see Section A.2.4.2). 

A.2.3.5 Reference BWR Mass Summary

Summary information on the masses of materials and their presumed categories are presented in

Table A.8. Materials designated as clean are from non-impacted areas as defined by MARSSIM. 

Materials that are potentially cleared are arrived at by subtracting clean, surficially radioactive,

suspect, and activated materials from the total mass. 

Table A.8 Mass summary for reference BWR

Category Material mass (t) 

Concretea Ferrous metals Aluminum Copper

Activated 176 327 N/A N/A

Surficially radioactive 123 8,668 58 N/A

Suspect 0 3,025 N/A 52

Potentially cleared 281,000 19,374 2 62

Clean 73,700 2,677 10.7 580

Total 355,000 34,071 70.7 694

N/A - not available

a

 Based on concrete density of 2.4 g/cm3

The following discussion presents greater detail on the source of the ferrous metals masses in

Table A.8.
Inventory of Materials Appendix A

7

 Includes all items in Table A.3 except primary containment, structural steel, rebar, pipe hangers, and neutronactivated components.

NUREG-1640 A-14

• Total mass of ferrous metals (Table A.3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34,071 t

• Clean, i.e., non-impacted rebar and structural steel (Table A.2 and Table A.6) ..... 2,677 t 

It should be noted that the quantities of non-impacted rebar and structural steel are based

on the assumption that all buildings except the Reactor Building, the Primary Containment,

the Turbine Generator Building, and the Radwaste and Control Building would be nonimpacted, as defined by MARSSIM. Other assumptions are plausible. For example, it

might be reasonable to classify most, or all, of the rebar in the Turbine Building as nonimpacted. This would increase the clean material to 7,394 t. 

• Neutron-activated (Table A.4) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 327 t

• Mass with activity on internal surfaces (Table A.5) ........................... 7,975 t

• Primary Containment (activity on external surfaces) (Tables A.6) ................. 693 t

• Total mass of systems (most of which have activities on internal surfaces and are therefore

presumed to be disposed of as LLRW)7 .................................... 11,000 t

• Potentially cleared (34,071 ! 2,677 ! 327 ! 11,000 ! 693) .................... 19,374 t

• Potentially cleared (assuming Turbine Building rebar is non-impacted) .......... 14,657 t

The potentially cleared material would include the following:

• Rebar . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11,555 – 6,272 t

• Structural steel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2,016 t

• Pipe hangers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1,086 t

The principal driver in terms of potentially cleared metal mass is rebar, which makes up more

than 50% of the total ferrous metals in the reference BWR (see Table A.3) . Most of this rebar

will either be clean ab initio (i.e., because it comes from non-impacted areas), or can be shown to

be potentially cleared if the dismantlement plan calls for separation of the rebar from the

concrete matrix. 

In a decommissioning cost study of the Millstone 1 Nuclear Power Station, a 2,011 MWt BWR

in Waterford, CT, TLG Services, Inc., (1999a) estimated that 5,768 tons (5,233 t) of carbon and

stainless steels and 555 tons (504 t) of copper would be potentially salvageable from “clean areas

of Unit 1.” An additional 8,781 tons (7,967 t) of ferrous metals and 555 tons (504 t) of copper

would potentially be cleared by an off-site processor. However, since the electrical output of

Millstone 1 was about 600 MW, the TLG materials estimates should be scaled for comparison
Appendix A Inventory of Materials

A-15 NUREG-1640

with the reference reactor estimates, as described in Section A.2.2. Scaled masses of clean and

cleared Millstone 1 materials are 7,330 t and 10,782 t, respectively. The scaled TLG estimate of

7,330 t of clean ferrous metal scrap falls within the range 2,677 t to 7,394 t for the reference

BWR developed above. The scaled TLG estimate of 10,782 t of free-released scrap is

comparable to the estimate of 14,657 t to 19,374 t of potentially cleared ferrous scrap developed

for the reference 1,000 MWe BWR. This suggests that the amounts of clean and potentially

cleared material from the reference BWR developed in the current study are in reasonable

agreement with an independent estimate.

A.2.4 Mass of Materials in Reference PWR

As of December 2002, 69 PWRs had NRC operating licenses (NRC 2003b). In addition, NRC

lists 8 PWRs formerly licensed to operate.

A.2.4.1 General Description of Reference PWR

A description of the reference PWR is based on information from a number of literature sources. 

Bryan and Dudley (1974) estimated the materials inventory of a 1,000 MWe PWR power plant. 

That plant used run-of-river cooling, and the design features were those that prevailed in 1971. 

More details of the plant systems and residual levels of radioactivity are taken primarily from

reports by Smith et al. (1978a, 1978b) and Konzek et al. (1995a, 1995b). Both reports describe

the 3,500 MWt (1,175 MWe) Trojan Nuclear Plant at Rainier, OR, operated by Portland General

Electric Company.

Table A.9 lists the estimated quantities of the principal metals used to construct a 1,000-MWe

PWR facility. According to Bryan and Dudley (1974), this facility also contained 179,681 t

(74,970 m3

) of concrete.

Table A.9 Estimates of metals used to construct a 1,000-MWe PWR facility

Material Total quantity (t)

Carbon steel 33,000

(Rebar) (9,600)

(All Other) (23,000)

 Stainless steel 2,100

 Galvanized iron 1,300

 Copper 690

 Bronze 25

 Brass 10

 Aluminum 18

Source: Bryan and Dudley 1974, except rebar, which is from UE&C 1972.

A detailed breakdown of the various materials within the 1,000 MWe PWR is presented in

Table A.10. 
Inventory of Materials Appendix A

NUREG-1640 A-16

Table A.10 Breakdown of materials used in PWR plant structures and reactor systems (t)

System

 Carbon steel Stainless steel Galvanized iron Copper Inconel Lead Bronze Aluminum Brass Nickel Concrete Silver

Structures–site 16,519.3 28.6 814.2 33.1 0.0 33.1 0.2 1.2 2.9 0.1 146,472 0.1

 Site improvements 1,692.9 0.0 17.9 1.5 0.0 0.7 0.0 0.1 0.0 0.0 4,887 0.0

 Reactor Building 7,264.2 5.7 301.3 9.3 0.0 0.0 0.0 0.1 0.3 0.0 54,329 0.0

 Turbine Building 3,641.2 0.0 196.4 1.6 0.0 0.0 0.1 0.8 1.4 0.0 15,931 0.0

 Intake–discharge 333.7 0.0 3.6 0.2 0.0 0.0 0.0 0.0 0.0 0.0 13,215 0.0

 Reactor auxiliariesa 1,358.7 0.0 109.8 0.8 0.0 0.0 0.0 0.1 0.2 0.0 33,876 0.0

 Fuel storage 364.6 21.1 43.4 0.3 0.0 0.0 0.0 0.1 0.1 0.0 7,163 0.0

 Miscellaneous buildings 1,864.0 1.8 141.9 19.4 0.0 32.4 0.1 0.1 0.9 0.1 17,071 0.1

Reactor plant equipment 3,444.9 1,154.6 5.5 50.4 124.1 4.5 0.5 5.2 0.0 0.0 982 0.0

 Reactor equipment 430.0 275.1 0.0 6.8 0.1 0.0 0.0 0.0 0.0 0.0 136 0.0

 Main heat trans. system 1,686.5 202.5 1.6 9.8 124.1 0.0 0.0 0.0 0.0 0.0 732 0.0

 Safeguards cool. system 274.2 199.1 1.1 2.9 0.0 0.0 0.1 0.0 0.0 0.0 0 0.0

 Radwaste system 35.2 31.9 0.8 0.2 0.0 0.0 0.0 0.0 0.0 0.0 0 0.0

 Fuel handling system 82.0 67.0 0.2 0.2 0.0 0.0 0.0 0.0 0.0 0.0 13 0.0

 Other reactor equipment 823.5 230.3 1.7 1.5 0.0 4.5 0.4 0.0 0.0 0.0 101 0.0

 Instrumentation & control 113.5 148.7 0.0 29.0 0.0 0.0 0.0 5.2 0.0 0.0 0 0.0

Turbine plant equipment 10,958.3 883.2 4.7 51.4 0.0 0.0 21.5 1.2 6.9 0.0 30,506 0.0

 Turbine-generator 4,138.7 129.9 0.5 35.2 0.0 0.0 19.7 0.0 0.0 0.0 11,353 0.0

 Heat rejection systems 2,501.1 9.1 2.2 3.0 0.0 0.0 0.7 0.0 0.4 0.0 15,143 0.0

 Condensing systems 1,359.8 392.3 0.6 1.3 0.0 0.0 0.2 0.0 1.5 0.0 1,282 0.0

 Feed-heating system 1,367.8 221.2 0.5 1.2 0.0 0.0 0.3 0.0 3.9 0.0 110 0.0

 Other equipment 1,541.3 89.4 0.9 0.7 0.0 0.0 0.5 0.0 1.1 0.0 2,618 0.0

 Instrumentation & control 49.8 41.3 0.0 10.0 0.0 0.0 0.0 1.2 0.0 0.0 0 0.0

Electric plant equipment 965.5 0.0 431.1 556.5 0.0 6.8 2.5 4.1 0.0 0.6 1,263 0.4

 Switchgear 30.4 0.0 1.4 2.8 0.0 0.0 0.7 0.0 0.0 0.0 0 0.3

 Station service equip. 654.1 0.0 8.6 19.1 0.0 6.8 0.7 0.0 0.0 0.0 128 0.1

 Switchboards 87.0 0.0 0.0 13.5 0.0 0.0 0.1 4.1 0.0 0.0 0 0.0

 Protective equipment 5.9 0.0 0.0 39.0 0.0 0.0 0.5 0.0 0.0 0.0 0 0.0

 Structures & enclosure 112.5 0.0 421.1 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,135 0.0

 Power & control wiring 75.6 0.0 0.0 482.2 0.0 0.0 0.5 0.0 0.0 0.6 0 0.0

Miscellaneous equipment 843.2 13.7 2.0 2.6 0.0 2.0 0.4 6.5 0.3 0.0 458 0.0

 Transportation & lifting 529.3 0.0 0.0 0.5 0.0 0.0 0.0 0.0 0.0 0.0 0 0.0

 Air & water service sys. 232.6 6.0 0.0 1.2 0.0 0.0 0.0 0.0 0.3 0.0 458 0.0

 Communications equip. 4.7 0.0 0.6 1.0 0.0 0.0 0.0 0.3 0.0 0.0 0 0.0

 Furnishings & fixtures 76.7 7.7 1.4 0.0 0.0 2.0 0.4 6.1 0.0 0.0 0 0.0

Entire plant 32,731.2 2,080.1 1,257.4 694.0 124.1 46.4 25.1 18.2 10.1 0.7 179,681 0.5

Source: Bryan and Dudley 1974

Note: Totals may not add due to rounding

a

 Underlined text identifies equipment or systems expected to be radioactive.
Appendix A Inventory of Materials

A-17 NUREG-1640

As noted, the 1,000 MWe PWR analyzed by Bryan and Dudley (1974) contained 74,970 m3 of

concrete. This quantity is similar to that for the reference PWR (i.e., 74,278 m3) presented by

Konzek (1995b, Appendix L). 

A.2.4.2 Mass of Systems and Components in Reference PWR

This section characterizes the masses of systems and components in terms of their relative

activity levels.

Mass of PWR Components with Volumetrically Distributed Activities

Volumetrically distributed activities are dispersed throughout the thickness of a component and

cannot be removed by surface decontamination methods. In the present analysis, volumetrically

radioactive materials comprises neutron-activated reactor components and structural materials. 

The reactor vessel and various internal components are assumed to be volumetrically

radioactive. In addition, concrete, rebar, and structural steel in the reactor building could also be

activated. The total mass of neutron-activated components in the reference PWR is estimated to

be 305.7 t (Smith et al. 1978a, Table 7.3-2).

Mass of PWR Systems and Components with Activities on Internal Surfaces

Since the reference PWR studies did not provide correlated data on the masses and activity of

systems and components, the Trojan Radiological Site Characterization Report (Portland

General Electric 1995) was used as a source for such data. Table A.11 presents data from this

report, based on actual samples. In some cases, measurements were not made because of high

radiation levels or because of continued operation of certain systems. Of the 58 systems

sampled, 23 showed surficial activity levels greater than 1,000 dpm/100 cm2

, and 2 showed low

but detectable levels (less than 1,000 dpm per 100 cm2). The table also indicates the assumed

radiological category (class) prior to survey by the Trojan staff.

The total mass of systems with internal surface activities is 8,769,000 lb (3,978 t).

In addition, the Trojan staff characterized the Activities on other systems and components which

were not internally sampled because (a) they were included in other assessments, (b) were

entirely electrical, or (c) were non-impacted. These are listed in Table A.12.

Radioactive material on the systems listed in Table A.11 consists of both fixed and removable

activities. According to Portland General Electric (1995, Section 6.1.2): “the total radioactivity

is not expected to be substantially reduced by nonaggressive decontamination methods. 

Operational experience during activities such as steam generator primary bowl hydrolasing

indicated that the radioactivity is tightly adherent to surfaces and will require disposal of the

entire component.” 
Inventory of Materials Appendix A

NUREG-1640 A-18

Table A.11 Trojan PWR system characterization data

Classa No. of 

samples System name Weight Activityb

 (Ci) lb t

C2 6 Component cooling water 475,874 215.856 GeLic

C1 18 HVAC-fuel & auxiliary buildings 45,800 20.775 >1 kc

C1 NSd Spent fuel pool cooling & demineralizer 57,281 25.983 5.6

C1 NS Spent fuel pool 628,378 285.032 100

C2 5 Condensate demineralizers 18,000 8.165 Cleane

Discharge & dilution 63,505 28.806 <1

C1 NS Residual heat removal 183,855 83.397 36

C1 NS Chemical & volume control 534,034 242.238 25

C1 NS Safety injection & accumulators 493,765 223.972 <1

C1 NS Control rod drive mechanisms 106,318 48.226 83

C2 8 HVAC-containment 407,328 184.764 >1 k

C2 2 Containment spray 75,252 34.134 >1 k

C1 NS Steam generators 2,650,448 1202.243 1416

C2 6 SG blowdown 39,449 17.894 >1 k

C1 NS Reactor coolant pumps 768,400 348.546 134

C1 NS Reactor coolant system piping 296,460 134.474 221

C1 NS Pressurizer 195,508 88.682 52.1

C1 NS Reactor vessel–internals (surface only) 1,286,000f 583.330 357.9

C1 2 Hydrogen recombiners 12,600 5.715 >1 k

C2 2 Primary water makeup system 90,006 40.827 >1 k

C1 1 Refueling water storage tank 97,928 44.420 7

C1 NS Solid radwaste 10,341 4.691 <1

C1 NS Clean radwaste 110,634 50.184 14

C1 NS Dirty radwaste 24,116 10.939 <1

C1 NS Gaseous radwaste 77,261 35.046 <1

C1 NS Process sampling 3,093 1.403 4

C2 21 Miscellaneous sumps 19,136 8.680 >1 k

Total 8,770,770 3978.421

Volume

ft3 m3

C2 2 Startup boiler Clean

C2 3 Condensate storage–transfer Clean

C2 2 Condenser & air removal Clean

C2 9 Condensate Clean

C2 5 Feedwater system (& AFW) Clean

C2 2 Extraction steam Clean

C2 4 Feedwater heaters, vents & drains Clean

C2 4 SG feed pump turbine drivers Clean

C2 11 Oily waste & storm drains 1,882 53.29 Cleane

C2 1 Degassifier Clean
Appendix A Inventory of Materials

Table A.11 Trojan PWR system characterization data

A-19 NUREG-1640

Classa No. of 

samples System name Volume Activityb

ft3 m3

C2 13 Main steam Clean

C2 9 Reheat & moisture separators Clean

I 2 Service water Clean

I 2 Turbine Building cooling water Clean

I 1 Process & auxiliary steam Clean

I 4 HVAC - turbine Clean

I 2 Circulating water pumps & aux. Clean

I 2 Misc. gas supply GeLi

I 4 Chemical injection Clean

I 13 Main turbine Clean

N 2 125 V DC 175 4.96 Cleane

N 2 480 V AC aux. load centers 5,080 143.9 Cleane

N 2 480 V motor control centers 8,426 238.6 Cleane

N 1 Lighting panel power supply 7 0.20 Cleane

N 5 Domestic water Clean

N 2 Makeup demineralizer water Clean

N 6 HVAC - control panel Clean

 N 1 P-250 computer Clean

N 1 125 V AC preferred instrument 1,400 39.64 Cleanc

N 2 Communications Clean

N 1 Annunciators Clean

N 1 Stator cooling Clean

N 2 Main generator & excitation Clean

N 4 Fish rearing facility Clean

Source: Portland General Electric 1995

a

 C1 – radioactive, C2 – suspect, I – indeterminate, N – non-impacted (clean)

b

 Does not include neutron activation; 1 Ci = 37 GBq

> 1 k – greater than 1,000 dpm/100 cm2

 above background

GeLi – less than 1,000 dpm/100 cm2 above background but showing activity with highly sensitive GeLi detector

c GeLi and >1 k, subsequently reclassified as < 1 Ci (Portland General Electric 2001)

d

 NS – not sampled due to high radiation levels or continued operation

e Subsequently reclassified as < 1 Ci (Portland General Electric 2001)

A.2.4.3 Concrete in Reference PWR

Remediation of radioactive structural surfaces is expected to be easier than remediation of

reactor piping with activity on internal surfaces. Removable activity can be cleaned up by

mopping or wiping the surfaces. Fixed activity on concrete can be removed by scabbling about 1

cm from the exposed surfaces. The volume of radioactive concrete components and the activity

on concrete surfaces are presented in Table A.13.
Inventory of Materials Appendix A

NUREG-1640 A-20

Table A.12 Expected categories of Trojan systems and components not sampled

Classa Description Reason not sampledb

C1 Refueling equipment A

C1 Containment Building A

C1 In-core neutron flux monitors A

C1 In-core temperature monitors A

C1 Fuel handling & refueling cavity A

C1 Vacuum cleaners A

C2 Miscellaneous buildings–structures A

C2 Turbine & Turbine Auxiliary Building A

C2 Condensate Demineralizer Building A

C2 Seismic monitor A

C2 Fuel & Auxiliary Building A

C2 Radiation shielding A

C2 Containment & misc. cranes A

I Intake–Discharge & Chlorine Buildings A

I Cooling tower structure A

I Elevators A

I Fuel Building crane A

N Technical Support Center Building A

N Turbine Building crane A

N Condensate demineralizer crane A

C2 Electric heat tracing power B

C2 Vibration & loose parts monitor B

C2 Nuclear instrumentation B

C2 Radiation monitors B

N 230 kV switchyard B

N 12.47 kV startup transformer B

N 4.17 kV aux. power B

N 120 V non-preferred Instrument AC B

N Computers (other than P-250) B

N Feedwater flow & level control B

N Feed line isolation actuation B

N Auxiliary feedwater autostart B

N Engineered safeguards actuation B

N Reactor control and protection B

N Reactor non-nuclear instrumentation B

N ATWS mitigation & actuation B

N Transformers & auxiliaries B

N 250 V DC B

N Meteorological equipment B

N Welding receptacles B

N Cathodic protection B

N Vehicle battery charger B
Appendix A Inventory of Materials

Table A.12 Expected categories of Trojan systems and components not sampled

Classa Description Reason not sampledb

A-21 NUREG-1640

N Motor operated doors B

N Security system B

C2 Fire protection C

C2 DD & DS, dechlorination system C

I Instrument & service air C

I Emergency diesel generators C

I HVAC - miscellaneous buildings C

I Sewage treatment C

I Turbine steam seal & drain C

N Traveling water screens & screen wash C

N Chlorination C

N Bearing cooling water C

N Water pretreatment C

N Diesel fuel oil C

N HVAC - Admin. Bldg. & Gatehouse C

N Lube oil storage & filtration C

N Cooling tower makeup & discharge C

N Cooling tower acid pump C

N Primary containment testing C

N Chilled water C

N Generator & hydrogen seal oil C

Source: Portland General Electric 1995

a See notes to Table A.11

b A – included in other assessments

B – entirely electrical

C – non-impacted (clean)

Table A.13 Volume and activity of Trojan structural concrete components

Building Volume Activity

ft3 m3 mCi MBq

Containment (floors) 668 18.92 20.4 755

Containment (walls) 2,262 64.05 2.71 100.3

Auxiliary 234 6.63 2.31 85.5

Fuel 176 4.98 1.13 41.8

MSSS–EPa 43 1.22 1.36 50.3

Turbine 75 2.12 2.39 88.4

Total 3,461 100.92 30.3 1121

Source: Portland General Electric 1995, Table 7.1

 a MSSS–EP: main steam support structure–electrical penetrations
Inventory of Materials Appendix A

8

 Totals may differ from tabulated values due to roundoff

NUREG-1640 A-22

Based on the data in Table A.13, the average specific activity, is estimated to be 4.6 Bq/g,

assuming a concrete density of 2.4 g/cm3. This material would most likely be disposed of as

LLRW.

The Trojan staff estimates that the volumes in Table A.13 should be increased by an additional

10% to account for radioactivity on ceilings and other non-floor surfaces, and the volumes

should be increased by another 10% to account for the possibility that some areas must have

more than 1 cm of the surface layer removed. Thus, the net volume removed is 4,184 ft3

(118.5 m3). This volume is exclusive of the activated volume in the primary shield wall. 

A.2.4.4 Reference PWR Mass Summary

A.2.4.4.1 Ferrous Metals

As noted in Table A.13, there was some activity on containment building walls, but this could be

removed by scabbling about 1 cm of material from the radioactive areas. No information is

available as to the activity levels of structural steel and rebar in those areas where there are

activities on concrete surfaces. In the absence of any specific information, the ferrous metals in

these structures are assumed to be clean or easily decontaminated by washing or wiping.

Based on the data listed in Table A.10, reactor plant equipment is expected to be a large source

of radioactive materials. This category comprises a total of 4,605 t of ferrous metals (carbon

steel, stainless steel, and galvanized iron), compared to the total of 3,978 t reported for the

Trojan Nuclear Plant, which is based on radiological surveys (see Table A.11). Based on the

clean systems listed in Table A.11, and the systems and components not sampled, as listed in

Table A.12, it is reasonable to assume that a significant fraction of the mass of ferrous metals in

Table A.10 would be designated as non-impacted (or clean) under MARSSIM. The assumed

ferrous metals breakdown for the reference 1,000 MWe PWR and the assumed MARSSIM class

for each system or structure are presented in Table A.14.

A reconciliation of the mass of ferrous metals by classification is given below:8

• Total mass of ferrous metals (Table A.10) ................................. 36,069 t

• Clean, i.e., non-impacted rebar and structural steel and equipment (Table A.14) . . . 6,311 t 

The quantities of non-impacted steel are based on the assumption that Electrical Plant

Equipment, Miscellaneous Equipment, Site Improvements, Intake–Discharge, and

Miscellaneous Buildings would be non-impacted as defined by MARSSIM. Other

assumptions are plausible. For example, it might be reasonable to classify most or all of

the ferrous metals in the Turbine Building as non-impacted. This would increase the clean

material by 3,838 t, to 10,149 t. 
Appendix A Inventory of Materials

A-23 NUREG-1640

• Neutron-activated (included in radioactive total below) . . . . . . . . . . . . . . . . . . . . . . . . . 306 t

• Mass of components with activities on internal surfaces (Table A.11) ............ 3,978 t

• Total mass of radioactive and suspect systems (most of which have activities on internal

surfaces and therefore are presumed to be radioactive and disposed of as LLRW) including

Reactor Auxiliaries and Fuel Storage Structures, and Reactor Plant Equipment from

Table A.10, and neutron-activated components ............................. 6,503 t

• Potentially cleared (36,069 - 6,311 - 6,503) ................................ 23,255 t

Table A.14 Summary of activity levels of ferrous metals in 1,000-MWe generic PWR

System Mass (t) MARSSIM class Category

Reactor plant equipment 3978 Class 1 Radioactivea

Reactor plant equipment 627 Class 2 Suspect

Turbine plant equipment 11,846 Class 3 Potentially clearedb

Electrical plant equipment 1,397 Non-impacted Clean

Miscellaneous equipment 859 Non-impacted Clean

Site improvements 1,711 Non-impacted Clean

Reactor Building 7,571 Class 2 Potentially clearedb

Turbine Building 3,838 Class 3 Potentially clearedb

Intake–discharge 337 Non-impacted Clean

Reactor auxiliaries 1,468 Class 2 Suspect

Fuel storage 429 Class 2 Suspect

Miscellaneous buildings 2,008 Non-impacted Clean

a

 See Table A.11 for details 

b

 Status after washing and/or wiping exposed steel

The mass of potentially cleared ferrous metals in this reconciliation is possibly overstated, as a

limited amount of the rebar and structural steel in the reactor building may be activated or have

surface activities not readily removable by wiping. Until additional decommissioning

experience with large PWRs has been gained, it will be difficult to more accurately estimate the

mix of radioactive and clean–cleared metal masses. Based on the reconciliation developed here,

it could be expected that the reference PWR containing 36,069 t of ferrous metals would release

6,311 t as non-impacted and clear 23,255 t. The ratio of clean to potentially cleared scrap from

PWR decontamination and decommissioning (D&D) could change, depending on the ability to

demonstrate that additional items beyond those noted here are clean. 

It is unlikely that all the clean and cleared steel from a given nuclear power plant would be

introduced into commerce in a single year. The schedule developed in Konzek et al. 1995a

allocates 1.7 years for dismantlement, which is the time span adopted for the present analysis. 

Based on actual dismantlement experience, the actual period is likely to be longer. (A longer

period would result in less material being cleared in any one year.) 
Inventory of Materials Appendix A

NUREG-1640 A-24

A.2.4.4.2 Copper

As listed in Table A.10, the reference PWR contains 694 t of copper. If we assume, in a manner

analogous to ferrous metals, that copper associated with reactor plant equipment and fuel storage

and reactor auxiliaries is radioactive, the mass of radioactive copper is 51.5 t. Copper associated

with Electrical Plant Equipment (556.5 t), Miscellaneous Equipment (2.6 t), Site Improvements

(1.5 t), Intake–Discharge (0.2 t) and Miscellaneous Building (19.4 t) is assumed to be nonimpacted (clean). Thus, the total mass of clean copper is 580.2 t. By difference, the mass of

potentially cleared copper is about 62 t. The mass of clean and potentially cleared copper is

about 642 t.

A.2.4.4.3 Aluminum

As listed in Table A.10, the reference PWR contains 18.2 t of aluminum. Of this total, 5.4 t is

associated with reactor equipment, reactor auxiliaries, and fuel storage and is likely to be

radioactive. A total of 10.8 t is associated with Site Improvements, Miscellaneous Buildings,

Electric Plant Equipment, and Miscellaneous Equipment. This material is presumed to be clean

(non-impacted). The balance—2.0 t—could be potentially cleared. 

Concrete

As listed in Table A.10, the reference PWR contains 179,681 t of concrete. Concrete associated

with Site Improvements (4,887 t), Intake–Discharge (13,215 t), Miscellaneous Buildings

(17,071 t), Electrical Plant Equipment (1,263 t), and Miscellaneous Equipment (458 t) is

assumed to be non-impacted. Thus, the total non-impacted (clean) concrete mass is 36,894 t. As

discussed previously, 118.5 m3

 of concrete would be scabbled from various surfaces and

disposed of as LLRW. Based on a concrete density of 2.4 g/cm3, this is equivalent to 284 t. By

difference, the mass of potentially cleared concrete would be 142,503 t.

Materials Summary

Radiological characterization of all materials in the reference PWR is summarized in Table A.15. 

It would be expected that most of the activated, surficially radioactive, and suspect materials

would be disposed of as LLRW and that most of the potentially cleared material would be

released from regulatory control. The clean material would not be subject to regulatory control. 

Table A.15 Mass summary for reference PWR (t)

Category Concrete Ferrous metals Aluminum Copper

Activated — 306 — —

Surficially radioactive 284 3,672 — —

Suspect — 2,525 5.4 52

Potentially cleared 142,503 23,255 2 62

Clean 36,894 6,311 10.7 580

Total 179,681 36,069 18.1 694
Appendix A Inventory of Materials

9

 A uranium mill tailings waste disposal facility in South Clive, UT, is also licensed under the regulation. 

A-25 NUREG-1640

A.2.5 Materials Inventories of Operating Nuclear Power Plants

At the end of 1996, Commonwealth Edison and the National Waste Management Corporation

surveyed nuclear utilities to assess generation and management of radioactive scrap metal

(Lorenz and Gardner 1997). Responses were received from 19 BWRs and 26 PWRs. Based on

these responses, the surveyors concluded that the then-current inventory of large components

(e.g., steam generators and turbine rotors) was 5,732 tons (5,200 t), and an additional 1,080 tons

(980 t) would be generated in 1997 from the replacement of steam generators at the McGuire and

Salem nuclear power plants. In addition, routine generation of radioactive scrap metal from the

respondents was expected to be about 2,000 tons (1,800 t) in 1997, and the existing inventory of

routine items was 7,955 tons (7,220 t). Approximately 90% of the routinely generated metal is

cleared after decontamination, and 10% is disposed of as LLRW. Inferentially, there is a “clean”

component of scrap metal, which was outside the scope of the survey.

The steam generators, which typically contain about 100 Ci (3.7 TBq) after a few years of

storage, are kept in on-site mausoleums. At the time of the survey, there were 28 PWR steam

generators in storage. Thirty-five turbine rotors, each weighing 110 tons (100 t), were also in

storage. The rotors have very low levels of residual radioactivity.

A.3 NRC Fuel Cycle Facility Licensees

This section presents a discussion of the nuclear fuel cycle facilities, including uranium mills,

UF6 conversion plants, uranium enrichment facilities, fuel fabrication facilities, and independent

spent fuel storage installations. 

A.3.1 Uranium Mills

The NRC currently licenses 22 uranium recovery facilities9 under 10 CFR Part 40, including

16 conventional uranium mills and 6 in-situ leach facilities (NRC 2003a). In addition, several

milling sites have been licensed by Agreement States (DOE 1995).

Uranium mills are excluded from the license termination requirements of 10 CFR 20. Most

conventional uranium mills have been shut down and are undergoing decommissioning. These

facilities would not be significant future sources of materials, since dismantlement will be

completed in the near future. One conventional mill is operating and one is on standby status. 

Since most materials generated during decommissioning are buried in onsite tailings piles or at

other approved sites, the quantities of potentially cleared materials from uranium mills are

expected to be small. 

Similar to the situation of conventional uranium mills, many in-situ leach facilities have been

shut down. These shut-down facilities are unlikely to be significant future sources of materials,

since dismantlement will be completed in the near future. Of the six in-situ leach facilities
Inventory of Materials Appendix A

NUREG-1640 A-26

licensed by NRC, three are operating, one is on standby status, one is being decommissioned,

and one is not yet built. Large quantities of materials are not expected to be generated when

these facilities are ultimately decommissioned. Radioactive equipment and plastic piping are

likely to be disposed of in tailings piles or at other licensed disposal sites.

A.3.2 Uranium Hexafluoride Production Facilities

Commercial U.S. nuclear power reactors are fueled with enriched uranium. This fuel is

produced by increasing the concentration of U-235 from 0.7%, the concentration in natural

uranium, to about 3%. Prior to the enrichment process, uranium oxide (yellowcake) is converted

to gaseous uranium hexafluoride (UF6).

As shown in Table A.16, the only operating UF6 conversion facility in the United States is

managed by Honeywell in Metropolis, IL. The NRC license for the Honeywell facility is due to

expire on June 30, 2005. The Sequoyah Fuels Corporation facility in Gore, OK, was shut down

in 1993 and is currently waiting decommissioning. Remediation at the Gore facility is expected

be completed in 2007.

Table A.16 Licensed uranium hexafluoride production facilities

Facility Process Startup - shutdown Capacity (MTU/y)a Status

Gore–Sequoyah Yellowcake to UF6 1970 - 1993 5,000 Shut down

Metropolis–Honeywell Yellowcake to UF6 1959 - 2005 14,000 In operation

a

 Metric Tons of Uranium 

A.3.2.1 Reference UF6 Production Facility

Elder and Blahnik (1981) performed a study of the decommissioning of a reference UF6

production facility. This reference facility is assumed to have an annual processing rate of

10,000 t of natural uranium. The basis for the reference facility was a combination of thenexisting and retired facilities (including both the Gore and Metropolis facilities); no attempt was

made to use a single existing facility as the basis of the study.

The reference UF6 production facility consists of a main building, a solvent extraction facility, a

warehouse, a cooling tower, retention lagoons, and other storage areas. The main building is a

55 m × 100 m steel frame structure with 3.8-cm-thick insulated metal siding. The interior walls

are constructed of concrete block and sheetrock. The floors are made of heavily reinforced

concrete, needed to support equipment. The roof is 3.5-cm-thick insulated corrugated metal

deck that is capped with asphalt and gravel. The solvent extraction facility has a steel frame with

metal siding and sealed concrete floors.

Material Masses

Elder and Blahnik (1981) provide considerable information on the quantity of ferrous metals and

some information on concrete, but no specific information on the quantities of aluminum or
Appendix A Inventory of Materials

A-27 NUREG-1640

copper within the facility. A condensed summary of the mass of steel contained in equipment

within the reference facility is presented in Table A.17.

In addition to steel in equipment, structural steel was used in the construction of the facility. 

Table A.18 gives an estimate of the mass of structural steel used in the facility, based on building

dimensions provided by Elder and Blahnik (1981), and “Structural Steel Weights per S. F. of

Floor Area” in R. S. Means 2000 (Section R051-220) for steel frame, one-story manufacturing

buildings with a floor load of 18 lbs/ft2 (88 kg/m2).

Table A.17 Mass of steel in equipment of UF6 production facility

Location Mass (t)

Sampling station 38.2

Wet yellowcake system 28.1

UF4 slurry processing 11.9

Ore concentrate dissolution 22.0

Solvent extraction 41.3

Uranyl nitrate concentration 33.0

Denitration 32.2

Uranium trioxide to uranium dioxide reduction 80.1

Hydrofluorination 255.7

Fluorination 99.5

Fluorine generation 264.6

Nitric Acid Recovery Area 15.6

Instrument Repair Shop 4.3

Radwaste Room 22.7

Decontamination Facility 5.6

Laundry 4.6

Change Rooms 1.7

Incinerator Facility 16.1

Subtotal 977.2

Piping, ductwork, trays & light fixtures 317.8

Total 1,295.0

Source: Elder and Blahnik 1981, Appendix A

Table A.18 Mass of structural steel in UF6 production facility buildings

Building Width (m) Length (m) Area (m2

) Mass (t) Cleared

fraction Mass (t)

Main Building 55 100 5,500 483.8 0.45217.7

Solvent Extraction Facility — — 377 33.2 14.9

Total 5,877 517 232.7

The reference facility is assumed to have a 12-in-thick (30.5-cm) reinforced concrete slab

basemat. The total floor area, as shown in Table A.18, is 5,877 m2 for a total volume of

1,791 m3

. The mass of the concrete is approximately 4,100 t.
Inventory of Materials Appendix A

NUREG-1640 A-28

Radioactivity

Table A.19 summarizes the surface activity levels of the equipment after decontamination. Postdecontamination levels on equipment are provided by Elder and Blahnik (1981, Appendix C);

equipment weights are provided in Appendix A of that document. The average activity was

calculated based on an average specific activity of 1.3 :Ci/g (48 kBq/g) (Elder and Blahnik

1981, Table 7.4-1).

Table A.19 Activity levels of equipment in UF6 production facility (piping not included)

Range (kg/t)a Average activity Mass (t) Percent kg/ta Bq/g

Clean — — 135.6 13.9%

0 – 0.1 4.63e-04 0.022 280.7b 28.7%

0.1 – 1.0 0.408 19.6 35.5 3.6%

1.0 – 10 3.76 181 442 45.2%

10 – 100 32.3 1,554 79 8.1%

100 – 1000 125 6,013 4.4 0.5%

Total 977.2 100.0%

a

 Kilograms of radioactive material per tonne of equipment 

b

 Assumed to be potentially cleared

A.3.2.2 Inventory Summary - UF6 Production Facilities

Mass of Steel

The mass of steel in the reference facility is 1,295 t in equipment (see Table A.17) and 517 t in

structural steel (see Table A.18). The equipment is assumed to be 13.9% clean, 28.7%

potentially cleared, and the balance radioactive (see Table A.19). There is no specific

information on the fraction of structural steel that would be subject to clearance. However, NRC

(1994, Table C.7.1.1) estimates that 45% of the wall area would have residual levels of

radioactivity. We therefore assume that 45% of the structural steel would be potentially cleared,

with the balance being clean. Any rebar in reinforced concrete is assumed to be clean and would

therefore not contribute to the mass of potentially cleared steel.

Mass of Concrete

The reference facility is estimated to contain approximately 4,100 t of concrete in the floor. One

half is assumed to be clean and one half potentially cleared (NRC 1994, Table C.7.1.1).

Mass of Copper and Aluminum

No data on the quantities or activity levels of copper or aluminum in UF6 production facilities

were located during the course of the present analysis. The quantities are expected to be small.
Appendix A Inventory of Materials

10 Metric Tons of Uranium

A-29 NUREG-1640

Mass of Material Potentially Cleared from Reference Facility

Steel: 232.7 t (Table A.18) + 280.7 t (Table A.19) ............................... ~513 t

Concrete: 4,100 × 0.5 ..................................................... 2,050 t

Scaling from Reference Facility

There are only two UF6 production facilities in the United States: the shut-down Sequoyah Fuels

Corporation facility, with a capacity of 5,000 MTU/y,10 and the Honeywell facility, with a

capacity of 14,000 MTU/y. The reference facility described by Elder and Blahnik (1981) has an

annual processing rate of 10,000 MTU/y. Since the combined capacities of the two facilities are

19,000 MTU/y, we apply a scaling factor of 1.9 (19,000 ÷ 10,000 = 1.9) to the reference facility

to estimate the mass of cleared materials from the two actual facilities.

A.3.3 Fuel Fabrication Facilities

Fabrication is the final step in the process used to produce uranium fuel. This process converts

enriched UF6 into a solid form of uranium suitable for use in a nuclear reactor. Fabrication of

reactor fuel consists of three basic steps: the chemical conversion of UF6 to UO2 powder; the

ceramic process that converts UO2 powder to pellets; and the mechanical process that loads the

fuel pellets into rods and constructs finished fuel assemblies.

Table A.20 lists the six uranium fuel fabrication facilities currently licensed to operate by the

NRC, plus one in decommissioning. This table lists the owner of each facility and its location,

current license expiration date, and processing capacity. As shown in the table, the licenses of

all fuel fabrication facilities are scheduled to expire by August 2013. 

Table A.20 Licensed uranium fuel fabrication facilities

Company Location Expires Capacity (t/y)

CE Nuclear Power, LLC Hematite, MO In decommissioning 450

Global Nuclear Fuel - America, L.L.C. Wilmington, NC June 2007 1200

Westinghouse Electric Company (BNFL) Columbia, SC November 2005 1150

Nuclear Fuel Services, Inc. Erwin, TN July 2009 Not provided

Framatome ANP Lynchburg, Inc. Lynchburg, VA August 2013 400

BWX Technologies Naval Nuclear Fuel Division Lynchburg, VA September 2005 Not provided

Framatome ANP Richland, Inc. Richland, WA November 2006 700
Inventory of Materials Appendix A

NUREG-1640 A-30

A.3.3.1 Reference Fuel Fabrication Facility

A reference fuel fabrication facility was analyzed as part of a series of studies of the technology

and costs of decommissioning nuclear facilities funded by the NRC in the late 1970s and early

1980s. A generic or reference design was selected for each facility studied. The reference

uranium fuel fabrication facility is based primarily on the Global Nuclear Fuel facility, as

described by Elder and Blahnik (1980).

Mass of Materials

Elder and Blahnik (1980) provide considerable information on the quantity of ferrous metals and

some information on concrete, but no specific information on the quantities of aluminum or

copper within the facility. Table A.21 lists the mass of steel contained in equipment within this

facility. This information is condensed from a series of tables prepared by Elder and Blahnik

(1980, Appendix A).

In addition to steel in equipment, structural steel is used in the construction of the facility. Table

A.22 gives an estimate of the mass of structural steel, based on building dimensions provided by

Elder and Blahnik (1980) and “Structural Steel Weights per S. F. of Floor Area” in R. S. Means

2000 (Section R051-220) for steel frame, one-story manufacturing buildings with a floor load of

18 lbs/ft2

 (88 kg/m2).

The reference facility is assumed to have a 12-in-thick (30.5-cm) reinforced concrete slab

basemat. The total floor area, as shown in Table A.22, is 19,475 m2, for a total volume of

approximately 5,940 m3

 and a mass of 14,256 t.

Radioactivity

Table A.23 summarizes the surface activity levels of the equipment after decontamination, as

reported by Elder and Blahnik (1980, Appendix C). Appendix A of that document lists the

weight of each piece of equipment. 

A.3.3.2 Inventory Summary – Fuel Fabrication Facilities

Mass of Steel

The mass of steel in the reference facility is 2,435 t in equipment (see Table A.21) and 1,713 t in

structural steel (see Table A.22). As shown in Table A.23, equipment that would be potentially

cleared would contain about 1,000 t. There is no specific information on the fraction of

structural steel that would be subject to clearance. However, NRC (1994, Table C.7.1.1)

estimates that 5% of the wall area would have residual levels of radioactivity. We therefore

assume that 5% of the structural steel would be potentially cleared, with the balance being clean. 

Any rebar in reinforced concrete is assumed to be clean and would therefore not contribute to the

mass of potentially cleared steel.
Appendix A Inventory of Materials

A-31 NUREG-1640

Table A.21 Mass of steel in fuel fabrication equipment

Area Weight (t)

Powder Warehouse 75.4

UF6 Cylinder Storage Room 97.0

UF6 Vaporization Room 107.4

Chemical Areas 294.6

Powder Storage & Feed Room 60.3

Pelletizing Room 49.7

Sintering Room 241.0

Grinding Room 50.7

Rodding Room 310.6

Gadolinia Rod Fabrication 26.4

Uranium Scrap Recovery Room 13.2

Chemical & Metallurgical Analytical Lab 18.7

Process Development Laboratory 67.6

Hot Machine Shop 23.2

Hot Instrument Shop 5.4

Radwaste Room 22.7

Decontamination Facility 5.9

Laundry Room 4.9

Change Room 1.7

Incinerator Facility 16.1

Fluoride Waste Effluent Treatment System 129.4

Nitrate Waste Effluent Treatment System 44.4

Waste Treatment Building 15.6

Excess Equipment Storage Yard 100.2

Radwaste Effluent Treatment System 8.4

Subtotal Equipment 1,790.5

Piping, Ductwork, Trays & Light Fixtures 644.9

Total 2,435.4

Table A.22 Mass of structural steel in buildings

Building Width (m) Length (m) Area

(m2

)

Mass (t)

Total Cleareda

Main Building 211.0 80.0 16,880 1,484.8 74.2

Uranium Scrap & Powder Storage Addition 47.0 27.0 1,269 111.6 5.6

Chemical Metallurgical Lab Addition 37.0 21.0 777 68.3 3.4

Fluoride Nitrate Waste Treatment Building 19.0 12.0 228 20.1 1.0

Incinerator Building 18.3 12.2 223 19.6 1.0

Boiler 14.0 7.0 98 8.6 0.4

Total 19,475 1,713.0 85.7

a

 Assumes 5% subject to clearance—see text
Inventory of Materials Appendix A

NUREG-1640 A-32

Table A.23 Activity levels on equipment in reference fuel fabrication facility

Range (kg/t)a Average activity Mass (t) Percent kg/ta Bq/g

Clean — — 1,137 46.7%

0 – 0.1 0.024 1.17 1,001b 41.1%

0.1 – 1.0 0.23 11.0 275 11.3%

1.0 – 10 1.80 86 19 0.8%

10 – 100 13.3 638 2 0.1%

Total 2,435 100.0%

a

 Kilograms of radioactive materials per tonne of equipment 

b

 Assumed to be potentially cleared

Mass of Concrete

The reference facility is estimated to contain 14,256 t of concrete in the floor. One half is

assumed to be clean and one half potentially cleared (NRC 1994, Table C.7.1.1).

Mass of Copper and Aluminum

No data on the quantities or activity levels of copper or aluminum in fuel fabrication facilities

were located during the course of the present analysis. 

Mass of Material Potentially Cleared from Reference Facility

Steel: 86 t (Table A.22) + 1001 t (Table A.23) .................................. 1,087 t

Concrete: 14,256 × 0.5 .................................................... 7,128 t

Scaling from Reference Facility

As shown in Table A.20, the capacities of the seven operating fuel fabrication facilities range

from 400 to 1,200 MTU/y. The reference facility described by Elder and Blahnik (1980) has a

capacity of 1,200 MTU/y. According to R. S. Means (2000, Section R17100-100, “Square Foot

Project Size Modifier”): 

One factor that affects the S. F. (square-foot) cost of a particular building is the size. In

general, for buildings built to the same specification in the same locality, the larger building

will have the lower S. F. cost. This is due mainly to the decreasing contribution of the

exterior walls plus the economy of scale usually achievable in larger buildings.

The source goes on to state that for facilities with a size factor (the actual facility size divided by

the reference facility size) of 0.50 or less, the S. F. cost multiplier is 1.1. 
Appendix A Inventory of Materials

A-33 NUREG-1640

Scaling from the reference fuel fabrication facility to specific facilities is based on the capacities

of each facility and includes the size multiplier:

Mi = mass of material in facility i

Mr = mass of material in reference facility

Ci = annual capacity of facility i

Cr = annual capacity of reference facility

= 1,200 MTU/y

fc = size multiplier

= 1.1 (Ci # 600 MTU/y)

= 1 (Ci > 600 MTU/y)

The scaling factor was applied to each of the seven facilities listed in Table A.20, as shown in

Table A.24. The two facilities for which annual capacities are not listed are assigned capacities

equal to the average of the other five facilities.

Table A.24 Scaling factors for uranium fuel fabrication facilities

Company Capacity (t/y) Size multiplier (fc) Scaling factor

CE Nuclear Power, LLC 450 1.1 0.413

Global Nuclear Fuel - America, LLC 1200 1 1.000

Westinghouse Electric Company (BNFL) 1150 1 0.958

Nuclear Fuel Services, Inc. 780 1 0.650

Framatome ANP Lynchburg, Inc. 400 1.1 0.367

BWX Technologies Naval Nuclear Fuel Division 780 1 0.650

Framatome ANP Richland, Inc. 700 1 0.583

Total 4.621

A.3.4 Uranium Enrichment Facilities 

According to NRC (2003b), the Agency regulates the two gaseous diffusion uranium enrichment

facilities, which are leased by the United States Enrichment Corporation from DOE. The two

facilities are located in Paducah, KY, and Portsmouth, OH. The Portsmouth plant ceased to

operate in March 2001—it is currently in cold standby and is not used for enrichment. Once the

plants are permanently shut down, control will revert back to DOE. The third U.S. gas diffusion

plant, the K-25 enrichment facility in Oak Ridge, TN, remains under DOE control. It has been

shut down and is undergoing decommissioning. Clearance of materials generated during

dismantlement will be regulated by DOE and is therefore not within the scope of the present

analysis. 
Inventory of Materials Appendix A

NUREG-1640 A-34

A.3.5 Spent Fuel Storage Facilities

An independent spent fuel storage installation (ISFSI) is a complex designed and constructed for

the interim storage of spent nuclear fuel. Table A.25 lists the dry spent fuel storage system

designs that have been approved by the NRC.

Table A.26 lists 19 dry spent fuel storage facilities in operation as of May 2002 (NRC 2002). 

There is also a single wet storage facility in Morris, Illinois, operated by the General Electric

Company. As of August 2003, the number of licensed facilities had increased to 28 (Keegan

2003). 

Table A.25 Spent fuel storage system designs

Vendor Storage design Model

General Nuclear Systems Metal cask CASTOR V/21

Westinghouse Electric Metal cask MC-10

NAC International, Inc Metal cask NAC S/T

NAC-C28 S/T

Transnuclear, Inc Metal cask TN-24

BNFL Fuel Solutions (Sierra Nuclear Corp) Metal–concrete cask VSC-24

Transnuclear West Concrete module NUHOMS-24P

NUHOMS-52B

Holtec International Metal cask HI-STAR 100

Holtec International Metal–concrete cask HI-STORM 100

Transnuclear Inc. Metal cask TN-32

NAC International Inc. Metal–concrete cask NAC-MPC

NAC International Inc. Metal–concrete cask NAC-UMS

Transnuclear Inc. Metal cask TN-68

BNFL Fuel Solutions Metal–concrete cask Fuel Solutions

Source: NRC 2000a, 2002

Spent fuel may be stored in either a wet or dry environment; the various techniques include:

• Concrete Casks

• Horizontal Storage Modules (HSM)

• Metal Casks

• Modular Vault Dry Storage (MVDS) 

• Pool (Wet) Storage

Ludwick and Moore (1984) developed five reference ISFSIs for the following designs:

• Silo – similar to the Concrete Casks design listed above

• Cask – similar to Metal Casks design listed above, except that these casks are stored indoors

• Vault – similar to MVDS system listed above

• Wet – same as Pool (Wet) Storage listed above
Appendix A Inventory of Materials

A-35 NUREG-1640

• Drywell — in-ground storage, not currently utilized

Table A.26 Licensed dry spent fuel storage facilities

Reactor name Utility Vendor Model No. casksa

Surry 1, 2 Virginia Electric & Power General Nuclear Systems

and others

TN-32, NAC-128, 

Castor V-21, X-33, MC-10 84b

H. B. Robinson 2 Carolina Power & Light Transnuclear West NUHOMS-7P 8c

Oconee 1, 2, 3 Duke Energy Company Transnuclear West NUHOMS-24P 87d

Fort St. Vrainb DOE FW Energy Applications MVDS single vault

Calvert Cliffs 1, 2 Calvert Cliffs Nuclear Transnuclear West NUHOMS-24P 120b

Palisades Consumers Energy BNFL Fuel Solutions VSC-24 18c

NUHOMS-32PT 1d

Prairie Island 1, 2 Nuclear Management Transnuclear West TN-40 17c

Point Beach 1, 2 Nuclear Management BNFL Fuel Solutions VSC-24 17d

Davis-Besse First Energy Nuclear Transnuclear West NUHOMS-24P 3c

Arkansas Nuclear 1, 2 Entergy Operations, Inc. BNFL Fuel Solutions VSC-24 24c

HI-STORM 100 20d

North Anna Virginia Electric & Power Transnuclear West TN-32 84b

Trojan Portland General 

Electric Corporation BNFL Fuel Solutions HI-STORM 100 (modified) 36b

TMI-2 Fuel Debris DOE Transnuclear West NUHOMS-12T 30b

Susquehanna Pennsylvania Power

& Light Transnuclear West NUHOMS-52B 26d

NUHOMS-61BT 10d

Peach Bottom 2, 3 Excelon Generating

Company Transnuclear Inc. TN-68 24d

Hatch 1, 2 Southern Nuclear

Operating Company Holtec International HI-STAR 100 3c

HI-STORM 100 15d

Dresden 1, 2, 3 Excelon Generating

Company Holtec International HI-STAR 100 4c

HI-STORM 100 18d

Rancho Seco Sacramento Municipal

Utility District Transnuclear West NUHOMS-24P 21b

McGuire Duke Power Transnuclear Inc. TN-32 10c

Sources: NRC 2002, Keegan 2003.

a Maximum likely number by end of life of facility

b Number approved

c Number loaded

d Number loaded + number planned, or estimate based on engineering judgement

The design of commercial ISFSIs has evolved greatly since 1984. Therefore, the present study

uses only selected information (e.g., wet facility data and some vault data) from Ludwick and

Moore (1984). Data for the other ISFSI designs are taken from vendor-prepared documents

(including Safety Analysis Reports, etc.) and other sources.
Inventory of Materials Appendix A

NUREG-1640 A-36

A.3.5.1 Concrete Casks

The ventilated storage cask system (VSC-24) developed by Sierra Nuclear Corporation (now

BNFL Solutions, Inc.) is a typical concrete cask design, which stores 24 PWR assemblies in a

vertical position. The principal components of the system are a steel multi-assembly sealed

basket (MSB), a ventilated concrete cask (VCC), and an MSB transfer cask (MTC). The

following discussion is based primarily on information presented by Raddatz and Waters (1996),

supplemented with information and data presented by BNFL (2000a, 2000b, 2000c, and 2000d). 

A diagram of the cask system is shown in Figure A.1. The principal components of the VSC-24

are listed in Table A.27.

The MSB consists of a steel cylindrical shell with a thick shield plug and steel cover plates

welded at each end. The shell length is fuel-specific and varies from 4.2 to 4.9 m, the outside

diameter is 1.6 m, and the shell thickness is 2.5 cm; the dimensions of the principal VSC-24

components are given in Table A.28. The internal steel basket consists of a welded structure

with 24 square storage locations. The basket aids in the insertion of the fuel assemblies,

enhances subcriticality during loading operations, and provides structural support during a

potential drop accident. The basket is coated with Carbozinc 11 for corrosion protection.

Table A.27 Mass of principal VSC-24 concrete cask components

Component Material Mass

lb t

VCC weather cover plate Steel 1,110 0.504

MSB structural lid Steel 2,384 1.082

MSB shielding lid – 2.5" plate Steel 2,003 0.909

MSB shielding lid – sandwich plate Steel 4,368 1.983

MSB – empty, w/o lids Steel 21,036 9.550

VCC – empty, w.o. cover plate

Steel liner 23,022 10.452

Concrete 173,720a 78.869

Rebar 8,133a 3.692

VCC total 204,875 93.013

MTC – empty, w.o. lid Steel 117,700 53.436

Basepad (per cask) Concrete 270,000a 122.580

Rebar 11,700a 5.312

Source: BNFL 2000a, Table 3.2-1

a Estimated for this study, based on component dimensions

The VCC is a reinforced-concrete cask in the shape of a hollow right circular cylinder. The cask

has four penetrations for air entry (located at the bottom) and four outlets located at the top. The

penetrations are protected from debris intrusion by wire mesh screens. The internal cavity of the

cask, as well as the inlets and outlets, are steel lined. After the MSB is inserted, a shield ring is

placed over the MSB–VCC gap and the cask weather cover is installed. The VCC height is

fuel-specific and varies from 5.0 to 5.7 m. The outer diameter is approximately 3.4 m, and the

walls consist of 74 cm-thick concrete and a 4.5 cm-thick steel liner.
Appendix A Inventory of Materials

A-37 NUREG-1640

Table A.28 Dimensions of principal components of VSC-24 concrete cask

Component Parameter Dimension

in cm

Ventilated Concrete Cask (VCC)

Outer diameter 132 335

Inner diameter 70.5 179

Concrete thickness 29 74

Height 197 – 225 500 – 572

Steel liner 1.75 4.45

Multi-Assembly Sealed Basket (MSB)

Outer diameter 62.5 159

Length 164 – 192 417 – 488

Thickness 1 2.5

Shield lid 9.5 24.1

Structural lid 3 7.6

MSB Transfer Cask (MTC) Not found

Basepad (per Cask)

Length 300a 762

Width 300a 762

Thickness 36a 91

Source: BNFL 2000a

a Estimated for this study

The MTC is a shielded lifting device with inner and outer structural steel cylinders, which house

lead and solid RX-277 neutron shield cylinders designed to reduce radiation from the fuel inside

the MSB–MTC. The MTC serves to transfer the MSB from the spent fuel pool (SFP) to the

VCC inside the fuel pool building. 

Figure A.1 VSC-24 concrete cask storage system (BNFL 2000b)
Inventory of Materials Appendix A

NUREG-1640 A-38

A.3.5.2 Horizontal Modular Storage (NUHOMS)

A popular version of a concrete ISFSI is the horizontal modular storage, or NUHOMS (NUtech

HOrizontal Modular Storage) system, developed by the Vectra Company (now Transnuclear

West Inc.) The standardized NUHOMS-24P/52B is designed to store either PWR or BWR

assemblies horizontally in a concrete structure, rather than vertically in a cask, as is the case with

the VSC-24. The principal components of the standardized NUHOMS are: (1) a stainless steel,

dry-shielded canister (DSC) with an internal fuel basket, (2) a concrete horizontal storage

module (HSM) that protects the DSC and provides radiation shielding (overpack), (3) a transfer

cask (TC) used to transfer the DSC from the spent fuel pool to the HSM, and (4) a hydraulic ram

system (HRS) used to insert the DSC into the HSM and TC. The following discussion is based

primarily on information presented by Raddatz and Waters (1996), supplemented with

information and data presented by TNW (2000). A diagram of the NUHOMS system is shown

in Figure A.2. The mass of principal NUHOMS components is listed in Table A.29. The

dimensions of these components are shown in Table A.30.

The DSC is designed to provide primary containment for 24 PWR or 52 BWR assemblies. The

DSC is a stainless steel cylinder approximately 4.7 m (186 in) long and 0.016 m (0.625 in) thick,

with an outside diameter of 1.7 m (67.25 in). Stainless steel end plates and steel end plugs filled

with lead are attached to both the top and bottom of the DSC with redundant seal welds. The

Figure A.2 NUHOMS spent fuel storage system (TNW 2000)
Appendix A Inventory of Materials

A-39 NUREG-1640

canister contains a basket assembly made of 24 or 52 stainless steel guide sleeves. The basket

geometry and guide sleeves provide criticality control. The basket assembly for BWR assembly

loading has additional neutron-absorbing plates. The lower end of the DSC is coated with a

lubricant to reduce friction when it is inserted and removed from the TC and HSM. 

Table A.29 Mass of principal NUHOMS components

Component Material

Mass

lb t

PWR BWR PWR BWR

DSC shell assembly Steel 15,778 15,658 7.157 7.102

DSC top shield plug Lead 7,859 7,621 3.565 3.457

DSC internal basket Steel 12,189 12,012 5.529 5.449

DSC top cover plates Steel 1,934 1,934 0.877 0.877

Horizontal storage module

(HSM)

Concretea 226,600 234,900 102.786 106.551

Rebara 9,852 10,213 4.469 4.633

Structural steela 6,548 6,887 2.970 3.124

HSM total 243,000 252,000 110.225 114.307

Transfer cask (TC) w. collar 

Steela 74,031 80,441 33.580 36.488

Leada 33,060 33,060 14.996 14.996

TC Total 107,091 113,501 48.576 51.484

Basepad Concretea 77,100 80,500 34.973 36.515

Rebara 3,352 3,500 1.521 1.588

Source: TNW 2000, Tables 8.1-4 & 8.1-5

a

 Estimated for this study

The HSM is constructed of reinforced concrete, structural steel, and stainless steel. The HSM

may be constructed as a single unit or as an array of modules (e.g., 2 × 20). A standardized

HSM is approximately 5.8 m long, 4.6 m high, and 2.9 m wide. The concrete walls and roof are

about 90 cm thick, and interior walls are about 45 cm thick. The outside wall at the end of a row

of HSMs has a thickness of about 60 cm. The HSM structure provides gamma and neutron

shielding.

A steel support rail structure anchored by the walls inside the HSM supports the DSC and

extends to the access opening. Stoppers on the rails prevent horizontal movement of the DSC

during a seismic event. A vertically sliding plate, consisting of thick steel and a neutronabsorbing material, covers the entrance to the HSM and is tack-welded closed once the DSC is in

place. Each HSM has two shielded air inlets on the front and two shielded air outlets on the

roof.

The TC is used to transfer the DSC from the SFP to the HSM. The TC is approximately 5.2 m

long with an inner diameter of 1.7 m. The length can be extended to accommodate BWR

assemblies. It consists of three concentric cylinders with shielding material in between,

connected by top and integral end plates. The top and bottom end plates are made of steel and a

solid neutron shield. The bottom end plate has a removable HRS access-port plug. The TC wall
Inventory of Materials Appendix A

NUREG-1640 A-40

consists of an inner stainless steel liner, a poured-lead shield, a structural carbon steel shell, a

solid BISCO-N3 neutron shield, and an outer carbon steel shell. It is hoisted by the trunnions

located on its sides, and mates (via the transfer trailer) with the access opening of the HSM for

transfer of the DSC. 

Table A.30 Dimensions of principal components of NUHOMS system

Component Parameter Dimensions

in cm

DSC Shell Assembly

Outer diameter 67.25 171

Thickness 0.625 1.59

Overall length PWR 186 472

BWR 196 498

Length cavity PWR 167 424

BWR 177 450

Horizontal Storage Module

Height 180 457

Width 116 295

Length PWR 228 579

BWR 238 605

Thickness

Front 30 76

Side 18 46

Rear 12 30

Floor 12 30

End 24 61

Transfer Cask w. collar

Overall length 205.5 522

Length cavity 186.75 474

Outer diameter 85.25 217

Inner diameter 68 173

Thickness

Stainless steel 0.5 1.27

Lead 3.5 8.89

Carbon steel 1.5 3.81

BISCO-N3 3 7.62

Carbon steel 0.125 0.318

Basepad

Width 116 295

Length PWR 228 579

BWR 238 605

Thickness 36 91

Source: TNW 2000

A.3.5.3 Metal Casks

Metal cask ISFSI designs are available from a number of vendors. The CASTOR system,

developed by General Nuclear Systems, Inc. (now a division of Gesellschaft für NuklearBehälter, mbH [GNB]), is selected as the reference design for this study. The following
Appendix A Inventory of Materials

A-41 NUREG-1640

discussion is based primarily on information presented by Raddatz and Waters (1996),

supplemented with information and data presented by GNB (2000). 

The mass of each principal CASTOR component is listed in Table A.31. The total mass of the

cask and basket is approximately 96.5 t, not including the fuel.

Table A.31 Principal CASTOR metal cask components

Component Material Mass

lb t

Cask Steel 180,557 81.901

Basket Steel 32,052 14.539

Basepad (per cask) Concretea 110,592 50.165

Rebara 4,792 2.174

Source: GNB 2000

a Estimated for this study, based on data from VEPCO 2000

The CASTOR X/32 is designed to store 32 PWR assemblies in a vertical position. The cask is

approximately 4.8 m high and 2.3 m in outside diameter. The dimensions of the principal

components of the CASTOR metal cask are listed in Table A.32. 

Table A.32 Dimensions of principal components of CASTOR metal cask

Component Material Parameter Dimensions

in cm

Cask body Carbon steel

Overall length 190.9 485

Cavity length 163.6 416

Outside diameter 91.6 233

Inside diameter 68.1 173

Wall thickness 11.8 30

Bottom thickness 7 18

Primary lid

Stainless steel

Thickness 10.2 26

Secondary lid Thickness 3.15 8.0

Bottom plate Thickness 1.38 3.5

Moderator rod — Thickness 2.76 7.0

Source: GNB 2000

The cask body consists of a ductile cast iron material with a thickness of 30 cm. The top of the

cask is sealed with two stainless steel lids bolted onto the cask, using both metallic and

elastomeric O-ring seals. The primary and secondary lids are 26 cm and 8 cm thick,

respectively. Gamma shielding is provided by the wall of the cask, and neutron shielding is

provided by a single row of polyethylene rods incorporated into the cask wall. The inside of the

cask and sealing surfaces have a nickel coating for corrosion protection. The internal cavity is

filled with helium for heat transfer and corrosion protection. An epoxy resin coating protects the

outside surface of the cask. Four trunnions are connected to the cask body for lifting and
Inventory of Materials Appendix A

NUREG-1640 A-42

rotating the cask. The inside of the cask contains a fuel basket structure comprising 32 square

tubes of welded stainless steel, and borated stainless steel plates for criticality control. 

A.3.5.4 Modular Vault Dry Store

The Modular Vault Dry Store (MVDS) system, built by Foster Wheeler Energy Applications,

Inc., is a concrete vault ISFSI designed to store (in a vertical position) 1,482 high-temperature

gas-cooled (HTGC) spent fuel elements, 37 reflector elements, and 6 neutron source elements

from the Fort St. Vrain power station, which has been decommissioned. A diagram of the

MVDS system is shown in Figure A.3. 

The MVDS system consists of a foundation structure supporting a matrix of six concrete vault

modules (VMs), one neutron source storage well, two standby storage wells, six charge face

structures (CFSs) forming the roofs over the VMs, and a transfer cask reception bay, with a steel

canopy above the structure (Raddatz and Waters 1996). Overall dimensions of the MVDS

facility are 44 m long, 22 m wide, and 25 m high. Based on these dimensions and an assumed

thickness of the walls and floor of 1.2 m, the concrete in the MVDS is estimated to have a

volume of 5,125 m3

 and a mass of about 11,800 t.

Figure A.3 Modular vault dry storage facility (Raddatz and Waters 1996)
Appendix A Inventory of Materials

A-43 NUREG-1640

Figure A.4 Pool (wet) storage facility (GE Nuclear Energy 2000)

A.3.5.5 Pool (Wet) Storage

The only ISFSI to utilize pool or wet storage is General Electric’s Morris Operations (GEMO). 

The GEMO facility was constructed in the late 1960s as a fuel reprocessing plant, but it never

operated as such. For the last 18 years, the GEMO has functioned as an ISFSI under NRC

license. 
Inventory of Materials Appendix A

NUREG-1640 A-44

The main building at GEMO is a massive structure of reinforced concrete, about 62 m by 24 m,

and about 27 m above grade. The western end of the building houses most of the fuel storage

facilities. This portion of the building is of steel frame and insulated metal siding construction

and is attached to the concrete main building. Fuel storage operation areas include:

• Cask receiving area.

• Decontamination area.

• Cask unloading basin.

• Fuel storage basins (illustrated in Figure A.4):

– Basin 1 has an area of about 84 m2

– Basin 2 has an area of about 139 m2

• Low-level waste evaporator

• Central Alarm Station–Secondary Alarm Station

• Basin water cleanup and cooling system

Fuel bundles are stored in stainless steel basket assemblies designed to protect fuel from physical

damage and to maintain fuel in a subcritical configuration. Baskets are locked into grids in the

fuel basins to provide seismic restraint. The basins are constructed below ground with stainless

steel lined, reinforced concrete walls about 60 cm thick poured in contact with the sides of a

bedrock excavation. The south wall of the basin is about 1.2 m thick, because it was intended to

stand independent of the surrounding rock to facilitate possible future expansion. Storage basin

floors were poured on bedrock and range in thickness from 76 to 140 cm. 

The pool storage area is estimated to contain approximately 840 m3

 of concrete, with a mass of

approximately 1,940 t. The entire Main Building (including those portions intended for fuel

reprocessing) would contain substantially more concrete.

A.3.5.6 Inventory Summary—Spent Fuel Storage Facilities

Steel

The only steel in the spent fuel storage facilities discussed in the preceding sections that would

be a likely candidate for clearance is the structural steel in the NUHOMS. All other steel would

be either neutron-activated or have high levels of surficial activity, or would be clean material

such as rebar. As shown in Table A.29, a NUHOMS used to store PWR fuel contains 3 t of

structural steel, while a corresponding BWR module contains 3.1 t.
Appendix A Inventory of Materials

11 Due to the nature of the facility designs, the concrete in the basepad of the NUHOMS is assumed to be clean. 

A-45 NUREG-1640

Concrete

The mass of concrete that could be potentially cleared from each of the five types of spent fuel

storage facilities discussed in the preceding sections is listed below.

1. Concrete cask – basepad . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 t

2. NUHOMS11 – horizontal storage module

a. PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 t

b. BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 107 t

3. Metal cask – basepad . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 t

4. MVDS – entire facility ................................................ 11,800 t

5. Wet storage – pool storage area ........................................... 1,940 t

Copper and Aluminum

No data on copper or aluminum in spent fuel storage facilities were found during the course of

the present study. The quantities of these metals in the five types of facilities discussed in the

preceding sections is judged to be small in comparison to the quantities of steel and concrete.

Scaling from Reference Facility

For concrete casks, NUHOMS, and metal casks, the total mass of material is scaled, based on the

number of approved casks of each type at each storage facility (see Table A.26). For modular

vault dry storage and pool (wet) storage, the scaling factor is unity, there being only one of each

such type of facility.

A.4 Non-Power Reactors

Non-power reactors (NPR) are of many forms, most being either pool or tank reactors. Pool

reactors have a core immersed in an open pool of water. The pools typically provide about 20 ft

(6 m) of water above the core to allow cooling and radiation shielding. At pool reactors, the

operating core and fuel can be observed through the pool water. The core of a tank reactor is in

a water-filled tank that is sealed at the top. 

Non-power reactors are also categorized by fuel type: plate fuel, TRIGA (Training, Research,

Isotopes, General Atomics), or AGN (Aerojet General Nucleonics). Plate fuel consists of several

thin plates containing a uranium mixture clad with aluminum formed into an assembly. This

geometry promotes efficient heat removal and the ability to provide a high neutron density. 
Inventory of Materials Appendix A

NUREG-1640 A-46

TRIGA fuel is in the shape of rods and consists of a uranium and zirconium hydride mixture. 

AGNs are compact, self-contained, low-power (< 5 watts) tank-type reactors. The 10-in (25-cm)

diameter core consists of uranium oxide powder embedded in a polyethylene moderator.

Table A.33 lists the currently licensed non-power reactors. 

A.4.1 Reference Non-Power Reactor

A research reactor is defined in 10 CFR 170.3 as a reactor licensed for operation at a thermal

power level of 10 MW or less, and which is not a testing facility. All but two of the reactors

listed in Table A.33 are licensed as research reactors, the exceptions being the low-power critical

experiment facility at Rensselaer Polytechnic and the 20 MW reactor at NIST. Consequently,

the reference NPR for the present analysis is based on the reference research reactor described

by Konzek et al. (1982), which in turn is based on the Oregon State University (OSU) 1,100 kW

TRIGA reactor.

Summary data on the structural materials, including concrete, structural steel, and rebar used in

the reference research reactor are presented by Konzek et al. (1982, Table B.2-1) and are listed

in Table A.34.

Additional information characterizing a reference research reactor is provided by NRC (1994),

which also uses the OSU reactor as a reference facility. NRC (1994, Table 7.1.1) estimates that

10% of the floor surface area and 2% of the wall surface area would be have some residual

radioactivity.

A.4.2 Scaling Factors for Non-Power Reactors

As is the case with commercial nuclear power reactors, scaling factors are developed for nonpower reactors to estimate the amount of material that would be generated during dismantlement. 

These scaling factors are based on data presented by Konzek et al. (1983) on the quantity of

waste generated during the decommissioning of four non-power reactors, summarized in Table

A.35.

The mass of waste listed in Table A.35 is plotted against the power level of each reactor in

Figure A.5. A regression analysis was used to fit the following power function to these data:

Miw = mass of waste generated during decommissioning of non-power reactor i (t) 

Pi = power level of reactor i (kW) 
Appendix A Inventory of Materials

A-47 NUREG-1640

Table A.33 Licensed non-power reactors

Facility name Location Power (kw) Typea fs 

b

Pool non-power reactors – with plate-type fuel

Ohio State University Columbus, OH 500 LW Mod 0.43

Purdue University West Lafayette, IN 1 LW Mod Lockheed 5e-04

Rhode Island Nuclear Science Center Narragansett, RI 2,000 LW Mod GE 1.91

University of Massachusetts Lowell, MA 1,000 LW Mod GE 0.9

University of Michigan - Ford Reactor Ann Arbor, MI 2,000 LW Mod 1.91

University of Missouri Rolla, MO 200 LW Mod 0.16

Worcester Polytechnic Institute Worcester, MA 10 LW Mod GE 0.006

Pool non-power reactors – with TRIGA fuel

Aerotest Operations Inc. San Ramon, CA 250 Conversion (Indus) 0.20

Armed Forces Radiobiological

Research Institute Bethesda, MD 1,100 + pulse Mark F 1.0

Cornell University Ithaca, NY 500 + pulse Mark II 0.43

Dow Chemical Company Midland, MI 300 Mark I 0.25

Kansas State University Manhattan, KS 250 + pulse Mark II 0.2

Oregon State University Corvallis, OR 1,100 + pulse Mark II 1.0

Pennsylvania State University University Park, PA 1,000 + pulse Conversion Mark II 0.9

Reed College Portland, OR 250 Mark I 0.2

Texas A&M College Station, TX 1,000 + pulse Conversion 0.9

U.S. Geological Survey Denver, CO 1,000 + pulse Mark I 0.9

U.S. Veterans Administration Omaha, NE 18 Mark I 0.012

University of Arizona Tucson, AZ 100 Mark I 0.075

McClellan Nuclear Radiation Center

University of California-Davis Sacramento, CA 2,000 + pulse Mark II 1.91

University of California Irvine, CA 250 Mark I 0.2

University of Maryland College Park, MD 250 Modified 0.2

University of Texas Austin, TX 1,100 + pulse Mark II 1.0

University of Utah Salt Lake City, UT 100 Mark I 0.1

University of Wisconsin Madison, WI 1,000 + pulse Conversion 0.9

Washington State University Pullman, WA 1,000 + pulse Conversion 0.9

PULSTAR (uranium dioxide pellets, zircalloy clad) fueled

North Carolina State University Raleigh, NC 1,000 — 0.9

Critical experiment facility — with uranium dioxide, stainless steel clad fuel

Rensselaer Polytechnic Institute Schenectady, NY 0.1 LW Mod 4e-05

Tank non-power reactors — plate-type fuel

General Electric Company Sunol, CA 100 Graphite Mod 0.075

Massachusetts Institute of Technology Boston, MA 4,900 LW Mod, HW Reflec 5.03

National Institute of Standards and Technology Gaithersburg, MD 20,000 Heavy Water 23

University of Florida Gainesville, FL 100 Argonaut 0.1

University of Missouri Columbia, MO 10,000 LW Mod & Cooled 10.9

Tank non-power reactors — AGNs

Idaho State University Pocatello, ID 0 AGN-201 #103 0

Texas A&M University College Station, TX 0.005 AGN-201 #106 2e-06

University of New Mexico Albuquerque, NM 0 AGN-201M #112 0

Total 56.5

a LW Mod: light-water moderated; HW Mod: heavy-water moderated; HW Reflec: heavy-water reflected

b Scaling factor—see text
Inventory of Materials Appendix A

NUREG-1640 A-48

Table A.34 Estimated quantities of structural material in reference NPR

Structure Concrete (m3

) Rebar (t) Structural steel (t)

Reactor Building 509 41.9 16.8

Reactor Structure 235 38.6 2.7

Radiation Center Annex 59 4.8 4.0

HX Addition 26 2.1 1.5

Pump House 8 0.6 0.2

Total 840 88.0 25.2

Source: Konzek et al. 1982, Table B.2-1

Table A.35 Waste generated during decommissioning of non-power reactors

Facility Type Power (kW) Mass (t)

Ames Laboratory Research Reactor Tank – MTR – D2O 5,000 1,224

Diamond Ordnance Radiation Facility Pool – TRIGA 250 27

Lynchburg Pool Reactor Pool – MTR 200 14

North Carolina State University Reactor-3 Pool – MTR 10 1.5

This power function, shown in Figure A.5 as a solid straight line, is an excellent fit to the data,

with a correlation coefficient, R2

 = 0.97. This function forms the basis of a scaling factor that is

Figure A.5 Mass of decommissioning radwaste generated from non-power reactors
Appendix A Inventory of Materials

A-49 NUREG-1640

used to estimate the mass of material that would be generated during the dismantlement of an

NPR with a given power rating:

Mi

 = mass of material generated during decommissioning of non-power reactor i

Mr = mass of material generated during decommissioning of reference NPR 

Pr = power level of reference NPR

= 1,100 kW

The quantity is the scaling factor for non-power reactor i . Scaling factors for each of

the 36 operating NPRs are listed in Table A.33.

A.4.3 Inventory Summary—Non-Power Reactors

Mass of Steel

Table A.34 gives the mass of structural steel in the reference NPR as 25.2 t. As noted in Section

A.4.1, 2% of the wall surfaces of the reference NPR would be have residual levels of

radioactivity. This value is adopted as the fraction of structural steel that would be subject to

clearance in the present analysis, resulting in 504 kg of steel that would be potentially cleared.

Mass of Concrete

The volume of concrete in the reference NPR is 840 m3

, as listed in Table A.34; the mass is

estimated to be 1,925 t. As noted in Section A.4.1, 10% of the floor of the reference NPR would

have residual levels of radioactivity. This value is adopted as the fraction of concrete that would

be subject to clearance in the present analysis, resulting in 192.5 t of concrete that would be

potentially cleared.

Mass of Copper and Aluminum

No data were found during the course of the present study on copper or aluminum in non-power

reactors that would enable an estimate of the quantities of these metals that would be subject to

clearance. The amounts of these metals in NPRs are judged to be small in comparison to the

amounts of steel and concrete.

Scaling from Reference Facility

Section A.4.2 describes the approach developed for scaling the materials inventory of the

reference NPR to other non-power reactors. This scaling approach is based on the quantities of
Inventory of Materials Appendix A

12 Jean-Claude Dehmel, U.S. NRC Office of Regulatory Research, private communication with Robert Anigstein,

SC&A, Inc., May 24, 2004.

13 Ken Miller, Hershey Medical Center, private communication with John Mauro, SC&A, Inc., February 27, 2001.

NUREG-1640 A-50

waste generated during the actual decommissioning of four non-power reactors, ranging in size

from 10 to 5,000 kW.

A.5 Non-Fuel-Cycle Facilities

This section addresses the materials that may be candidates for clearance during routine

operations and during decontamination and decommissioning in support of license termination of

NRC and Agreement State non-fuel-cycle facilities. 

NRC (2003b) lists a total of 21,422 materials licenses in the United States. Of these, 4,797 are

NRC licenses while 16,625 are administered by Agreement States. NRC (2000c, Appendix G)

assigns program codes to all NRC licenses. Program codes in the 2000 series are assigned to

medical uses of radioactive materials. According to the NRC License Tracking System, the

2000 series comprises a total of 1,735 active licenses. Of these, 706 are held by medical

institutions, while 916 are medical private practice licenses.12 The medical field thus accounts

for about 35% of the materials licenses.

Although fewer in number, the medical institutions, due to their larger size, are judged to

account for the bulk of materials that would be potentially cleared from all medical licensees. 

The reference facility selected for the present analysis is based on information obtained during a

visit by SC&A personnel to the Milton S. Hershey Medical Center in Harrisburg, PA. 

The first step in the assessment was to estimate the total amount of material, equipment,

furniture, etc., that is at play at a typical large research and university hospital, in this case the

Hershey Medical Center (HMC). The term “at play” refers to material that is under regulatory

control at any given time and that may be cleared per year. The quantity of material at play was

determined by estimating the number of rooms under regulatory control at any given time, the

number cleared per year, and the inventory of material in these rooms. 

About 250 rooms are under regulatory control at Hershey Medical Center at any particular time,

and 6 to 12 of these are cleared each year. The steel components that would be scrapped and

potentially cleared from one room are:13

• 1 sink and drain, estimated weight = 50 lb (~23 kg)

• 20 m of sheet metal ductwork, estimated weight = 100 lb (~45 kg)

Assuming that an average of nine rooms are cleared each year, 1,350 lb (612 kg) of steel scrap

would be generated. (There would be little or no concrete, copper, or aluminum.)
Appendix A Inventory of Materials

A-51 NUREG-1640

Due to the large size of this facility, it would be inappropriate to simply multiply the annual

amount of cleared material by the total number of medical licensees. However, an approximate

measure of the size of an institution is the number of its employees. Hershey Medical Center has

about 5,100 employees. According to the Bureau of the Census (2004), U.S. hospitals had

5,165,228 paid employees in 2002. In the absence of more specific information, we use a

scaling factor of 1,000 to estimate the total amount steel scrap that would be potentially cleared

from U.S. hospitals. Based on this information, approximately 600 t per year would be

potentially cleared. Over the 50-year period during which other major nuclear facilities, notably

nuclear power plants, would be dismantled, hospitals could clear 30 kt of steel scrap. 

A.6 Estimates of Mass-to-Surface Area Ratios

As stated in Section 1.1 of the main report, the surficial normalized doses—doses normalized to

areal activity concentrations—are calculated by dividing the mass-based doses by the mass-tosurface ratio of each of the four materials addressed in the present analysis. 

A.6.1 Ferrous Metals

As stated in Section 3.8.1 of the main report, the mass-to-surface ratios of the various steel

components of nuclear power reactors are analyzed in order to create a frequency distribution

that is used in calculating surficial normalized doses. This analysis addresses three general types

of components—rebar, structural steel, and pipe hangers—that are judged to be likely candidates

for clearance. The total mass of rebar and structural steel in the reference BWR is listed in Table

A.2; the mass of BWR pipe hangers is listed in Table A.3. Corresponding data for a reference

PWR is provided by UE&C (1972). These data are listed in Table A.36. 

Table A.36 Ferrous metal components used in mass-to-surface ratio analysis

Component or system

BWR PWR

Mass (t) Fraction Mass (t) Fraction

Rebar 18,351 80.69% 9,592 58.37%

Structural steel 3,307 14.54% 5,862 35.67%

Pipe hangers 1,085 4.77% 980 5.96%

Total 22,743 100.00% 16,434 100.00%

A.6.1.1 Reinforcing Steel (Rebar)

Reinforcing steel bar (rebar) is supplied in 11 standard sizes (R. S. Means 2000). Each size bar

is given a designator based on its diameter. In English units, the designator is the diameter in

units of c inch—for example, a #3 bar would be d or 0.375 inches in diameter, while a #8 bar

would be 1 inch in diameter. For the larger diameter bars, this match between c in and its

designator is not exact—e.g., #14 bar has a diameter of only 1.693 in, instead of 1.75 in. The

metric designators are based on the approximate bar diameter in millimeters. 
Inventory of Materials Appendix A

NUREG-1640 A-52

No data were found during the course of the present study that would enable us to quantify the

amount of each size of rebar used in construction of a nuclear power plant. However, anecdotal

evidence leads to the conclusion that nuclear plants utilize virtually the entire spectrum of rebar

sizes.

• Both PWRs (Konzek et al. 1995a, Section 6.6.2) and BWRs (Smith et al. 1994b, Section

H.6.1) utilize #18 rebar to reinforce their biological shield walls.

• Openings were cut in the containment walls of the R. E. Ginna, Byron, and Palisades plants

during steam generator replacement. These cuts were through three layers of #18 rebar

(Bluegrass n/d, Concut n/d).

• Decommissioning cost studies specify unit cost factors for the removal of concrete heavily

reinforced with #9 and #18 rebar (TLG Services, Inc. 1999b).

• The Korean Peninsula Energy Development Organization issued a procurement package for

Quality Class Q #14 and #18 reinforcing steel bars (KEDO 2000).

• Braverman (2001, Section 7.2.1) describes a “shear wall typical of those found in NPPs

[nuclear power plants]” with “reinforcement consisting of #5 bars spaced at 8.5 in (21.6 cm)

at each face in each direction.” Braverman (2001,Table 8.1) presents crack acceptance limits

for #4, #5, #6, #7, #8 and >#9 rebar.

• The D. C. Cook containment sub-compartment walls have #9 rebar on 12-inch centers

(vertical) and #11 rebar on 6- or 12-inch centers (horizontal) (NRC 2000d).

• The reactor building for the K Production Reactor at the Savannah River Site contains #11

rebar in its base mat, and #8 and #11 rebar in its walls (WSRC 1991).

In the absence of more specific data, we assume that the rebar in a reference BWR or PWR is

evenly distributed among the 11 common rebar sizes listed in Table A.37; thus, the total mass of

rebar of any one size is equal to of the total mass of rebar in a given nuclear plant.

A.6.1.2 Structural Steel

Structural steel in an array of sizes is used throughout nuclear power plants. Steel I-beams are

available in a wide variety of configurations, ranging from 4 × 13 [depth (in) by

linear weight (lbs/ft)] to 24 × 104 and 30 × 99 for wide (W) beams, and 3 × 5.7 to 24

× 106 for standard (S) beams. Weights and dimensions for 137 I-beam sizes—110

W-beams and 27 S-beams—are listed on the on-line catalog of the South St. Paul

Steel Supply Co., Inc. (2004). A schematic diagram of an I-beam is shown on the

right. The flanges that form the top and bottom parts of the I-beam are connected by

the web—the vertical part, as shown in the diagram.
Appendix A Inventory of Materials

14 The thickness of clamps for several of the smaller pipe sizes are specified in terms of gauges. Different sheet

metal and wire gauges are employed by different U.S. industries. We made the simplifying assumption that the thickness

in inches is the reciprocal of the gauge number.

A-53 NUREG-1640

Table A.37 Reinforcing steel (rebar)

Designator Diameter Crosssection

Area per

linear ft

Weight per

linear ft Mass-to-surface

English Metric in in2 ft2 lb/ft lb/ft2 g/cm2

#3 10 0.375 0.11 0.098 0.376 3.83 1.87

#4 13 0.5 0.196 0.131 0.668 5.1 2.49

#5 16 0.625 0.307 0.164 1.043 6.38 3.12

#6 19 0.75 0.442 0.196 1.502 7.65 3.74

#7 22 0.875 0.601 0.229 2.045 8.93 4.36

#8 25 1 0.785 0.262 2.67 10.2 4.98

#9 29 1.128 0.999 0.295 3.398 11.51 5.62

#10 32 1.27 1.267 0.332 4.307 12.95 6.33

#11 36 1.41 1.561 0.369 5.309 14.38 7.03

#14 43 1.693 2.251 0.443 7.654 17.27 8.44

#18 57 2.257 4.001 0.591 13.603 23.02 11.25

Source: R. S. Means 2000

As in the case of rebar, we assume that the total mass of structural steel in the reference BWR

and reference PWR is evenly distributed over these 137 I-beam sizes. Not all surfaces of the

I-beam would have the same potential exposure to residually radioactive materials. In the

simplified model used in the present analysis, the effective mass-to-surface ratio is based on the

thickness of the top and bottom flange (dimension “D” in the above diagram) and the assumption

that only the top and bottom surfaces (adjacent to the letters “B” and “C” in the diagram) would

have been exposed. In effect, the I-beam is treated as a plate with thickness “D” and with only

one surface exposed to residually radioactive materials. The thickness of the flange ranges from

0.205 to 1.25 inches (0.521 – 3.175 cm); the range of the resulting mass-to-surface ratios is 4.08

to 24.9 g/cm2

. The entire mass of the I-beam is included in the inventory of potentially cleared

materials.

A.6.1.3 Pipe Hangers

Large numbers of hangers are used to support piping in a nuclear power plant. A typical pipe

hanger consists of two main parts: a wall brace and a pipe clamp. Table A.38 presents data on

the thickness of the material used in pipe clamps for hangers capable of handling a range of pipe

sizes.

Detailed data on pipe hangers in the reference PWR are listed in Table A.39. Each size of PWR

pipe hanger is assigned the same thickness and mass-to-surface ratio as the corresponding pipe

clamp listed in Table A.38, assuming that the heaviest (i.e., thickest) clamps available for each

pipe size are used in nuclear power plant service.14 The mass-to-surface ratio is based on the
Inventory of Materials Appendix A

NUREG-1640 A-54

assumption that any residual radioactive materials would be present on only one surface of the

hanger. For the reference BWR, Bierschbach (1996) classifies pipe hangers only as being

“small” or “large” (see Table A.3). Since this information is insufficient for estimating a

distribution of mass-to-surface ratios, the BWR pipe hangers are assigned the same frequency

distribution as those in the reference PWR.

Table A.38 Typical pipe clamp data

Nominal pipe

 size (in)

Standard Heavy duty Double bolt

Thicknessa Mass (lb) Thicknessa Weight Thicknessa Weight

 1⁄2 11 ga 0.31 — — — —

 3⁄4 11 ga 0.35 — — — —

1 11 ga 0.39 — — — —

1 1⁄4 11 ga 0.4 — — — —

1 1⁄2 11 ga 0.45 — — — —

2 3 ga 1.23 — — — —

2 1⁄2 3 ga 1.33 — — — —

3 3 ga 1.53 d 4.96 — —

3 1⁄2 3 ga 1.68 d 5.36 — —

4 3 ga 1.86 d 5.74 — —

5 3 ga 2.13 d 7.13 — —

6 d 5.06 1⁄2 13.48 d 14.14

8 d 6.08 1⁄2 15.78 1⁄2 20.99

10 1⁄2 12.81 e 24.2 1⁄2 33.71

12 1⁄2 13.08 3⁄4 41.54 e 48.17

14 1⁄2 16.7 3⁄4 53.25 3⁄4 70.5

16 1⁄2 23.19 3⁄4 56.35 3⁄4 93.9

18 e 33.12 3⁄4 70.12 1 123.72

20 e 38.66 3⁄4 74.68 1 156.43

24 e 52.27 3⁄4 126.29 1 204.65

30 3⁄4 105.13 — — — —

Source: PHD Manufacturing, Inc. (n/d)

a

 thickness in inches unless otherwise stated

b

 sheet metal gauge

A.6.1.4 Miscellaneous Equipment

Miscellaneous equipment is not included in the frequency distribution of mass-to-surface ratios

because the necessary data on such equipment were not found in the course of the present study.
Appendix A Inventory of Materials

A-55 NUREG-1640

Table A.39 PWR pipe hanger data

Nominal pipe

size (in) Numbera Massb Total

mass (kg)

Thicknessc Ratio

(g/cm2 lb ) a kg in cm

1 4,920 82 37 183,000 0.09 0.23 1.81

2 2,962 123 56 165,258

3 1,554 164 74 115,603 0.33 0.84 6.64

4 1,172 205 93 108,982

6 452 288 131 59,048 0.50 1.27 9.96

8 1,002 370 168 168,168

10 246 453 205 50,548 0.63 1.59 12.40

12 134 535 243 32,519 0.75 1.91 14.90

14 236 618 280 66,157

18 19 783 355 6,748

1.00 2.54 19.90 20 3 865 392 1,177

24 80 1,030 467 37,377

28 32 1,195 542 17,346

a

 Konzek et al. 1995a, Table C.5; Bierschbach 1995, Table A.1

b

 Each hanger

c

 From Table A.38 (see text)

A.6.1.5 Mass-to-Surface Ratios of Ferrous Metals

As discussed in the previous sections, the bulk of ferrous metals that would be cleared from a

commercial nuclear power plant is assumed to comprise 11 sizes of rebar, 137 sizes of I-beams,

and 6 thicknesses of pipe hangers, for a total of 153 discrete categories. Since the dismantlement

of such a plant is assumed to span 1.7 years, an average of = 0.5882 of the material would be

cleared during any 1-year period of this 1.7-year time span. However, due to the nature of the

dismantlement activities, it is not likely that all of the items in the 153 categories would be

cleared at a uniform rate. The fraction of each category that would be cleared in 1 year is

represented by a triangular probability distribution with a range of 0 – 1 and a mean

(expectation) value of 0.5882. This distribution was applied separately to each of the 153

categories in a Monte Carlo simulation involving 10,000 realizations. An overall mass-tosurface ratio for cleared ferrous metals was calculated in each realization by taking the total mass

of materials cleared in a given 1-year period divided by the total surface area of these materials:

= average mass-to-surface ratio of carbon steel components likely to be cleared from a

BWR or PWR in a given 1-year period (g/cm2)

ej = fraction of components in category j cleared in given 1-year period
Inventory of Materials Appendix A

NUREG-1640 A-56

mj = total mass of components in category j (g)

aj = total exposed surface area of components in category j (cm2)

These 10,000 individual values for each type of reactor—PWR and BWR—were utilized in the

probabilistic analyses of individual exposure scenarios to convert the mass-based normalized

doses to surficial normalized doses, as discussed in Section 3.8.1 of the main report. The mean

of the 10,000 values of is 5.34 ± 0.27 g/cm2 for a PWR and 4.53 ± 0.26 g/cm2 for a BWR. The

range of values is represented by the standard deviation of the individual values, not the standard

error of the mean. These data are presented as a matter of interest; however, only the individual

values were utilized in the radiological assessments.

A.6.2 Concrete

A.6.2.1 Concrete in Reference PWR

The volume of concrete used in constructing a 1,000 MWe PWR is summarized by UE&C

(1972), who also provide data on the area of the forms required to pour the various concrete

structures. Data used to calculate the mass-to-surface ratios for the various components, based

on this information, are presented in Table 6.1 of the main report. The 18 components in that

table are assumed to be potentially cleared after surface scabbling of hot spots. These

components constitute over 95% of the 142,500 t of concrete that would be potentially cleared

from a reference PWR (see Table A.15). As in the case of ferrous metals, we assume that the

clearance would take place over the 1.7-year period of dismantlement, and that a random fraction

of each component, represented by a triangular distribution with the same parameters, would be

cleared during any 1-year period of this 1.7-year time span. A new value of was calculated for

each realization in the probabilistic analyses of the concrete exposure scenarios.

A.6.2.2 Concrete in BWR

As noted in Table A.8, the mass of potentially cleared concrete in a reference BWR is about

281,000 t. This is assumed to comprise the Reactor Building, Primary Containment, Turbine

Generator Building, and Radwaste and Control Building, adjusted for removal of activated and

surficially radioactive material. Since data comparable to that for the PWRs were not available

to calculate the mass-to-surface area ratio for the reference BWR, values of are calculated in

the same way as in the probabilistic analysis of concrete cleared from the PWR. 

A.6.3 Copper

As listed in Table A.10, a reference PWR contains 694 t of copper. Of this total, 482 t (or about

70 percent) is categorized as power and control wiring associated with electrical plant

equipment. However, no details are available concerning the sizes and quantities of copper wire

used. UC&E (1972) characterize a total of 29 t of bus bar. We assume that the balance of the

copper—665 t—is 600 volt PVC-insulated copper conductor.
Appendix A Inventory of Materials

15 Nonferrous wire is designated by AWG (American Wire Gauge) or the equivalent Brown & Sharpe (B & S)

gauges. These gauges are numbered 0000 – 40, corresponding to nominal wire diameters of 0.460 – 0.0044 inch (1.168 –

0.0112 cm). Nehring designates wire (or cable) that is heavier than 0000 AWG by gauge numbers 250 – 1000. The

gauges in this range designate progressively heavier wire, unlike AWG sizes, of which the thinnest wire is 40 gauge.

A-57 NUREG-1640

Wire that is surveyed prior to clearance would be stripped of its insulation and chopped into

short lengths. Wire that is heavier than 10 gauge is typically stranded. The very large diameter

cables would most likely be separated into individual strands. The heaviest cable listed by the

Nehring Electrical Works Co. (n/d), 1000 gauge, is composed of 61 strands.15 The individual

strands are estimated to be between 6 and 8 gauge, based on the wire dimensions listed by

Nehring. For the purpose of the present analysis, it is assumed that the wire in the PWR is

uniformly distributed over even-numbered gauges ranging from 8 to 14. Given the absence of

similar data for BWRs, the same distribution is utilized in the assessment of copper scrap cleared

from both types of light-water reactors. Further information on the probability distribution of

mass-to-surface ratios of cleared copper scrap is presented in Section 4.2.1 of the main report.

A.6.4 Aluminum

As described in Table A.10, a reference PWR contains about 18 t of aluminum, including 6.1 t in

furnishings and fixtures, 400 kg in communication equipment, 4.1 t in switchboards, 6.4 t in

instrumentation and controls, and 1.2 t in structures (mostly in the turbine building). Furnishings

and fixtures encompass items such as office furniture, office equipment, lockers, benches,

laboratory furniture and fixtures, and laundry and dining facilities (UE&C 1972). From this

limited description, we conclude that the aluminum is likely to be sheet metal or thin-walled

tubing, ranging in thickness from 0.0625 to 0.25 in (0.16 to 0.64 cm). In the absence of any

other data, the same conclusion is applied to a BWR. Further information on the probability

distribution of mass-to-surface ratios of cleared aluminum scrap is presented in Section 5.2.1 of

the main report.

A.7 Total Mass of Potentially Cleared Materials from Licensed Facilities

This section presents a summary of the masses of potentially cleared ferrous metals, concrete,

aluminum, and copper resulting from the decommissioning of NRC-licensed facilities. The

cumulative masses were adjusted for facility size using the scaling factor concept described in

Section A.2.2 and elsewhere. Summary information is presented in Table A.40. In this table,

the cumulative mass is the product of the reference facility mass of potentially cleared materials

and the scaling factor. It is apparent that nuclear power reactors will contribute 98% of the

ferrous metals, 99% of the concrete, and all of the aluminum and copper. These estimates are

based on the available data included in this study. As indicated in the table, not all materials

were identified at all facilities. Consequently, the actual fractions of the masses of potentially

cleared materials from nuclear power reactors may be slightly less than stated here. 

The estimated total masses of potentially cleared materials from decommissioning of all licensed

facilities are listed below.
Inventory of Materials Appendix A

NUREG-1640 A-58

• Ferrous metals . . . . . . . . . . . . . . . . . . . 2.4 Mt

• Concrete . . . . . . . . . . . . . . . . . . . . . . . . 20 Mt

• Copper ......................... 6,585 t

• Aluminum . . . . . . . . . . . . . . . . . . . . . . . 212 t

These are estimates of potentially cleared materials generated during dismantlement of licensed

facilities. They do not include any materials generated during normal facility operation. The

estimates are based on the maximum estimated mass of potentially cleared materials from each

type of facility and do not consider variability in the data. Implicit in the development of the

mass of potentially cleared materials is the assumption that the activity levels in radioactive

materials are sufficiently high that there are very limited economic or risk-based incentives to

decontaminate materials for clearance. Consequently, variability in the mass of potentially

cleared material is expected to be primarily at the expense of clean material only. Industry

decommissioning practices reviewed in the course of preparing this appendix are generally

consistent with this practice, although some deviations are possible.
Appendix A Inventory of Materials

A-59 NUREG-1640

Table A.40 Mass of potentially cleared materials from decommissioning of licensed facilities

Description

No. of facilitiesScaling factor

Mass per facility (t) Total mass (t) Fraction of total mass Ferrous Concrete Aluminum Copper Ferrous Concrete Aluminum Copper Ferrous Concrete Aluminum Copper

Nuclear power reactors

BWR 35 32.327 19,374 281,000 2 62 6.26e+05 9.08e+06 64.7 2,004 0.264 0.454 0.304 0.304

PWR 69 65.866 23,255 142,503 2 62 1.53e+06 9.39e+06 132 4,084 0.645 0.469 0.620 0.620

Shutdown PWRb 8 6.088 23,255 142,503 2 62 1.42e+05 8.68e+05 12.2 377 0.060 0.043 0.057 0.057

Shutdown BWR 9 1.922 19,374 281,000 2 62 3.72e+04 5.40e+05 3.84 119 0.016 0.027 0.018 0.018

Total 121 2.34e+06 1.99e+07 212 6,585 0.984 0.994 1.000 1

Non-power reactors

Operating 36 56.71 0.504 192.5 a a 29 10,917 a a 1e-05 5e-04 a a

Fuel cycle facilities

Fuel fabs 7 4.62 1,087 7,128 a a 5,022 32,931 a a 0.002 0.002 a a

U conversion 2 1.9 513 2,050 a a 975 3,895 a a 4e-04 2e-04 a a

ISFSIc

Modular vault 1 1 0 11,800 0 0 0 11,800 0 0 0 6e-04 0 0

Wet 1 1 0 1,940 0 0 0 1,940 0 0 0 1e-04 0 0

Concrete 7 148 0 122.58 0 0 0 18,142 0 0 0 9e-04 0 0

NUHOMS-PWR 7 270 3 102.9 0 0 810 27,783 0 0 3e-04 0.001 0 0

NUHOMS-BWR 1 36 3.1 106.6 0 0 112 3,838 0 0 5e-05 2e-04 0 0

Metal cask 7 226 0 50.209 0 0 0 11,347 0 0 0 6e-04 0 0

Materials licensees

Hospitals — 1,000 30.6 a a a 30,600 a a a 0.013 a a a

Total 2.37e+06 2.00e+07 212 6,585 1 1 1 1

a No data available

b Does not include Yankee and Trojan

c Sum of ISFSI facilities is greater than number of facilities analyzed because some facilities have more than one type of

cask.
Inventory of Materials Appendix A

NUREG-1640 A-60

References

Anigstein, R., et al. 2001. “Technical Support Document – Potential Recycling of Scrap Metal

from Nuclear Facilities, Part I: Radiological Assessment of Exposed Individuals.” Washington,

DC.: U.S. Environmental Protection Agency, Office of Radiation and Indoor Air

http://www.epa.gov/radiation/cleanmetals/docs/tsd (August 12, 2002).

Bierschbach, M. C. 1995. “Estimating Pressurized Water Reactor Decommissioning Costs: A

User’s Manual for the PWR Cost Estimating Computer Program (CECP) Software,”

NUREG/CR-6054. Washington, DC: U.S. Nuclear Regulatory Commission. 

Bierschbach, M. C. 1996. “Estimating Boiling Water Reactor Decommissioning Costs,”

NUREG/CR-6270. Washington, DC: U.S. Nuclear Regulatory Commission.

Bluegrass Bit Company. (n/d). “Bluegrass Nuclear Performance and Experience.”.

http://www.bluegrassbit.com/clients/nuc-jobs/nuc_h.html (May 4, 2004).

BNFL Fuel Solutions Corporation (BNFL). 2000a. “Revision 1 of License Amendment Request

00-02, DFI Amendment,” BFS/NRC-00-079, Docket No. 72-1007. Scotts Valley, CA: Author.

BNFL Fuel Solutions Corporation (BNFL). 2000b. “Fuel SolutionsTM Storage System Safety

Analysis Report.” Revision 4, WNSF-200, Docket No. 72-1026. Scotts Valley, CA: Author.

BNFL Fuel Solutions Corporation (BNFL). 2000c. “Fuel SolutionsTM W21 Canister Storage

Safety Analysis Report.” Revision 4, WNSF-201, Docket No. 72-1026. Scotts Valley, CA:

Author.

BNFL Fuel Solutions Corporation (BNFL). 2000d. “Fuel SolutionsTM W74 Canister Storage

Safety Analysis Report.” Revision 4, WNSF-203, Docket No. 72-1026. Scotts Valley, CA:

Author.

Braverman, J. I., et al. 2001. “Probability-Based Evaluation of Degraded Reinforced Concrete

Components in Nuclear Power Plants,” NUREG/CR-6715. Washington, DC: U.S. Nuclear

Regulatory Commission.

Bryan, R. H., and I. T. Dudley. 1974. “Estimated Quantities of Materials Contained in a 1000-

MW(e) PWR Power Plant,” ORNL-TM-4515. Oak Ridge, TN: Oak Ridge National Laboratory. 

Bureau of the Census (U.S.) 2004. “2002 Economic Census: Table 1. Advance Summary

Statistics for the United States, 2002 NAICS Basis.”

http://www.census.gov/econ/census02/advance/TABLE1.HTM (May 31, 2004).

Code of Federal Regulations, Title 10, Energy, Part 20, “Standards for Protection Against

Radiation,” (10 CFR 20).

http://www.nrc.gov/reading-rm/doc-collections/cfr/part020/full-text.html (May 2, 2003).
Appendix A Inventory of Materials

A-61 NUREG-1640

Code of Federal Regulations, Title 10, Energy, Part 40, “Domestic Licensing of Source

Material” (10 CFR 40).

http://www.nrc.gov/reading-rm/doc-collections/cfr/part040/full-text.html (April 29, 2004).

Code of Federal Regulations, Title 10, Energy, Part 170, “Fees for Facilities, Materials, Import

and Export Licenses, and Other Regulatory Services under the Atomic Energy Act of 1954, as

Amended,” 170.3, “Definitions,” (10 CFR 170.3).

http://www.nrc.gov/reading-rm/doc-collections/cfr/part170/part170-0003.html (May 4, 2004).

Concrete Cutting and Breaking, Inc. (Concut). (n/d). “Nuclear Plant Renovation.”

http://www.concut.com/ps_nuclearplant.htm (May 4, 2004).

Department of Energy (U.S.), Energy Information Administration (DOE). 1995.

“Decommissioning of U.S. Uranium Production Facilities.” DOE-EIA-0592. Washington, DC:

Author. 

Elder, H. K., and D. E. Blahnik. 1980. “Technology, Safety and Costs of Decommissioning a

Reference Uranium Fuel Fabrication Plant,” NUREG/CR-1266. Vols. 1 and 2. Washington, DC:

U.S. Nuclear Regulatory Commission.

Elder, H. K., and D. E. Blahnik. 1981. “Technology, Safety and Costs of Decommissioning a

Reference Uranium Hexafluoride Conversion Plant,” NUREG/CR-1757. Washington, DC: U.S.

Nuclear Regulatory Commission. 

GE Nuclear Energy. 2000. “Consolidated Safety Analysis Report for Morris Operations, Morris,

Illinois” NEDO-21326D9. Author.

Gesellschaft für Nuklear-Behälter, mbH (GNB). 2000. “Topical Safety Analysis Report for the

Dry Storage Cask CASTOR® X/32 S.” GNB B 124/99, Revision 1, Docket No. 72-1028. Essen,

Germany: Author.

Keegan, E. (NRC Spent Fuel Program Office). 2003. <ENK@nrc.gov> “ISFSI information”

August 21, 2003, personal e-mail to Jean-Claude Dehmel, NRC Office of Regulatory Research.

Konzek, G. J., et al. 1982. “Technology, Safety and Costs of Decommissioning Reference

Nuclear Research and Test Reactors,” NUREG/CR-1756. Vols. 1 and 2. Washington, DC: U.S.

Nuclear Regulatory Commission.

Konzek, G. J., et al. 1983. “Technology, Safety and Costs of Decommissioning Reference

Nuclear Research and Test Reactors,” NUREG/CR-1756. Addendum. Washington, DC: U.S.

Nuclear Regulatory Commission.

Konzek, G. J., et al. 1995a. “Revised Analysis of the Decommissioning for the Reference

Pressurized Water Reactor Power Reactor Station,” NUREG/CR-5884. Vol. 1, Main Report.

Washington, DC: U.S. Nuclear Regulatory Commission.
Inventory of Materials Appendix A

NUREG-1640 A-62

Konzek, G. J., et al. 1995b. “Revised Analysis of the Decommissioning for the Reference

Pressurized Water Reactor Power Reactor Station,” NUREG/CR-5884. Vol. 2, “Appendices.”

Washington, DC: U.S. Nuclear Regulatory Commission. 

The Korean Peninsula Energy Development Organization (KEDO). 2000. “Opportunity to

Participate in Reinforcing Steel Bar Procurement Package No. 9-104-C206.” 

http://www.kedo.org/Procurement/ProcPackage9-104-C206.htm (May 20, 2002).

Lorenz, S., and F. Gardner, 1997. “Recycling of Metals in Practice - Commercial Experience.”

In R. G. Post (Ed.), Waste Management '97. Tucson, AZ: University of Arizona.

Ludwick, J. D., and E. B. Moore. 1984. “Technology, Safety and Costs of Decommissioning

Reference Independent Spent Fuel Storage Installations,” NUREG/CR-2210. Washington, DC:

U.S. Nuclear Regulatory Commission. 

Nehring Electrical Works Co. (n/d). “600 Volt Thermoplastic Insulated Cable.”

http://www.nehringelectrical.com/html/p8.htm (May 5, 2003).

Nuclear Regulatory Commission (U.S.) (NRC). 1988. “General Requirements for

Decommissioning Nuclear Facilities.” Federal Register: Vol. 53, No. 123. June 27, 1988. 

Nuclear Regulatory Commission (U.S.) (NRC). 1993. “Manual for Conducting Radiological

Surveys in Support of License Termination,” NUREG/CR-5849. Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 1994. “Generic Environmental Impact Statement

in Support of Rulemaking on Radiological Criteria for Decommissioning of NRC-Licensed

Nuclear Facilities,” NUREG-1496, Vol. 2, Draft Report for Comment. Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 2000a. “Information Digest, 2000 Edition,”

NUREG-1350, Vol. 12. Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 2000b. “Decommissioning of Nuclear Power

Reactors,” Regulatory Guide 1.184. Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 2000c. “Consolidated Guidance about Materials

Licenses: Guidance about Administrative Licensing Procedures,” Final NUREG-1556, Vol. 20.

Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 2000d. “Donald C. Cook– Summary of June 1,

2000, Public Meeting Regarding Containment Subcompartment Wall.” Washington, DC. Letter

to Robert P. Powers, Indiana Michigan Power Company, dated June 12, 2000.

Nuclear Regulatory Commission (U.S.) (NRC). 2000e. “Multi-Agency Radiation Survey and

Site Investigation Manual (MARSSIM),” NUREG-1575, Rev. 1. Washington, DC: Author.
Appendix A Inventory of Materials

A-63 NUREG-1640

Nuclear Regulatory Commission (U.S.) (NRC). 2002. “Information Digest, 2002 Edition,”

NUREG-1350, Vol. 14. Washington, DC: Author.

Nuclear Regulatory Commission (U.S.) (NRC). 2003a. “Fact Sheet on Uranium Mill Tailings.”

Washington, DC: Author. http://www.nrc.gov/reading-rm/doc-collections/fact-sheets/milltailings.html (May 4, 2004).

Nuclear Regulatory Commission (U.S.) (NRC). 2003b. “Information Digest, 2003 Edition,”

NUREG-1350, Vol. 15. Washington, DC: Author.

Oak, H. D. et al. 1980a. “Technology, Safety and Costs of Decommissioning a Reference

Boiling Water Reactor Power Station,” NUREG/CR-0672, Vol. 1, “Main Report.” Washington,

DC: U.S. Nuclear Regulatory Commission.

Oak, H. D. et al. 1980b. “Technology, Safety and Costs of Decommissioning a Reference

Boiling Water Reactor Power Station,” NUREG/CR-0672, Vol. 2, “Appendices.” Washington,

DC: U.S. Nuclear Regulatory Commission.

PHD Manufacturing, Inc. (n/d). “Online Catalog: Pipe Clamps.” http://www.phd-mfg.com/ (May

4, 2004).

Portland General Electric Corp. 1995. “Trojan Nuclear Plant: Radiological Site Characterization

Report,” Revision 0.1. Author.

Portland General Electric Corp. 2001. “Trojan Decommissioning Plan and License Termination

Plan,” Revision 9. Author.

R. S. Means Company Staff. 2000. Building Construction Cost Data, 2000. 58th ed. Kingston,

MA: R. S. Means Company, Incorporated.

Raddatz, M. G., and M. D. Waters. 1996. “Information Handbook on Independent Spent Fuel

Storage Installations,” NUREG-1571. Washington, DC: U.S. Nuclear Regulatory Commission.

Smith, R.I. et al. 1978a. “Technology, Safety, and Costs of Decommissioning a Reference

Pressurized Water Reactor Power Reactor Station,” NUREG/CR-0130, Vol. 1, “Main Report.“

Washington, DC: U.S. Nuclear Regulatory Commission.

Smith, R. I. et al. 1978b. “Technology, Safety, and Costs of Decommissioning a Reference

Pressurized Water Reactor Power Reactor Station,” NUREG/CR-0130, Vol. 2, “Appendices.”

Washington, DC: U.S. Nuclear Regulatory Commission.

Smith, R. I. et al. 1994a. “Revised Analyses of Decommissioning for the Reference Boiling

Water Reactor Power Station,” NUREG/CR-6174, Vol. 1, “Main Report.” Washington, DC:

U.S. Nuclear Regulatory Commission.
Inventory of Materials Appendix A

NUREG-1640 A-64

Smith, R. I. et al. 1994b. “Revised Analyses of Decommissioning for the Reference Boiling

Water Reactor Power Station,” NUREG/CR-6174, Vol. 2, “Appendices.” Washington, DC: U.S.

Nuclear Regulatory Commission.

South St. Paul Steel Supply Co., Inc. 2004. “Hot Rolled Steel Products.” South St. Paul, MN.

http://www.sspss.com (May 6, 2004).

TLG Services, Inc. 1999a. “Decommissioning Cost Study for the Millstone Nuclear Power

Station Unit 1.” Bridgewater, CT: Author.

TLG Services, Inc. 1999b. “Decommissioning Cost Estimate for the Zion Nuclear Power Station

Units 1 and 2,” Adams System Document No. C04-1326-002. Bridgewater, CT: Author.

Transnuclear West, Inc. (TNW). 2000. “Final Safety Analysis Report for the Standard

NUHOMS® Horizontal Modular Storage System for Irradiated Nuclear Fuel.” NUH-003,

Revision 5, NUH003.0103. Fremont, CA: Author.

United Engineers and Constructors, Inc. (UE&C). 1972. “Volume I: Pressurized Water Reactor

Plant, 1000-MWe Central Station Power Plants, Investment Cost Study,” WASH-1230 (Vol I).

Washington DC: U.S. Atomic Energy Commission, Division of Reactor Development and

Technology.

Virginia Electric & Power Company (VEPCO). 2000. “North Anna Independent Spent Fuel

Storage Installation, Final Safety Analysis Report.” Revision 2. Richmond, VA: Author.

Westinghouse Savannah River Company (WSRC). 1991. “Savannah River Site Production

Reactor Safety Analysis Report, K Production Reactor.” WSRC-SA-1000-3, Amendment 1.

Aiken, SC: Author.
APPENDIX B

PARAMETER VALUES

Appendix B Parameter Values

B-iii NUREG-1640

CONTENTS

Page

Appendix B Parameter Values . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1

B.1 Probability Distributions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1

B.2 Types of Distributions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1

B.2.1 Uniform . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1

B.2.2 Triangular . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1

B.2.3 Beta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-2

B.2.4 Normal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-2

B.2.5 Lognormal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-2

B.2.6 Custom . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-2

B.3 Fixed Values . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3

B.4 Data Quality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-37

Tables

B.1 Data quality levels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3

B.2 Partitioning of impurities in iron- and steelmaking . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-4

B.3 Mass fractions in iron- and steelmaking . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-6

B.4 Partitioning of impurities in copper fire refining . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-7

B.5 Mass fractions in fire refining of copper scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-8

B.6 Partitioning of impurities in secondary aluminum smelting . . . . . . . . . . . . . . . . . . . . . . . B-9

B.7 Mass fractions in secondary smelting of aluminum scrap . . . . . . . . . . . . . . . . . . . . . . . . B-10

B.8 Radionuclide-independent parameters of exposure scenarios . . . . . . . . . . . . . . . . . . . . . B-11

B.9 Radionuclide-independent parameters specific to copper scenarios . . . . . . . . . . . . . . . . B-21

B.10 Radionuclide-independent parameters specific to aluminum scenarios . . . . . . . . . . . . B-22

B.11 Radionuclide-independent parameter definitions specific to concrete scenarios . . . . . B-23

B.12 Time spent on various activities: cumulative distributions . . . . . . . . . . . . . . . . . . . . . . B-23

B.13 Hydrogeological parameters: custom distributions . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-24

B.14 Distance from landfill boundary to nearest well: continuous cumulative distribution . B-24

B.15 Radioactive decay data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-25

B.16 Dose conversion factors for inhalation—effective dose equivalent (:Sv/Bq) . . . . . . . B-26

B.17 Dose coefficients for inhalation—effective dose (:Sv/Bq) . . . . . . . . . . . . . . . . . . . . . . B-28

B.18 Dose conversion factors for ingestion—effective dose equivalent (:Sv/Bq) . . . . . . . . B-30

B.19 Dose coefficients for ingestion—effective dose (:Sv/Bq) . . . . . . . . . . . . . . . . . . . . . . B-32

B.20 Dose coefficients for external exposure to contaminated soil . . . . . . . . . . . . . . . . . . . . B-34

B.21 Soil-water distribution coefficients and food transfer factors . . . . . . . . . . . . . . . . . . . . B-35

Appendix B Parameter Values

B-1 NUREG-1640

B PARAMETER VALUES

This appendix presents detailed numerical data used in the analyses of the clearance of all

materials. The tables in this appendix list data that supplement the information in Volume 1 of

this report. 

As discussed in Section 1.3 of the main report, each of the exposure scenarios described in

Chapters 3 – 6 is characterized by a set of parameters that constitute a mathematical description

of that scenario. Each scenario models the exposure of a group of individuals to the residual

activity of a given medium. The concentration of a given radionuclide in such a medium is the

result of one or more processes: the mixing of cleared material (e.g., scrap metal) with similar

material from sources other than nuclear facilities, the melt-refining of scrap metal by a

secondary metal producer, the commingling of material disposed of in a landfill with wastes

from other sources, etc. Each of these processes is characterized by additional parameters.

B.1 Probability Distributions

In the present analysis, a parameter that does not have a single fixed value is characterized by a

probability distribution. The type of distribution and the numerical parameters that define the

distribution is determined by the supporting data as well as professional judgement. The

approach used to characterize parameter distributions follows the practices recommended by the

IAEA (1989). 

B.2 Types of Distributions

The types of probability distributions used in the present analysis are described in the following

sections, which present some general guidelines which are followed in assigning distributions to

the various parameters. It should be noted that the nature of the data underlying many of the

parameters varies greatly; assigning probability distributions to such parameters requires

professional judgement that cannot be summarized as a set of simple rules. The actual

distribution used for each parameter is specified in Tables B.2 – B.11. 

B.2.1 Uniform

Uniform distributions—the simplest type of distribution—are assigned to parameters for which

there is information on the range of values but no data on which to base a best estimate.

B.2.2 Triangular

Triangular distributions are assigned when there is information on the minimum and maximum

and a basis for estimating the best estimate or the mean, but no other information on the likely

shape of the distribution.
Parameter Values Appendix B

NUREG-1640 B-2

B.2.3 Beta

In the present analysis, beta distributions are often used to model the partitioning of impurities

during the melting and refining of scrap metal. Such distributions are used when there is

information on which to base the best estimate and when there is a range which is either

naturally imposed (e.g., the partition factor cannot be less than zero or greater than one), or is

based on professional judgement. A natural variability, such as the variability of the physicochemical environment in the melting furnace, is not well represented by a triangular distribution,

with it’s the sharp peak and discontinuous first derivative, while a uniform distribution would

embody the false assumption that all values in the interval were equally likely. The beta

distribution, defined only on the desired interval, is constructed with a mean equal to the best

estimate and a standard deviation equal to one-fourth of the interval. Such a distribution can be

thought of as a compromise between a uniform distribution (too broad) and a triangular

distribution (too sharply peaked). In fact, the variance of such a beta distribution is equal to the

average of the variances of a uniform distribution and a symmetrical triangular distribution over

the same interval.

The methodology used to assign a range of values to each of the partition factors is described in

Section J.5 of Volume 4.

B.2.4 Normal

Normal distributions are used to represent parameters which are described by normal

distributions in the literature. These distributions are also used when the mean value and the

standard deviation or coefficient of variation is reported for a parameter. Limits are imposed on

these distributions if minimum and/or maximum values are reported, or if constrained by the

definition of a given scenario. 

B.2.5 Lognormal

Lognormal distributions are used to represent parameters which are described by lognormal

distributions in the literature. These distributions are also used when the available data are best

described by such a distribution. Limits are imposed on these distributions if minimum and/or

maximum values are reported, or if constrained by the definition of a given scenario.

B.2.6 Custom

Custom distributions are used to represent certain parameters. Custom distributions may be

either discrete or continuous. If the parameter can only assume one of several discrete values,

each with an assigned probability, it is assigned a discrete distribution. Examples of such

distributions are shown in Table B.13. If the parameter can take on a continuous range of values

and the source data is in the form of percentiles, a continuous cumulative distribution can be

constructed by linear interpolation between adjacent data points. Examples of such distributions

are shown in Tables B.12 – B.14. Custom distributions can also be constructed by algebraic

manipulation of beta functions. Examples of such distributions are presented in Footnote c on
Appendix B Parameter Values

B-3 NUREG-1640

page B-19 and in Sections C.2.6 and C.4.4. Other unique distributions are described in other

chapters and appendices of the present report.

B.3 Fixed Values

Fixed values are assigned to several types of parameters. Physical quantities, such as radioactive

decay rates, are assigned their accepted values; experimental uncertainties are not addressed in

the present assessment. Dose factors listed by Eckerman et al. (1988), Eckerman and Ryman

(1993), ICRP (1987, 1994, 1996) have been adopted for regulatory purposes and are therefore

treated as fixed parameters.

Other parameters within a scenario are considered constant if they are fundamental to the

definition of the scenario. Examples include the time period over which potential exposures

occur (one year) and the thickness of the surface soil layer. The uncertainty and variability in

some parameter values has been combined into specific uncertainty factors. The uncertainty

factors typically represent an attempt to capture the most significant or the best known sources of

uncertainty and variability in an exposure pathway or environmental transport pathway. An

example is the food pathway, where individual parameter values such as growing periods for

plants, hold-up periods, and translocation fractions were held constant, and an input distribution

was developed for the parameter for the fraction of the diet derived from home-grown sources. 

Finally, some parameters are assigned fixed values either because they are known with a high

degree of certainty, or because only a single value is cited in the literature, with no basis for a

range.

B.4 Data Quality

The quality of the data employed in the analysis varies widely. The quality of the parameters is

rated on a scale of one to six, one being the highest. As with the assignment of probability

distributions to the parameters, the evaluation of the data quality follows some general

guidelines, but also relies to a great extent on professional judgement. The general guidelines

for assigning data quality are listed in Table B.1 The actual data quality assigned to each

parameter is listed in Tables B.2 – B.11.

Table B.1 Data quality levels

Level Criteria

1 Physical quantities with fixed values (see text); parameters that define scenario or model;

published data based on large number of samples applicable to scenario

2 Data on related experience or populations which closely match scenario descriptions

3 Data on related experience or populations which approximate scenario descriptions

4 Values based on a few data points, limited industry experience, or theoretical models

5 Values based on sparse data or expert opinion 

6 Anecdotal data based on one observation
Parameter Values Appendix B

NUREG-1640 B-4

Table B.2 Partitioning of impurities in iron- and steelmaking

Symbol

Parameter description/scenario

Metala

Data quality

Distribution

Alpha,

fixed value,

or formulab

Betac Min. Max.

fa Atmospheric release fractions of volatile elements

H + — derived 1 ! fp 0.85 0.95

C CS 4 beta 2.1763 3.7857 0 0.73

Fe 4 fixed 0

Na, P, S, K, Ca, Sc, Cr, Mn, Fe, Co, Ni, Zn, As,

Se, Sr, Y, Zr, Nb, Mo, Tc, Ru, Ag, Cd, Sn, Sb,

Te, Cs, Ba, Ce, Pm, Sm, Eu, Gd, Tb, Tm, Ta,

W, Os, Ir, Tl, Pb, Bi, Po, Ra, Ac, Th, Pa, U, Np,

Pu, Am, Cm, Bk, Cf, Es

+ 4 fixed 0

Cl, I + — derived 1! fd ! fg 0 1.0

fd Dust partitioning factors

H + 4 fixed 0

C CS 4 fixed 0

C, Cr, Mn Fe, Co, Ni, Mo, Tc, Ru, Ag, W, Ir Fe 4 uniform 0 0.01

Na, K CS 4 beta 49.52 49.52 0.40 0.60

Fe — derived 1 ! fg 0.5 1.0

P + 5 uniform 0.02 0.04

S + 4 beta 8.7574 282.24 0.01 0.05

Cl, I + 4 beta 2.7522 8.2543 0 0.50

Ca, Sc, Sr, Y, Zr, Nb, Ba, Ce, Pm, Sm, Eu, Gd,

Tb, Tm, Ta, Ra, Ac, Th, Pa, U, Np, Pu, Am, Cm,

Bk, Cf, Es

+ 4 beta 15.209 288.43 0.025 0.075

Cr CS 4 uniform 0.01 0.03

Mn CS 4 uniform 0.03 0.04

Fe, Co, Ni, Mo, Tc, Ru, W, Ir CS 4 uniform 0.005 0.015

Zn CS — derived 1 ! fp 0.80 1.00

Fe — derived 1 ! fp 0.97 0.99

As + 4 beta 6.0038 14.006 0.1 0.5

Ag CS 4 beta 3.96 26.484 0.01 0.25

Cd + 4 fixed 1.0

Se, Te, Pb, Tl, Bi, Po CS — derived 1 ! fp 0.925 0.975

Se Fe 4 beta 14.851 197.05 0.035 0.105

Sn + 4 uniform 0.005 0.015

Sb CS 4 beta 4.2762 36.419 0.01 0.20

Fe 4 beta 368.61 15.395 0.94 0.98

Te Fe 4 beta 49.52 49.52 0.4 0.6

Cs CS — derived 1 ! fg 0.95 1.00

Fe — derived 1 ! fg 0.5 1.0

Os + — derived 1 ! fp 0.925 0.975

Tl, Pb Fe — derived 1 ! fp 0.90 0.96

Bi Fe — derived 1 ! fp 0.93 0.97

Po Fe 4 fixed 1.0
Appendix B Parameter Values

Table B.2 Partitioning of impurities in iron- and steelmaking

Symbol

Parameter description/scenario

Metala

Data quality

Distribution

Alpha,

fixed value,

or formulab

Betac Min. Max.

B-5 NUREG-1640

fg Slag partitioning factors

H, C, Co, Ni, Zn, As, Se, Mo, Tc, Ru, Ag, Cd,

Sn, Te, W, Os, Ir, Tl, Pb, Bi, Po + 4 fixed 0

Na, K CS — derived 1 ! fd 0.4 0.6

Na, K, Cs Fe 4 beta 2.7522 8.2543 0.0 0.5

P + 4 beta 16.597 7.6334 0.50 0.87

S + 4 beta 86.619 19.67 0.74 0.89

Ca, Sc, Sr, Y, Zr, Nb, Ba, Ce, Pm, Sm, Eu, Gd,

Tb, Tm, Ta, Ra, Ac, Th, Pa, U, Np, Pu, Am, Cm,

Bk, Cf, Es

+ — derived 1 ! fd 0.925 0.975

Cr CS — derived 1 ! fd ! fp 0 0.59

Cr, Fe, Sb Fe 4 fixed 0

Mn CS — derived 1 ! fd ! fp 0.72 0.95

Fe — derived 1 ! fd ! fp 0.00 0.04

Fe CS 4 uniform 0.01 0.03

Cl, I + 4 beta 2.7522 8.2543 0 0.5

Sb, Cs CS 4 beta 3.906 151.73 0 0.05

fp Metal product partitioning factors

H + 4 beta 14.327 128.83 0.05 0.15

C CS — derived 1 ! fa 0.27 1.00

C, Cr, Fe, Co, Ni, Mo, Tc, Ru, Ag, W, Ir Fe — derived 1 ! fd 0.99 1.00

P + — derived 1 ! fd ! fg 0.09 0.48

S + — derived 1 ! fd ! fg 0.06 0.25

Na, Cl, K, Ca, Sc, Sr, Y, Zr, Nb, Cd, Ba, Ce,

Pm, Sm, Eu, Gd, Tb, Tm, Ta, Ra, Ac, Th, Pa, U,

Np, Pu, Am, Cm, Bk, Cf, Es

+ 4 fixed 0

Cr CS 4 beta 6.5969 3.0341 0.40 0.97

Mn CS 4 beta 4.7375 31.684 0.02 0.24

Fe 4 beta 423.22 10.894 0.96 0.99

Fe CS — derived 1 ! fd ! fg 0.955 0.985

Co, Ni, Mo, Tc, Ru, W, Ir CS — derived 1 ! fd 0.985 0.995

Zn CS 4 beta 3.5068 31.533 0 0.2

Fe 4 uniform 0.01 0.03

As + — derived 1 ! fd 0.5 0.9

Se, Te, Tl, Pb, Bi, Po CS 4 beta 15.209 288.43 0.025 0.075

Se Fe — derived 1 ! fd 0.895 0.965

Ag CS — derived 1 ! fd 0.75 0.99

Sn + — derived 1 ! fd 0.985 0.995

Sb CS — derived 1 ! fd ! fg 0.75 0.99

Fe — derived 1 ! fd 0.02 0.06

Te Fe — derived 1 ! fd 0.4 0.6

Os + 4 beta 15.209 288.43 0.025 0.075

Tl, Pb Fe 4 beta 20.239 268.54 0.04 0.10

Bi Fe 4 beta 23.793 451.21 0.03 0.07

Po Fe 4 fixed 0
Parameter Values Appendix B

NUREG-1640 B-6

Notes to Table B.2

a

 CS = carbon steel, Fe = cast iron, + = both metals

b

 Alpha parameter of beta distribution, formula for derived value, or fixed value; symbols in formulae shown in column 1

c

 Beta parameter of beta distribution

Table B.3 Mass fractions in iron- and steelmaking

Symbol

Parameter Description/Furnace type

Data quality

Distribution

Mode or

fixed value Min. Max.

fs Mass of scrap as fraction of metal in furnace charge

BOF 6 fixed 0.24

EAF 6 fixed 0.955

Cast iron 6 fixed 0.915

gh Mass of home scrap as fraction of scrap in furnace charge

BOF 6 fixed 0.24

EAF 6 fixed 0.25

Cast iron 6 fixed 0.384

fd Mass of dust generated as fraction of metal poured

BOF 3 triangular 0.0175 0 0.031

EAF 3 triangular 0.0165 0.011 0.022

Cast iron 5 uniform 0 0.01

fg Mass of slag generated as fraction of metal poured

BOF 3 triangular 0.12 0.051 0.22

EAF 3 triangular 0.13 0.12 0.14

Cast iron 5 uniform 0.016 0.087

, Efficiency of APCD

BOF 4 triangular 0.997 0.994 0.999

EAF 5 uniform 0.9988 0.9991

Cast iron 5 uniform 0 0.95
Appendix B Parameter Values

B-7 NUREG-1640

Table B.4 Partitioning of impurities in copper fire refining

Symbol

Parameter description/scenario

Data quality

Distribution

Alpha,

fixed

value, or

formulaa

Betab Min. Max.

fa Atmospheric release fractions of volatile elements

H, C 4 fixed 1

Na, P, S, Cl, K, Ca, Sc, Cr, Mn, Fe, Co, Ni, Zn,

As, Se, Sr, Y, Zr, Nb, Mo, Tc, Ru, Ag, Cd, Sn,

Sb, Te, I, Cs, Ba, Ce, Pm, Sm, Eu, Gd, Tb, Tm,

Ta, W, Os, Ir, Tl, Pb, Bi, Po, Ra, Ac, Th, Pa, U,

Np, Pu, Am, Cm, Bk, Cf, Es

4 fixed 0

fd Dust partitioning factors

H, C, Na, Ca, Sc, Cr, Mn, Fe, Co, Ni, Sr, Y, Zr,

Nb, Mo, Tc, Ru, Ag, Sn, Ba, Ce, Pm, Sm, Eu,

Gd, Tb, Tm, Ta, W, Os, Ir, Ra, Ac, Th, Pa, U,

Np, Pu, Am, Cm, Bk, Cf, Es

4 fixed 0

P, S, K 4 beta 2.626 2.626 0.10 0.90

Cl, I, Bi 4 beta 3.765 71.395 0 0.1

Zn, Cd, Sb, Pb 4 beta 3.906 151.73 0 0.05

As - derived 1 - fg - fp 0.10 0.80

Se, Te, Cs - derived 1- fp 0.80 0.90

Tl 4 beta 19.358 23.659 0.30 0.60

Po - derived 1- fp 0.500 0.990

fg Slag partitioning factors

H, C, Se, Ru, Ag, Te, Cs, Os, Ir, Bi, Po 4 fixed 0

Na, Ca, Sc, Cr, Sr, Y, Zr, Nb, Mo, Tc, Ba, Ce, 

Pm, Sm, Eu, Gd, Tb, Tm, Ta, W, Ra - derived 1- fp 0.9985 0.9995

P, S, K - derived 1 - fd - fp 0.0985 0.8995

Cl, I - derived 1 - fd 0.90 1.00

Mn - derived 1- fp 0.95 0.98

Fe - derived 1- fp 0.750 0.980

Co, Ni - derived 1- fp 0.40 0.99

Zn, Cd 4 beta 44.348 8.452 0.74 0.94

As 4 beta 3.869 5.802 0.10 0.70

Sn - derived 1- fp 0.60 0.88

Sb 4 beta 5.282 3.17 0.31 0.94

Tl - derived 1 - fd - fp 0.20 0.60

Pb 4 beta 1.776 2.215 0 0.89

Ac, Np, Pu, Am, Cm, Bk, Cf, Es - derived 1- fp 0.99 0.999

Th, Pa, U - derived 1- fp 0.98 0.999
Parameter Values Appendix B

Table B.4 Partitioning of impurities in copper fire refining

Symbol

Parameter description/scenario

Data quality

Distribution

Alpha,

fixed

value, or

formulaa

Betab Min. Max.

NUREG-1640 B-8

fp Metal product partitioning factors

H, C, Cl, I 4 fixed 0

Na, P, S, K, Ca, Sc, Cr, Sr, Y, Zr, Nb, Mo, Tc,

Ba, Ce, Pm, Sm, Eu, Gd, Tb, Tm, Ta, W, Ra 4 uniform 0.0005 0.0015

Mn 4 uniform 0.02 0.05

Fe 4 beta 4.64 29.71 0.02 0.25

Co, Ni 4 beta 2.668 6.079 0.01 0.60

Zn, Cd - derived 1 - fd - fg 0.010 0.260

As, Se, Te, Cs, Tl 4 beta 30.488 172.67 0.10 0.20

Ru, Ag, Os, Ir 4 fixed 1

Sn 4 beta 9.956 28.33 0.120 0.400

Sb - derived 1 - fd - fg 0.010 0.690

Pb - derived 1 - fd - fg 0.06 1

Bi - derived 1 - fd 0.90 1

Po 4 beta 2.976 8.691 0.01 0.5

Ac, Np, Pu, Am, Cm, Bk, Cf, Es 4 uniform 0.001 0.010

Th, Pa, U 4 uniform 0.001 0.020

a

 Alpha parameter of beta distribution, formula for derived value, or fixed value; symbols in formulae shown in column 1

b

 Beta parameter of beta distribution

Table B.5 Mass fractions in fire refining of copper scrap

Symbol

Parameter

Data quality

Distribution

Mean orfixed value

Standarddeviation

Min Max.

fs mass of scrap as fraction of metal in furnace charge 4 fixed 1

gh mass of home scrap as fraction of scrap in furnace 4 fixed 0.475

fd mass of dust generated as fraction of metal poured 2 lognormal 0 0.003 0 0

fg mass of slag generated as fraction of metal poured 5 uniform 0 0

, efficiency of APCD 6 fixed 0.92
Appendix B Parameter Values

B-9 NUREG-1640

Table B.6 Partitioning of impurities in secondary aluminum smelting

Symbol

Parameter description/scenario

Data quality

Distribution

Alpha,

fixed

value, or

formulaa

Betab Min. Max.

fa Atmospheric release fractions of volatile elements

H - derived 1 - fp 0.80 1.00

C, Na, P, S, Cl, K, Ca, Sc, Cr, Mn, Fe, Co, Ni, 

Zn, As, Se, Sr, Y, Zr, Nb, Mo, Tc, Ru, Ag, Cd,

Sn, Sb, Te, Cs, Ba, Ce, Pm, Sm, Eu, Gd, Tb,

Tm, Ta, W, Os, Ir, Tl, Pb, Bi, Po, Ra, Ac, Th,

Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es

4 fixed 0

I 4 beta 2.752 8.254 0 0.5

fd Dust partitioning factors

H, C, Na, S, Cl, K, Ca, Sc, Sr, Y, Ru, Ag, I, Cs,

Ce, Pm, Sm, Eu, Gd, Tb, Tm, Ra, Ac, Th, Np,

Am, Cm, Bk, Cf, Es

4 fixed 0

P, Cr, As, Se, Mo, Tc, Sn, Sb, Te, Ta, W, Os, Ir,

Tl, Pb, Bi, Po, Pa 4 beta 3.38 23.645 0.00 0.25

Mn, Fe, Co, Ni, Zn, Nb, Cd, Ba, 4 beta 5.612 96.253 0.01 0.1

Zr 4 derived fd÷(fd+fg+fp) 0.00 1.00

U, Pu 4 beta 3.77 71.40 0.00 0.10

fg Dross partitioning factors

H, S, Ru, Ag, Cd 4 fixed 0

C, Na, K, Ce - derived 1- fp 0.90 0.99

P, Cr, As, Se, Mo, Tc, Sn, Sb, Te, Ta, W, Os, Ir,

Tl, Pb, Bi, Po, Pa 4 beta 3.38 23.645 0.00 0.25

Cl, Sc, Y, Cs, Pm, Sm, Eu, Gd, Tb, Tm, Ra 4 fixed 1

Ca, Sr - derived 1- fp 0.75 0.99

Mn, Fe, Co, Ni, Zn, Nb 4 beta 5.612 96.253 0.01 0.10

Zr 4 derived fg÷(fd+fg+fp) 0.00 1.00

I - derived 1- fa 0.50 1.00

Ba - 1 - fd 0.90 0.99

Ac, Th, Np, Am, Cm, Bk, Cf, Es - derived 1- fp 0.50 0.99

U, Pu 4 beta 14.809 6.5 0.50 0.89

fp Metal product partitioning factors

H 4 beta 3.507 31.53 0.00 0.20

C, Na, K, Ce 4 beta 5.612 96.253 0.01 0.10

P, Cr, As, Se, Mo, Tc, Sn, Sb, Te, Ta, W, Os, Ir,

Tl, Pb, Bi, Po, Pa - derived 1 - fd - fg 0.50 1.00

S, Ru, Ag 4 fixed 1

Cl, Sc, Y, I, Cs, Ba, Pm, Sm, Eu, Gd, Tb, Tm,

Ra 4 fixed 0

Ca, Sr 4 beta 3.96 26.484 0.01 0.25

Mn, Fe, Co, Ni, Zn, Nb - derived 1 - fd - fg 0.80 0.98

Zr 4 derived fp÷(fd+fg+fp) 0.00 1.00

Cd - derived 1 - fd 0.90 0.99

Ac, Th, Np, Am, Cm, Bk, Cf, Es 4 beta 2.976 8.691 0.01 0.50

U, Pu - derived 1 - fd - fp 0.01 0.50 a

 Alpha parameter of beta distribution, formula for derived value, or fixed value; symbols in formulae shown in column 1 b

 Beta parameter of beta distribution
Parameter Values Appendix B

a

 Fraction with respect to metal in furnace charge, unless otherwise noted

NUREG-1640 B-10

Table B.7 Mass fractions in secondary smelting of aluminum scrap

Symbol

Parametera

Data quality

Distribution

Mean,

mode or

fixed

value

Standard

deviation Min Max.

fs mass fraction of scrap 4 fixed 1

gh mass fraction of heel 5 uniform 0.2 0.4

fd mass fraction of dust generated 2 normal 2.15e-03 1.75e-03 0.00048 —

fda mass fraction of dust released 2 normal 6.5e-04 1.5e-04 0 fd

fg mass fraction of dross generated 4 triangular 0.15 0.09 0.24

fAl,d mass fraction of Al in dust 5 fixed 0.394

mass fraction of Al2O3 in dross 5 uniform 0.2 0.5

mass fraction of Al in Al2O3 1 derived 0.529
Appendix B Parameter Values

c

 Mean value of natural logarithms

d

 Standard deviation of natural logarithms

e

 See Table B.13

f

 Mean value of distribution

g

 Standard deviation of distribution

B-11 NUREG-1640

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

bc soil-specific exponential parameters of contaminated zone

all groundwater scenarios 2 lognormal -0.0253c 0.216d 0.501 1.9

bv soil-specific exponential parameters of vadose zone

all groundwater scenarios 2 lognormal 1.06c 0.66d 0.5 30

Bm, Bod breathing rates for moderate physical activity and for outdoor activities (m3

/h)

all scenarios where used 4 triangular 1.2 0.6 1.8

Bs breathing rate for indoor activities (m3

/h)

all scenarios where used 4 triangular 1.2 0.5 1.2

d1 thickness of surface soil layer (m)

Airborne emissions 1 fixed 0.15

dfh dilution factor for immobilization process

EAF dust disposal 4 fixed 0.77

dfr dilution factor

Slag basement 5 fixed 0.01

dg depth of slag (m)

Leachate–steel slag 6 fixed 1

dL depth of contaminated zone (m)

all landfill groundwater scenarios 1 custome 1.32 10.1

ds thickness of soil layer available for resuspension (resuspension layer) (m)

Airborne emissions 6 fixed 0.01

dw depth of well below water table (m)

all groundwater scenarios 1 custome 2.24 35.2

Dz max height of adjacent buildings (m)

Airborne emissions 5 uniform 15 50

D/Q relative deposition rate: particulates & iodines (m-2)

Airborne emissions 2 lognormal 0f 0g 6.0e-09 6.2e-08

fc fraction of slag in asphaltic concrete

Driving on slag road 5 fixed 0.8

fD plume depletion factor at distance of 1,000 m

Airborne emissions 1 fixed 0.9005

a

 Mode of triangular distribution or fixed value (except as noted)

b

 Standard deviation or geometric standard deviation of lognormal distribution, as noted
Parameter Values Appendix B

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 See Table B.13

d

 Mean value of natural logarithms

NUREG-1640 B-12

Fd fraction of EAF dust in waste stream

Processing EAF dust 5 fixed 0.75

EAF dust disposal 5 fixed 0.75

fE fraction of steel scrap recycled at EAFs

Processing EAF dust 2 fixed 0.58

EAF dust disposal 2 fixed 0.58

home-grown fractions of food—Airborne emissions

fhf fruit 4 triangular 0.052 0.027 0.161

fhk milk 4 triangular 0.043 0.000 0.254

fhm meat 4 triangular 0.064 0.003 0.319

fhf all vegetables 4 triangular 0.144 0.027 0.308

fraction of total plant mass that is water

Airborne emissions 3 fixed 0.75

fv,C fraction of total plant mass that is stable carbon

Airborne emissions 3 fixed 0.11

fw fraction of waste in landfill volume

all scenarios where used 4 fixed 0.8

Fr indoor resuspension factor (m-1)

Airborne emissions 6 fixed 0

H absolute humidity of the atmosphere at receptor (g/m3

)

Airborne emissions 4 triangular 7.0 3.0 16.0

he effective release height (m)

Airborne emissions 1 fixed 0

I infiltration rate (m/y)

all groundwater scenarios 3 customc 0 0.0526

Is secondary ingestion rate (g/h)

all scenarios where used 5 uniform 0.0e+00 2.0e-02

l

w daily intake of tapwater (mL/d)

all groundwater scenarios 2 lognormal 6.864d 0.575 196 4732

J Ksa seepage velocity (m/y) = hydraulic gradient (J) × saturated hydraulic conductivity of aquifer (Ksa)

all groundwater scenarios 3 customc 0.10 10,800

Ksv saturated hydraulic conductivity of vadose zone (m/y)

all scenarios where used 3 customc 0.004 2450

a

 Mode of triangular distribution or fixed value (except as noted)

b

 Standard deviation of natural logarithms
Appendix B Parameter Values

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 See Table D.9

d

 See Table B.13

B-13 NUREG-1640

rate of slag utilization (t/d)

Building road with slag 4 fixed 1279

mL mass of load (tons)

Transferring EAF dust 3 fixed 22

Scrap truck–driver 3 fixed 20

Slag truck–driver 3 fixed 22

EAF dust–bulk trailer 3 fixed 22

EAF dust–dump trailer 3 fixed 22

Metal product–driver 3 fixed 22

mp maximum size of slag pile (Mg)

Leachate–steel slag 5 fixed 23000

Mt

 mass of EAF dust generated in U.S. annually (g)

all scenarios where used 3 fixed 8.39e+11

Nd number of drivers

Scrap truck–driver 5 uniform 6 8

nD number of nuclear plants undergoing dismantlement annually

Processing EAF dust 2 customc 1 18

EAF dust disposal 2 customc 1 18

P areal soil density (kg dry&weight soil/m2

)

all scenarios where used 4 fixed 240

Pd indoor dust-loading on floors (g/m2

)

all scenarios where used 6 fixed 0.4

pea effective porosity of aquifer

all groundwater scenarios 3 customd 0.05 0.426

pev effective porosity of vadose zone

all groundwater scenarios 3 normal 0.355 0.0906 0.075 0.635

pta total porosity of aquifer 

all groundwater scenarios 3 normal 0.43 0.06 0.2446 0.6154

ptv total porosity of vadose zone

all groundwater scenarios 3 customd 0.41 0.45

r fraction of deposited activity intercepted by crops—Airborne emissions

iodines 4 fixed 1.0

other particulates 4 fixed 0.25

 rH-3 ratio of tritium concentration in plant water to tritium concentration in atmospheric water

Airborne emissions 6 fixed 0.5

a

 Mode of normal or triangular distributions, or fixed value (except as noted)

b

 Standard deviation of normal distribution
Parameter Values Appendix B

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 See Table B.12

NUREG-1640 B-14

Ssx indoor shielding factor (dimensionless)

Airborne emissions 5 uniform 0.04 0.70

Svx Vehicle shielding factor (dimensionless)

all scenarios where used 5 triangular 0.5 0.3 0.7

T period during which mill is recycling cleared scrap (y)

all scenarios where used 6 fixed 1.7

ta assessment period (d)

all scenarios where used 1 fixed 365.25

tb period of long&term buildup for activity in soil (d)

Airborne emissions 6 fixed 621

tdd time spent on dusty activities outdoors (h/mo)

Airborne emissions 3 customc 0 320

tdw time driving with one-way load (h/w)

Slag truck–driver 3 triangular 24.5 15 32.5

EAF dust–dump trailer 3 triangular 26 19 33.5

average time driving with one-way load (h/w)

Slag truck–driver 3 fixed 24.5

EAF dust–dump trailer 3 fixed 26

Metal product–driver 3 fixed 26

t1dw time in driver’s seat (h/w)

Driver–diesel engine 4 triangular 54 41 70

tgv growing period for plant v (d)—Airborne emissions

leafy vegetables 6 fixed 45

non-leafy vegetables 6 fixed 90

fruit 6 fixed 90

stored hay 6 fixed 45

stored grain 6 fixed 90

fresh forage 6 fixed 30

th holdup period between harvesting and consumption (d)—Airborne emissions

fruit 6 fixed 14

leafy vegetables 6 fixed 1

non-leafy vegetables 6 fixed 14

grain 6 fixed 14

meat 6 fixed 20

milk 6 fixed 1

a

 Mode of triangular distribution, or fixed value

b

 Not used
Appendix B Parameter Values

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

B-15 NUREG-1640

tid time spent indoors (min/d)

Airborne emissions 2 normal 1001.4 275.14 8 1440 

tit time spent loading and unloading truck (hours/trip)

all transport scenarios where used 5 uniform 0.25 0.5

tmd max time permitted driving without an 8-h rest period

EAF dust–dump trailer 6 fixed 10

tod time spent outdoors (min/d)

Airborne emissions 2 normal 154 158.3 1.0 1290

ts time from release of cleared material from nuclear facility to time scenario begins (d)

Scrap yard 5 uniform 3 17

Handling slag (EAF) 5 uniform 10 56

Handling slag (BOF) 5 uniform 10 40

Baghouse maintenance 5 uniform 10 56

Transferring EAF dust 5 uniform 10 56

Processing EAF dust 5 uniform 11 67

Processing steel slag (EAF) 5 uniform 13 241

Processing steel slag (BOF) 5 uniform 13 225

Handling metal product (EAF & other) 5 uniform 8 52

Handling metal product (BOF) 5 uniform 8 36

Airborne emissions (EAF & other) 5 uniform 8 52

Airborne emissions (BOF) 5 uniform 8 36

Building road with slag (EAF) 5 uniform 195 242

Building road with slag (BOF) 5 uniform 195 226

Exposure to large mass (EAF & other) 5 uniform 23 123

Exposure to large mass (BOF) 5 uniform 23 93

Exposure to small mass (EAF) 5 uniform 23 123

Exposure to small mass (BOF) 5 uniform 23 93

Steel object on body (EAF) 5 uniform 23 123

Steel object on body (BOF) 5 uniform 23 93

Driver–automobile 5 uniform 26 175

Home with steel studs (EAF) 5 uniform 113 303

Home with steel studs (BOF) 5 uniform 113 273

Sailor–hull plate (EAF) 5 uniform 555 600

Sailor–hull plate (BOF) 5 uniform 555 584

Driver–diesel engine 5 uniform 26 175

Slag basement (EAF) 5 uniform 115 279

Slag basement (BOF) 5 uniform 115 263

a

 Mode of normal distribution or fixed value

b

 Standard deviation of normal distribution
Parameter Values Appendix B

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 In addition to time needed to construct road (calculated)

d

 See Table B.12

NUREG-1640 B-16

ts time from release of cleared material from nuclear facility to time scenario begins (d)

Driving on slag road (EAF) 5 uniform 196c 243c

Driving on slag road (BOF) 5 uniform 196c 227c

Scrap truck–driver 5 uniform 2 6

Slag truck–driver (EAF & other) 5 uniform 12 59

Slag truck–driver (BOF) 5 uniform 12 43

EAF dust–bulk trailer 5 uniform 10 60

EAF dust–dump trailer 5 uniform 10 60

Metal product–driver (EAF & other) 5 uniform 8 86

Metal product–driver (BOF) 5 uniform 8 56

Scrap disposal–industrial 5 uniform 2 7

Scrap disposal–municipal 5 uniform 2 7

Dust disposal-industrial (BOF) 5 uniform 12 46

Dust disposal-industrial (other) 5 uniform 12 62

Dust disposal-municipal (BOF) 5 uniform 12 46

Dust disposal-municipal (other) 5 uniform 13 73

Slag disposal–industrial (EAF & other) 5 uniform 12 62

Slag disposal–industrial (BOF) 5 uniform 12 46

Leachate–steel slag (EAF) 5 uniform 13 59

Leachate–steel slag (BOF) 5 uniform 13 43

EAF dust disposal 5 uniform 13 73

All landfill leachate scenarios 6 fixed 0.85 y

tt duration of trip (h)

Scrap truck–driver 5 uniform 1 1.5

ttr transfer time of EAF dust (h)

Transferring EAF dust 5 uniform 0.5 1

tv time spent in automobile (min/d)

Driving on slag road 2 customd 1 1,280

tw time in driver’s seat hauling one-way load (h/w)

Slag truck–driver 3 triangular 26.5 17.7 34.2

EAF dust–drivers 3 triangular 28 22 36.5

Metal product–driver 3 triangular 28 22 36.5

a

 Mode of triangular distribution or fixed value

b

 Not used
Appendix B Parameter Values

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

B-17 NUREG-1640

average time in driver’s seat hauling one-way load (h/w)

Slag truck–driver 3 fixed 26.5

EAF dust–drivers 3 fixed 28

Metal product–driver 3 fixed 28

txd daily exposure duration (h/d)

Scrap yard 5 uniform 4 6

Handling slag 5 uniform 2 6

Baghouse maintenance 5 uniform 4 6

Processing EAF dust 5 uniform 2 6

Processing steel slag 5 uniform 2 6

Handling metal product 5 uniform 4 8

Slag basement 5 triangular 16 4 16

Exposure to large mass 5 triangular 4 2 8

Exposure to small mass 5 triangular 4 2 8

Steel object on body 5 triangular 5 2.9 16.0

Driver–automobile 5 uniform 6.3 11.5

Home with steel studs 5 triangular 8 4 16

Sailor–hull plate (bunk) 5 uniform 7.0 9.4

Sailor–hull plate (lounge) 5 uniform 0.5 1.5

Building road with slag 1 fixed 8

Scrap disposal–industrial 5 uniform 5 7

Scrap disposal–municipal 5 uniform 5 7

Dust disposal-industrial 5 uniform 5 7

Dust disposal-municipal 5 uniform 5 7

Slag disposal–industrial 5 uniform 5 7

Slag disposal–municipal 5 uniform 5 7

EAF dust disposal 5 uniform 5 7

tys annual exposure duration (d/y)

Baghouse maintenance 5 uniform 1 10

Slag basement 5 fixed 350

Exposure to large mass 5 fixed 350

Exposure to small mass 5 fixed 350

Steel object on body 5 fixed 350

Driver–automobile 5 fixed 300

Home with steel studs 5 fixed 350

Steel ship scenarios 4 customc 330 309 351

Sailor–hull plate 4 triangular 300 183 335

a

 Mode of triangular, mean of custom distribution, or fixed value

b

 Not used

c

 See Section 3.7.4.1 in main report
Parameter Values Appendix B

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

NUREG-1640 B-18

tys annual exposure duration (d/y)

Driver–diesel engine 5 uniform 200 250

all other scenarios where used 6 fixed 250

human consumption rates—Airborne emissions

Uf fruit (kg/y) 3 fixed 56.98

Uk milk (L/y) 3 fixed 81.8

Ul leafy vegetables (kg/y) 3 fixed 16.97

Um meat (kg/y) 3 fixed 70.5

Us soil (kg/y) 3 fixed 0.01826

Uv non-leafy vegetables (kg/y) 3 fixed 48.4

Uw well pumping rate (m3

/a)

Leachate–steel slag 5 uniform - 250 1500

Ux uncertainty parameter for external exposure

Scrap yard 5 uniform 0.4 1.6

Handling slag 5 uniform 0.5 1.0

Baghouse maintenance 5 uniform 0.9 1.1

Transferring EAF dust 5 uniform 0.9 1.1

Processing EAF dust 5 uniform 0.6 1.4

Processing steel slag 5 uniform 0.6 1.4

Handling metal product 5 uniform 0.2 1.8

Driving on slag road 5 fixed 1

Slag basement 5 uniform 0.9 1.1

Exposure to large mass 5 uniform 0.2 1.8

Exposure to small mass 5 customc 0.1 10

Steel object on body 5 uniform 0.7 1.3

Driver–automobile 5 uniform 0.9 1.1

Home with steel studs 5 uniform 0.9 1.1

Sailor–hull plate (bunk) 5 uniform 0.87 1.13

Sailor–hull plate (center) 4 fixed 1

Steel ship scenarios 1 fixed 1

Driver–diesel engine (driving) 5 uniform 0.8 1.2

Driver–diesel engine (sleeping) 5 uniform 0.9 1.1

Building road with slag 5 fixed 1

Scrap truck–driver 5 uniform 0.7 1.3

Slag truck–driver 5 uniform 0.7 1.3

EAF dust–bulk trailer 5 uniform 0.8 1.2

EAF dust–dump trailer (driving) 5 uniform 0.88 1.12

a

 Fixed value

b

 Not used

c

 See Section C.2.6
Appendix B Parameter Values

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 X = 50 + 1950 Beta (", $), " = 0.476934, $ = 3.638114

d

 See Table B.13

B-19 NUREG-1640

Ux uncertainty parameter for external exposure

EAF dust–dump trailer (sleeping) 5 uniform 0.91 1.09

Metal product–driver 5 uniform 0.7 1.3

all disposal scenarios 1 fixed 1

v average speed (mph)

Driving on slag road 3 fixed 33.6

Slag truck–driver 5 uniform 40 50

EAF dust–bulk trailer 4 triangular 50 40 60

EAF dust–dump trailer 4 triangular 50 40 60

Metal product–driver 4 triangular 50 40 60

w width of typical highway (m)

Driving on slag road 3 fixed 7.315

X distance traveled (miles)

Slag truck–driver 6 fixed 60

EAF dust–bulk trailer 4 triangular 1000 65 2000

EAF dust–dump trailer 4 triangular 1000 65 2000

Metal product–driver 4 customc 276 50 2000

x distance from release point to receptor (m)

Airborne emissions 1 fixed 1000

xo distance from landfill boundary to nearest receptor well (m)

all groundwater scenarios 3 customd 0.6 1609.3

Yv yield of plant v (kg wet&weight plant/m2

): Airborne emissions

fruit 4 fixed 2.0

leafy vegetables 4 fixed 2.0

non-leafy vegetables 4 fixed 4.0

stored hay 4 fixed 1.5

stored grain 4 fixed 1.0

fresh forage 4 fixed 1.5

)z thickness of vadose zone (m)

all groundwater scenarios 3 customd 0.305 610

8r turnover rate of slag (y-1)

Leachate–steel slag 6 fixed 2

8w weathering constant at harvest (d-1)

fresh forage 4 fixed 0.0495

Da bulk density of aquifer (g/cm3)

all groundwater scenarios 3 customd 1.16 1.8

a

 Mode of triangular, mean of custom distribution, or fixed value

b

 Not used
Parameter Values Appendix B

Table B.8 Radionuclide-independent parameters of exposure scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviationb Min. Max.

c

 See Table B.13

d

 Mean of distribution

e

 Standard deviation of distribution

f

 See Section 3.7.1.1 in main report

NUREG-1640 B-20

Dg specific gravity (bulk density [g/cm3]) of slag

all scenarios where used 6 fixed 2

Dv bulk density of vadose zone (g/cm3)

all groundwater scenarios 3 customc 1.6 1.67

Dw waste density (g/cm3)

all groundwater landfill scenarios 3 customc 0.7 2.08

P/Q annual average atmospheric dispersion factor (s/m3)

Airborne emissions 2 lognormal 4.605e-06d 1.837e-06e 1.1e-06 1.7e-05

PC concentration of stable carbon (as CO2) in the atmosphere (g/m3)

Airborne emissions 2 fixed 0.16

Pd mass loading of material (mg/m3)

Scrap yard 2 customf 1.170 0.078 0.962 1.378

Handling slag 4 lognormal 2.433 1.27 5.0

Transferring EAF dust 4 lognormal 2.433 1.27 5.0

Handling metal product 4 lognormal 2.433 1.27 5.0

Processing EAF dust 4 lognormal 2.433 1.27 5.0

Processing steel slag 4 lognormal 2.433 1.27 5.0

Building road with slag 4 lognormal 2.433 1.27 5.0

Slag truck–driver 4 lognormal 4.78 2.65

EAF dust–dump trailer 4 lognormal 2.433 1.27 5.0

Slag disposal–industrial 4 lognormal 2.433 1.27 5.0

Slag disposal–municipal 4 lognormal 2.433 1.27 5.0

Pdd, Ps concentration of resuspended soil for dusty activities outdoors and soil blown indoors (g/m3)

Airborne emissions 2 lognormal 0.003 1.45 0 —

Pdo concentration of resuspended soil for normal activities outdoors (g/m3)

Airborne emissions 5 uniform 1e-05 2e-03

a

 Mode of lognormal, mean of custom distribution, or fixed value (except as noted)

b Standard deviation of custom distribution, or geometric standard deviation of lognormal distribution (except as noted)
Appendix B Parameter Values

B-21 NUREG-1640

Table B.9 Radionuclide-independent parameters specific to copper scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mode or

fixed value FD, Fg

a Min. Max.

CCu concentration of Cu in H2O (g/mL)

Drinking!copper pipes 4 triangular 3.0e-07 2e-07 0

ffr fraction of Cu scrap consumed by fire-refining furnaces (dimensionless)

Airborne emissions 3 fixed 0.286

Is secondary ingestion rate (g/h)

Scrap yard, handling metal product 5 uniform 0 4.0e-03

mCu mass of Cu scrap cleared from 1 reactor (g)

all scenarios where used 4 fixed 6.2e+07

Mfr combined capacity of all U.S. fire-refining facilities (g)

Airborne emissions 3 fixed 2.71e+11

NR number of reactors scheduled for dismantlement

Airborne emissions 1 fixed 118

ts time from release of cleared material from nuclear facility to time scenario begins (d)

Scrap yard 5 uniform 3 36

Handling metal product 5 uniform 4 41

Handling slag 5 uniform 4 41

Baghouse maintenance 5 uniform 4 41

Airborne emissions 5 uniform 4 41

Scrap truck!driver 5 uniform 2 6

Metal product!driver 5 uniform 7 71

Slag truck!driver 5 uniform 6 44

Dust truck!driver 5 uniform 34 101

Exposure to small mass 5 uniform 17 131

Copper object on body 5 uniform 17 131

Drinking!copper pipes 5 uniform 17 341

Scrap disposal!industrial & municipal 5 uniform 3 13

Slag disposal!industrial & municipal 5 uniform 7 51

tys exposure duration (d/y)

Drinking!copper pipes 4 triangular 300 250 300

Ux uncertainty parameter for external exposure

Scrap yard 5 uniform 0.36 1.64

Handling slag 5 fixed 1

Metal product!driver (driver’s seat) 5 uniform 0.9 1.1

Metal product!driver (sleeper) 5 uniform 0.93 1.07

v average speed (mph)

all transportation scenarios 4 triangular 50 40 60

X distance traveled (mi)

Scrap, slag, and dust trucks!driver 2 normal 130 15.1 50 —

Metal product!driver 2 lognormal 393 40.09 50 2000

Pd mass loading of material (mg/m3)

Scrap yard, handling metal product 4 lognormal 0.4865 0.127218 1.0

Handling slag 4 lognormal 1.2162 0.127218 2.5 a

 Standard deviation of normal distribution, geometric standard deviation of lognormal
Parameter Values Appendix B

NUREG-1640 B-22

Table B.10 Radionuclide-independent parameters specific to aluminum scenarios

Symbol

Parameter description/scenario

Data quality

Distribution

Mean, mode,

or fixed valuea FD

b Min. Max.

mAl intake of aluminum from cookware (g/d)

Aluminum cookware 6 fixed 3.5e-03

MAl mass of Al scrap cleared from 1 reactor (g)

all scenarios where used 5 uniform 1.2e+06 2.0e+06

ts time from release of cleared material from nuclear facility to time scenario begins (d)

Scrap yard 5 uniform 3 36

Baghouse maintenance 5 uniform 4 51

Handling metal product 5 uniform 4 51

Dross handling 5 uniform 4 51

Airborne emissions 5 uniform 4 51

Scrap truck!driver 5 uniform 2 6

Metal product!driver 5 uniform 7 81

Dross and dust truck!driver 5 uniform 34 111

Scrap disposal 5 uniform 3 13

Dross disposal 5 uniform 35 118

Exposure to large or small mass 5 uniform 17 141

Driver!engine block 5 uniform 25 204

Aluminum cookware 5 uniform 17 141

txs daily exposure duration 

Exposure to large mass (h/d) 4 triangular 4 2 7

Aluminum cookware (min/d) 2 lognormal 52.37 52.9 1.00 —

tys exposure duration (d/y)

Exposure to large mass 6 fixed 250

Aluminum cookware 1 fixed 365

Ux uncertainty parameter for external exposure

Scrap yard 5 uniform 0.5 1.5

Dross handling 5 uniform 0.4 1.6

Cookware 5 fixed 1

Exposure to small mass 5 customc 1 0.2 6.62

Dust truck—driver 5 uniform 0.7 1.3

v average speed (mph)

all transportation scenarios 4 triangular 50 40 60

X distance traveled (mi)

Scrap, dross, and dust truck!driver 2 normal 130 15.1 50 —

Metal product!driver 2 lognormal 393 40.1 50 2000

Pd mass loading of material (mg/m3)

All handling & disposal scenarios, where used 4 lognormal 2.433d 1.27e — 5.0 a

 Mode of triangular, mean of custom, normal or lognormal distributions, unless otherwise noted b

 Standard deviation, unless otherwise noted

c

 See Section C.4.4

d

 Geometric mean

e

 Geometric standard deviation
Appendix B Parameter Values

B-23 NUREG-1640

Table B.11 Radionuclide-independent parameter definitions specific to concrete scenarios Symbol

Parameter description/scenario

Data quality

Distribution

Mean,

mode, or

fixed

valuea

Standard

deviation Min. Max.

rate of road production (m2/d) 

concrete road scenarios 4 fixed 1657

Pd10 8-hour time-weighted average limit of respirable concrete dust (mg/m3)

all scenarios where parameter is used 4 lognormal 0.07 0.017 — 0.14

X distance traveled (mi)

Truck driver 2 normal 231 24.3 50

db thickness of road base (cm)

concrete road scenarios 4 fixed 30.5

dc thickness of concrete (cm)

concrete road scenarios 4 fixed 10.2

fc fraction of recycled concrete material in asphaltic concrete

concrete road scenarios 4 triangular 0.24 0.1 0.8

ts time from release of cleared material from nuclear facility to time scenario begins (d)

Processing concrete 5 uniform 2 30

Truck driver 5 uniform 3 60

Road building 5 uniform 4 75

Driving on road 5 uniform 5b 76b

Disposal!industrial 5 uniform 4 67

Disposal!MSW 5 uniform 4 67

tyh weekly exposure duration (h/wk)

Truck driver 4 triangular 28 22 36.5

Ux uncertainty in geometry factor (dimensionless)

Processing concrete 5 uniform 0.6 1.4

Truck driver 5 uniform 0.7 1.3

Db bulk density of RCM (g/cm3)

concrete road scenarios 3 fixed 1.4

Dc mass density of concrete (g/cm3)

concrete road scenarios 2 fixed 2.4 a

 Mean of lognormal, mode of triangular distributions

b

 In addition to time needed to construct road (calculated)

Table B.12 Time spent on various activities: continuous cumulative distributions

Symbol Parameter

description

Percentile/

time

tdd time spent on dusty activities outdoors (h/mo)

CDF (%) 5 75 90 95 98 99 100

Value (h/mo) 0 3 15 40 88 160 320

tv time spent in automobile (min/d)

CDF (%) 0 5 25 50 75 90 95 98 99 100

Value (min/d) 1 10 34 63 110 175 240 345 450 1280

Note: Continuous cumulative distributions are described in Section B.2.6
Parameter Values Appendix B

NUREG-1640 B-24

Table B.13 Hydrogeological parameters: custom distributions

Symbol

Parameterdescription

CDF (%)

0 10 25 50 75 90 100

I infiltration rate (m/y) (# Ksv)

Valuea 1.00e-05 1.88e-02 3.50e-02 4.32e-02 4.77e-02 4.86e-02 5.26e-02

J Ksa seepage velocity (m/y)

Logarithmb -2.30259 0.770108 2.155245 3.735286 5.393628 6.984716 9.287301

Ksv saturated hydraulic conductivity of vadose zone (m/y)

Logarithm -5.58068 -0.51751 0.732368 2.076938 3.575151 5.123964 7.803843

pea effective porosity of aquifer

Value 0.05 0.103 0.163 0.236 0.296 0.334 0.426

)z thickness of vadose zone (m)

Logarithm -1.18744 0.41871 1.115142 1.673351 2.639057 3.417727 6.413459

Da bulk density of aquifer (g/cm3)

Value 1.16 1.29 1.43 1.56 1.63 1.7 1.8

Dw waste density (g/cm3)

Logarithm -0.35667 -0.30653 -0.23319 -0.11991 0.285179 0.378436 0.732368

dL depth of contaminated zone (m)

CDF (%) 0 33.33333 66.66667 86.66667 100

Logarithm 0.277632 0.951658 1.408545 1.822935 2.312535

dw depth of well below water table (m)

CDF (%) 0 38.46154 76.92308 100

Logarithm 0.806476 1.702928 2.587764 3.561046

ptv total porosity of vadose zone

Probability (%) 10 40 50

Value (discrete) 0.41 0.43 0.45

Dv bulk density of vadose zone (g/cm3)

Probability (%) 10 65 25

Value (discrete) 1.6 1.65 1.67

Note: All parameters have continuous cumulative distributions except ptv and Dv, which have discrete distributions. These

distributions are described in Section B.2.6.

a

 Value of parameter corresponding to each percentile

b

 “ Logarithm” = natural logarithm of parameter value 

Table B.14 Distance from landfill boundary to nearest well: continuous cumulative distribution

xo (m) CDF (%) xo (m) CDF (%) xo (m) CDF (%)

0.6 0 304.8 30 804.6 70

13.7 3 304.8 35 868.6 75

19.8 4 365.7 40 914.4 80

45.7 5 396.2 45 1158.2 85

103.6 10 426.7 50 1219.1 90

152.4 15 457.2 55 1371.5 95

182.9 20 609.6 60 1523.9 98

243.8 25 762.0 65 1609.3 100

Note: Continuous cumulative distributions are described in Section B.2.6
Appendix B Parameter Values

B-25 NUREG-1640

Table B.15 Radioactive decay data

Nuclide Half-life 8 (d-1) Nuclide Half-life 8 (d-1)

H-3 12.35 y 1.54e-04 Sm-151 90 y 2.11e-05

C-14 5730 y 3.31e-07 Eu-152 13.33 y 1.42e-04

Na-22 2.60 y 7.29e-04 Eu-154 8.8 y 2.16e-04

P-32 14.29 d 4.85e-02 Eu-155 4.96 y 3.83e-04

S-35 87.44 d 7.93e-03 Gd-153 242 d 2.86e-03

Cl-36 3.01e+05 y 6.30e-09 Tb-160 72.3 d 9.59e-03

K-40 1.28e+09 y 1.48e-12 Tm-170 128.6 d 5.39e-03

Ca-41 1.40e+05 y 1.36e-08 Tm-171 1.92 y 9.88e-04

Ca-45 163 d 4.25e-03 Ta-182 115 d 6.03e-03

Sc-46 83.83 d 8.27e-03 W-181 121.2 d 5.72e-03

Cr-51 27.704 d 2.50e-02 W-185 75.1 d 9.23e-03

Mn-53 3.70e+06 y 5.13e-10 Os-185 94 d 7.37e-03

Mn-54 312.5 d 2.22e-03 Ir-192 74.02 d 9.36e-03

Fe-55 2.7 y 7.03e-04 Tl-204 3.779 y 5.02e-04

Fe-59 44.53 d 1.56e-02 Pb-210 22.3 y 8.51e-05

Co-56 78.76 d 8.80e-03 Bi-207 38 y 4.99e-05

Co-57 270.9 d 2.56e-03 Po-210 138.376 d 5.01e-03

Co-58 70.8 d 9.79e-03 Ra-226 1600 y 1.19e-06

Co-60 5.271 y 3.60e-04 Ra-228 5.75 y 3.30e-04

Ni-59 75,000 y 2.53e-08 Ac-227 21.772 y 8.72e-05

Ni-63 96 y 1.98e-05 Th-228 1.9131 y 9.92e-04

Zn-65 243.9 d 2.84e-03 Th-229 7340 y 2.59e-07

As-73 80.3 d 8.63e-03 Th-230 75380 y 2.52e-08

Se-75 119.8 d 5.79e-03 Th-232 1.410e+10 y 1.35e-13

Sr-85 64.84 d 1.07e-02 Pa-231 32,760 y 5.79e-08

Sr-89 50.5 d 1.37e-02 U-232 68.9 y 2.75e-05

Sr-90 28.78 y 6.59e-05 U-233 159,200 y 1.19e-08

Y-91 58.51 d 1.18e-02 U-234 2.455e+06 y 7.73e-10

Zr-93 1.53e+06 y 1.24e-09 U-235 704000000 y 2.70e-12

Zr-95 64.02 d 1.08e-02 U-236 2.3415e+07 y 8.10e-11

Nb-93m 16.13 y 1.18e-04 U-238 4.470e+09 y 4.25e-13

Nb-94 20,300 y 9.35e-08 Np-237 2.14e+06 y 8.87e-10

Nb-95 34.975 d 1.98e-02 Pu-236 2.858 y 6.64e-04

Mo-93 4,000 y 4.74e-07 Pu-238 87.7 y 2.16e-05

Tc-97 2.60e+06 y 7.30e-10 Pu-239 24,110 y 7.87e-08

Tc-97m 87 d 7.97e-03 Pu-240 6,563 y 2.89e-07

Tc-99 2.13e+05 y 8.91e-09 Pu-241 14.35 y 1.32e-04

Ru-103 39.26 d 1.77e-02 Pu-242 373000000 y 5.09e-12

Ru-106 373.59 d 1.86e-03 Pu-244 8.08e+07 y 2.35e-11

Ag-108m 418 y 4.54e-06 Am-241 432.2 y 4.39e-06

Ag-110m 249.79 d 2.77e-03 Am-242m 141 y 1.35e-05

Cd-109 462.6 d 1.50e-03 Am-243 7370 y 2.57e-07

Sn-113 115.09 d 6.02e-03 Cm-242 162.8 d 4.26e-03

Sb-124 60.2 d 1.15e-02 Cm-243 29.1 y 6.52e-05

Sb-125 2.7582 y 6.88e-04 Cm-244 18.1 y 1.05e-04

Te-123m 119.7 d 5.79e-03 Cm-245 8,500 y 2.23e-07

Te-127m 109 d 6.36e-03 Cm-246 4,730 y 4.01e-07

I-125 60.14 d 1.15e-02 Cm-247 1.56e+07 y 1.22e-10

I-129 1.57e+07 y 1.21e-10 Cm-248 3.39e+05 y 5.60e-09

I-131 8.04 d 8.62e-02 Bk-249 320 d 2.17e-03

Cs-134 2.062 y 9.20e-04 Cf-248 333.5 d 2.08e-03

Cs-135 2.30e+06 y 8.25e-10 Cf-249 351 y 5.41e-06

Cs-137 30.07 y 6.31e-05 Cf-250 13.08 y 1.45e-04

Ba-133 10.74 y 1.77e-04 Cf-251 898 y 2.11e-06

Ce-139 137.66 d 5.04e-03 Cf-252 2.638 y 7.19e-04

Ce-141 32.501 d 2.13e-02 Cf-254 60.5 d 1.15e-02

Ce-144 0.781 y 2.43e-03 Es-254 275.7 d 2.51e-03

Pm-147 2.6234 y 7.23e-04
Parameter Values Appendix B

NUREG-1640 B-26

Table B.16 Dose conversion factors for inhalation—effective dose equivalent (:Sv/Bq)

Nuclide Scrap/

concrete

Metal product Slag/dross/dust/airborne

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

H-3 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05

C-14 5.64e-04 5.64e-04 5.64e-04 5.64e-04 6.36e-06 5.64e-04 5.64e-04

Na-22 2.07e-03 2.07e-03 2.07e-03 2.07e-03 2.07e-03 2.07e-03 2.07e-03

P-32 4.19e-03 1.64e-03 1.64e-03 1.64e-03 1.64e-03 1.64e-03 1.64e-03

S-35 6.69e-04 8.15e-05 6.69e-04 8.15e-05 6.69e-04 6.69e-04 6.69e-04

Cl-36 5.93e-03 5.93e-03 5.93e-03 5.93e-03 5.93e-03 5.93e-03 5.93e-03

K-40 3.34e-03 3.34e-03 3.34e-03 3.34e-03 3.34e-03 3.34e-03 3.34e-03

Ca-41 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04

Ca-45 1.79e-03 1.79e-03 1.79e-03 1.79e-03 1.79e-03 1.79e-03 1.79e-03

Sc-46 8.01e-03 8.01e-03 8.01e-03 8.01e-03 8.01e-03 8.01e-03 8.01e-03

Cr-51 9.03e-05 9.03e-05 9.03e-05 9.03e-05 9.03e-05 9.03e-05 9.03e-05

Mn-53 1.35e-04 1.35e-04 1.35e-04 1.35e-04 1.35e-04 1.35e-04 1.35e-04

Mn-54 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03

Fe-55 7.26e-04 3.61e-04 3.61e-04 3.61e-04 3.61e-04 3.61e-04 3.61e-04

Fe-59 4.00e-03 3.30e-03 3.30e-03 3.30e-03 3.30e-03 3.30e-03 3.30e-03

Co-56 1.07e-02 1.07e-02 1.07e-02 1.07e-02 1.07e-02 1.07e-02 1.07e-02

Co-57 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03

Co-58 2.94e-03 2.94e-03 2.94e-03 2.94e-03 2.94e-03 2.94e-03 2.94e-03

Co-60 5.91e-02 5.91e-02 5.91e-02 5.91e-02 5.91e-02 5.91e-02 5.91e-02

Ni-59 3.58e-04 3.58e-04 3.58e-04 3.58e-04 2.48e-04 2.48e-04 3.58e-04

Ni-63 8.39e-04 8.39e-04 8.39e-04 8.39e-04 6.22e-04 6.22e-04 8.39e-04

Zn-65 5.51e-03 5.51e-03 5.51e-03 5.51e-03 5.51e-03 5.51e-03 5.51e-03

As-73 9.34e-04 9.34e-04 9.34e-04 9.34e-04 9.34e-04 9.34e-04 9.34e-04

Se-75 2.29e-03 2.29e-03 2.29e-03 2.29e-03 2.29e-03 2.29e-03 1.95e-03

Sr-85 5.18e-04 1.36e-03 5.18e-04 5.18e-04 5.18e-04 5.18e-04 5.18e-04

Sr-89 1.76e-03 1.12e-02 1.76e-03 1.76e-03 1.76e-03 1.76e-03 1.76e-03

Sr-90 6.70e-02 3.53e-01 6.70e-02 6.70e-02 6.70e-02 6.70e-02 6.68e-02

Y-91 1.32e-02 1.32e-02 1.32e-02 1.32e-02 1.32e-02 1.32e-02 8.72e-03

Zr-93 2.25e-02 8.67e-02 2.25e-02 2.25e-02 2.25e-02 2.25e-02 2.25e-02

Zr-95 4.30e-03 6.40e-03 4.30e-03 4.30e-03 4.30e-03 4.30e-03 4.30e-03

Nb-93m 7.90e-03 7.90e-03 7.90e-03 7.90e-03 7.90e-03 7.90e-03 7.90e-03

Nb-94 1.12e-01 1.12e-01 1.12e-01 1.12e-01 1.12e-01 1.12e-01 1.12e-01

Nb-95 1.57e-03 1.57e-03 1.57e-03 1.57e-03 1.57e-03 1.57e-03 1.57e-03

Mo-93 7.68e-03 7.68e-03 7.68e-03 7.68e-03 7.68e-03 7.68e-03 7.68e-03

Tc-97 2.68e-04 2.68e-04 2.68e-04 2.68e-04 2.68e-04 2.68e-04 2.68e-04

Tc-97m 1.32e-03 1.32e-03 1.32e-03 1.32e-03 1.32e-03 1.32e-03 1.32e-03

Tc-99 2.25e-03 2.25e-03 2.25e-03 2.25e-03 2.25e-03 2.25e-03 2.25e-03

Ru-103 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03

Ru-106 1.29e-01 1.29e-01 1.29e-01 1.29e-01 1.29e-01 1.29e-01 1.29e-01

Ag-108m 7.66e-02 8.14e-03 8.14e-03 8.14e-03 8.14e-03 7.66e-02 7.66e-02

Ag-110m 2.17e-02 1.07e-02 1.07e-02 1.07e-02 1.07e-02 2.17e-02 2.17e-02

Cd-109 3.09e-02 3.09e-02 1.22e-02 1.22e-02 1.22e-02 1.22e-02 1.07e-02

Sn-113 2.89e-03 2.89e-03 2.89e-03 2.89e-03 2.89e-03 2.89e-03 2.89e-03

Sb-124 6.80e-03 6.80e-03 6.80e-03 6.80e-03 6.80e-03 6.80e-03 6.80e-03

Sb-125 3.75e-03 3.75e-03 3.75e-03 3.75e-03 3.75e-03 3.75e-03 3.75e-03

Te-123m 2.86e-03 2.86e-03 2.86e-03 2.86e-03 2.86e-03 2.86e-03 2.86e-03

Te-127m 5.89e-03 5.89e-03 5.89e-03 5.89e-03 5.89e-03 5.89e-03 5.89e-03

I-125 6.53e-03 6.53e-03 6.53e-03 6.53e-03 6.53e-03 6.53e-03 6.53e-03

I-129 4.69e-02 4.69e-02 4.69e-02 4.69e-02 4.69e-02 4.69e-02 4.69e-02

I-131 8.89e-03 8.89e-03 8.89e-03 8.89e-03 8.89e-03 8.89e-03 8.89e-03

Cs-134 1.25e-02 1.25e-02 1.25e-02 1.25e-02 1.25e-02 1.25e-02 1.25e-02

Cs-135 1.23e-03 1.23e-03 1.23e-03 1.23e-03 1.23e-03 1.23e-03 1.23e-03

Cs-137 8.63e-03 8.63e-03 8.63e-03 8.63e-03 8.63e-03 8.63e-03 8.63e-03

Ba-133 2.11e-03 2.11e-03 2.11e-03 2.11e-03 2.11e-03 2.11e-03 2.11e-03

Ce-139 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03 2.45e-03

Ce-141 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03 2.42e-03

Ce-144 1.01e-01 1.01e-01 1.01e-01 1.01e-01 1.01e-01 1.01e-01 1.01e-01

Pm-147 1.06e-02 1.06e-02 1.06e-02 1.06e-02 1.06e-02 1.06e-02 6.97e-03
Appendix B Parameter Values

Table B.16 Dose conversion factors for inhalation—effective dose equivalent (:Sv/Bq)

Nuclide Scrap/

concrete

Metal product Slag/dross/dust/airborne

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

B-27 NUREG-1640

Sm-151 8.10e-03 8.10e-03 8.10e-03 8.10e-03 8.10e-03 8.10e-03 8.10e-03

Eu-152 5.97e-02 5.97e-02 5.97e-02 5.97e-02 5.97e-02 5.97e-02 5.97e-02

Eu-154 7.73e-02 7.73e-02 7.73e-02 7.73e-02 7.73e-02 7.73e-02 7.73e-02

Eu-155 1.12e-02 1.12e-02 1.12e-02 1.12e-02 1.12e-02 1.12e-02 1.12e-02

Gd-153 2.56e-03 6.43e-03 2.56e-03 6.43e-03 2.56e-03 2.56e-03 6.43e-03

Tb-160 6.75e-03 6.75e-03 6.75e-03 6.75e-03 6.75e-03 6.75e-03 6.75e-03

Tm-170 7.11e-03 7.11e-03 7.11e-03 7.11e-03 7.11e-03 7.11e-03 7.11e-03

Tm-171 2.47e-03 2.47e-03 2.47e-03 2.47e-03 2.47e-03 2.47e-03 2.47e-03

Ta-182 1.21e-02 1.21e-02 1.21e-02 1.21e-02 1.21e-02 1.21e-02 1.21e-02

W-181 4.09e-05 4.09e-05 4.09e-05 4.09e-05 4.09e-05 4.09e-05 4.09e-05

W-185 2.03e-04 2.03e-04 2.03e-04 2.03e-04 2.03e-04 2.03e-04 2.03e-04

Os-185 2.68e-03 2.68e-03 2.68e-03 2.68e-03 2.68e-03 2.68e-03 2.68e-03

Ir-192 7.61e-03 4.88e-03 4.88e-03 4.88e-03 7.61e-03 7.61e-03 7.61e-03

Tl-204 6.50e-04 6.50e-04 6.50e-04 6.50e-04 6.50e-04 6.50e-04 6.50e-04

Pb-210 6.04e+00 6.04e+00 6.04e+00 6.04e+00 6.04e+00 6.04e+00 6.04e+00

Bi-207 5.41e-03 5.41e-03 5.41e-03 5.41e-03 5.41e-03 5.41e-03 5.41e-03

Po-210 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00

Ra-226 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00 2.32e+00

Ra-228 1.32e+00 1.37e+00 1.32e+00 1.32e+00 1.32e+00 1.32e+00 1.31e+00

Ac-227 3.55e+02 1.82e+03 3.55e+02 3.55e+02 3.55e+02 3.55e+02 4.71e+02

Th-228 6.84e+01 9.32e+01 9.32e+01 9.32e+01 9.32e+01 9.32e+01 6.84e+01

Th-229 5.84e+02 5.85e+02 4.71e+02 4.71e+02 4.71e+02 4.71e+02 5.84e+02

Th-230 8.80e+01 8.80e+01 7.07e+01 7.07e+01 7.07e+01 7.07e+01 8.80e+01

Th-232 4.43e+02 4.43e+02 3.11e+02 3.11e+02 3.11e+02 3.11e+02 4.43e+02

Pa-231 3.47e+02 3.47e+02 2.32e+02 2.32e+02 2.32e+02 2.32e+02 3.47e+02

U-232 1.78e+02 1.78e+02 1.78e+02 1.78e+02 1.78e+02 1.78e+02 1.78e+02

U-233 3.66e+01 3.66e+01 3.66e+01 3.66e+01 3.66e+01 3.66e+01 3.66e+01

U-234 3.58e+01 3.58e+01 3.58e+01 3.58e+01 3.58e+01 3.58e+01 3.58e+01

U-235 3.32e+01 3.32e+01 3.32e+01 3.32e+01 3.32e+01 3.32e+01 3.32e+01

U-236 3.39e+01 3.39e+01 3.39e+01 3.39e+01 3.39e+01 3.39e+01 3.39e+01

U-238 3.20e+01 3.20e+01 3.20e+01 3.20e+01 3.20e+01 3.20e+01 3.20e+01

Np-237 1.46e+02 1.46e+02 1.46e+02 1.46e+02 1.46e+02 1.46e+02 1.46e+02

Pu-236 3.91e+01 3.91e+01 3.50e+01 3.50e+01 3.50e+01 3.50e+01 3.91e+01

Pu-238 1.06e+02 1.06e+02 7.79e+01 7.79e+01 7.79e+01 7.79e+01 1.06e+02

Pu-239 1.16e+02 1.16e+02 8.33e+01 8.33e+01 8.33e+01 8.33e+01 1.16e+02

Pu-240 1.16e+02 1.16e+02 8.33e+01 8.33e+01 8.33e+01 8.33e+01 1.16e+02

Pu-241 2.23e+00 2.23e+00 1.34e+00 1.34e+00 1.34e+00 1.34e+00 2.23e+00

Pu-242 1.11e+02 1.11e+02 7.92e+01 7.92e+01 7.92e+01 7.92e+01 1.11e+02

Pu-244 1.09e+02 1.09e+02 7.82e+01 7.82e+01 7.82e+01 7.82e+01 1.09e+02

Am-241 1.20e+02 1.20e+02 1.20e+02 1.20e+02 1.20e+02 1.20e+02 1.20e+02

Am-242m 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02

Am-243 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02 1.19e+02

Cm-242 4.67e+00 4.67e+00 4.67e+00 4.67e+00 4.67e+00 4.67e+00 4.67e+00

Cm-243 8.30e+01 8.30e+01 8.30e+01 8.30e+01 8.30e+01 8.30e+01 8.30e+01

Cm-244 6.70e+01 6.70e+01 6.70e+01 6.70e+01 6.70e+01 6.70e+01 6.70e+01

Cm-245 1.23e+02 1.23e+02 1.23e+02 1.23e+02 1.23e+02 1.23e+02 1.23e+02

Cm-246 1.22e+02 1.22e+02 1.22e+02 1.22e+02 1.22e+02 1.22e+02 1.22e+02

Cm-247 1.12e+02 1.12e+02 1.12e+02 1.12e+02 1.12e+02 1.12e+02 1.12e+02

Cm-248 4.47e+02 4.47e+02 4.47e+02 4.47e+02 4.47e+02 4.47e+02 4.47e+02

Bk-249 3.75e-01 3.75e-01 3.75e-01 3.75e-01 3.75e-01 3.75e-01 3.75e-01

Cf-248 1.37e+01 1.37e+01 1.37e+01 1.37e+01 1.37e+01 1.37e+01 1.20e+01

Cf-249 1.03e+02 1.56e+02 1.03e+02 1.03e+02 1.03e+02 1.03e+02 1.56e+02

Cf-250 5.57e+01 7.08e+01 5.57e+01 5.57e+01 5.57e+01 5.57e+01 7.08e+01

Cf-251 1.05e+02 1.59e+02 1.05e+02 1.05e+02 1.05e+02 1.05e+02 1.59e+02

Cf-252 4.24e+01 4.24e+01 4.24e+01 4.24e+01 4.24e+01 4.24e+01 3.70e+01

Cf-254 7.93e+01 7.93e+01 7.93e+01 7.93e+01 7.93e+01 7.93e+01 6.85e+01

Es-254 1.11e+01 1.11e+01 1.11e+01 1.11e+01 1.11e+01 1.11e+01 1.11e+01
Parameter Values Appendix B

NUREG-1640 B-28

Table B.17 Dose coefficients for inhalation—effective dose (:Sv/Bq)

Nuclide Scrap

metal Concrete Iron/steel Copper Aluminum

Metal Slag/dust Airborne Metal Slag Dust/air Metal Dross Dust/air

H-3 4.1e-05 4.1e-05 4.1e-05 4.1e-05 1.8e-05 4.1e-05 4.1e-05 4.1e-05 4.1e-05 4.1e-05 1.8e-05

C-14 5.8e-04 5.8e-04 5.8e-04 5.8e-04 6.5e-06 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04

Na-22 1.3e-03 2.0e-03 1.3e-03 2.0e-03 1.3e-03 1.3e-03 2.0e-03 1.3e-03 1.3e-03 2.0e-03 1.3e-03

P-32 3.2e-03 2.9e-03 8.0e-04 1.1e-03 8.0e-04 8.0e-04 1.1e-03 8.0e-04 8.0e-04 1.1e-03 8.0e-04

S-35 1.3e-03 1.1e-03 5.3e-05 1.1e-03 1.3e-03 1.3e-03 1.1e-03 1.3e-03 5.3e-05 1.3e-03 1.3e-03

Cl-36 6.9e-03 5.1e-03 6.9e-03 5.1e-03 6.9e-03 6.9e-03 5.1e-03 6.9e-03 6.9e-03 5.1e-03 6.9e-03

K-40 2.1e-03 3.0e-03 2.1e-03 3.0e-03 2.1e-03 2.1e-03 3.0e-03 2.1e-03 2.1e-03 3.0e-03 2.1e-03

Ca-41 1.7e-04 1.9e-04 1.7e-04 1.9e-04 1.7e-04 1.7e-04 1.9e-04 1.7e-04 1.7e-04 1.9e-04 1.7e-04

Ca-45 2.7e-03 2.3e-03 2.7e-03 2.3e-03 2.7e-03 2.7e-03 2.3e-03 2.7e-03 2.7e-03 2.3e-03 2.7e-03

Sc-46 6.4e-03 4.8e-03 6.4e-03 4.8e-03 6.4e-03 6.4e-03 4.8e-03 6.4e-03 6.4e-03 4.8e-03 6.4e-03

Cr-51 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05 3.6e-05

Mn-53 5.2e-05 3.6e-05 5.2e-05 3.6e-05 5.2e-05 5.2e-05 3.6e-05 5.2e-05 5.2e-05 3.6e-05 5.2e-05

Mn-54 1.5e-03 1.2e-03 1.5e-03 1.2e-03 1.5e-03 1.5e-03 1.2e-03 1.5e-03 1.5e-03 1.2e-03 1.5e-03

Fe-55 7.7e-04 9.2e-04 3.7e-04 3.3e-04 3.7e-04 3.7e-04 3.3e-04 3.7e-04 3.7e-04 3.3e-04 3.7e-04

Fe-59 2.2e-03 3.0e-03 3.5e-03 3.2e-03 3.5e-03 3.5e-03 3.2e-03 3.5e-03 3.5e-03 3.2e-03 3.5e-03

Co-56 6.3e-03 4.9e-03 6.3e-03 4.9e-03 6.3e-03 6.3e-03 4.9e-03 6.3e-03 6.3e-03 4.9e-03 6.3e-03

Co-57 9.4e-04 6.0e-04 9.4e-04 6.0e-04 9.4e-04 9.4e-04 6.0e-04 9.4e-04 9.4e-04 6.0e-04 9.4e-04

Co-58 2.0e-03 1.7e-03 2.0e-03 1.7e-03 2.0e-03 2.0e-03 1.7e-03 2.0e-03 2.0e-03 1.7e-03 2.0e-03

Co-60 2.9e-02 1.7e-02 2.9e-02 1.7e-02 2.9e-02 2.9e-02 1.7e-02 2.9e-02 2.9e-02 1.7e-02 2.9e-02

Ni-59 1.8e-04 2.2e-04 1.8e-04 9.4e-05 1.3e-04 1.8e-04 9.4e-05 1.3e-04 1.8e-04 2.2e-04 1.8e-04

Ni-63 4.4e-04 5.2e-04 4.4e-04 3.1e-04 4.4e-04 4.4e-04 3.1e-04 4.4e-04 4.4e-04 5.2e-04 4.4e-04

Zn-65 2.9e-03 2.8e-03 2.9e-03 2.8e-03 2.9e-03 2.9e-03 2.8e-03 2.9e-03 2.9e-03 2.8e-03 2.9e-03

As-73 9.3e-04 6.5e-04 9.3e-04 6.5e-04 9.3e-04 9.3e-04 6.5e-04 9.3e-04 9.3e-04 6.5e-04 9.3e-04

Se-75 1.4e-03 1.7e-03 1.4e-03 1.7e-03 1.4e-03 1.4e-03 1.7e-03 1.4e-03 1.4e-03 1.4e-03 1.0e-03

Sr-85 3.9e-04 5.6e-04 7.7e-04 5.6e-04 3.9e-04 3.9e-04 5.6e-04 3.9e-04 3.9e-04 5.6e-04 3.9e-04

Sr-89 1.0e-03 1.4e-03 7.5e-03 1.4e-03 1.0e-03 1.0e-03 1.4e-03 1.0e-03 1.0e-03 1.4e-03 1.0e-03

Sr-90 2.6e-02 3.2e-02 1.5e-01 3.2e-02 2.6e-02 2.6e-02 3.2e-02 2.6e-02 2.6e-02 3.1e-02 2.5e-02

Y-91 8.4e-03 6.1e-03 8.4e-03 6.1e-03 8.4e-03 8.4e-03 6.1e-03 8.4e-03 8.4e-03 5.2e-03 6.7e-03

Zr-93 9.6e-03 6.6e-03 2.5e-02 6.6e-03 9.6e-03 9.6e-03 6.6e-03 9.6e-03 9.6e-03 6.6e-03 9.6e-03

Zr-95 4.5e-03 3.6e-03 5.5e-03 3.6e-03 4.5e-03 4.5e-03 3.6e-03 4.5e-03 4.5e-03 3.6e-03 4.5e-03

Nb-93m 1.6e-03 8.6e-04 1.6e-03 8.6e-04 1.6e-03 1.6e-03 8.6e-04 1.6e-03 1.6e-03 8.6e-04 1.6e-03

Nb-94 4.5e-02 2.5e-02 4.5e-02 2.5e-02 4.5e-02 4.5e-02 2.5e-02 4.5e-02 4.5e-02 2.5e-02 4.5e-02

Nb-95 1.6e-03 1.3e-03 1.6e-03 1.3e-03 1.6e-03 1.6e-03 1.3e-03 1.6e-03 1.6e-03 1.3e-03 1.6e-03

Mo-93 2.2e-03 1.2e-03 2.2e-03 1.2e-03 2.2e-03 2.2e-03 1.2e-03 2.2e-03 2.2e-03 1.2e-03 2.2e-03

Tc-97 2.1e-04 1.6e-04 2.1e-04 1.6e-04 2.1e-04 2.1e-04 1.6e-04 2.1e-04 2.1e-04 1.6e-04 2.1e-04

Tc-97m 3.1e-03 2.7e-03 3.1e-03 2.7e-03 3.1e-03 3.1e-03 2.7e-03 3.1e-03 3.1e-03 2.7e-03 3.1e-03

Tc-99 3.9e-03 3.2e-03 3.9e-03 3.2e-03 3.9e-03 3.9e-03 3.2e-03 3.9e-03 3.9e-03 3.2e-03 3.9e-03

Ru-103 2.8e-03 2.2e-03 2.8e-03 2.2e-03 2.8e-03 2.8e-03 2.2e-03 2.8e-03 2.8e-03 2.8e-03 2.8e-03

Ru-106 6.2e-02 3.5e-02 6.2e-02 3.5e-02 6.2e-02 6.2e-02 3.5e-02 6.2e-02 6.2e-02 6.2e-02 6.2e-02

Ag-108m 3.5e-02 1.9e-02 6.1e-03 7.3e-03 6.1e-03 6.1e-03 3.5e-02 3.5e-02 6.1e-03 3.5e-02 3.5e-02

Ag-110m 1.2e-02 7.3e-03 5.5e-03 6.7e-03 5.5e-03 5.5e-03 1.2e-02 1.2e-02 5.5e-03 1.2e-02 1.2e-02

Cd-109 8.1e-03 9.6e-03 8.1e-03 4.4e-03 5.8e-03 5.8e-03 4.4e-03 5.8e-03 5.8e-03 5.1e-03 6.2e-03

Sn-113 2.5e-03 1.9e-03 2.5e-03 1.9e-03 2.5e-03 2.5e-03 1.9e-03 2.5e-03 2.5e-03 1.9e-03 2.5e-03

Sb-124 6.1e-03 4.7e-03 6.1e-03 4.7e-03 6.1e-03 6.1e-03 4.7e-03 6.1e-03 6.1e-03 4.7e-03 6.1e-03

Sb-125 5.3e-03 4.0e-03 5.3e-03 4.0e-03 5.2e-03 5.3e-03 4.1e-03 5.3e-03 5.3e-03 4.1e-03 5.3e-03

Te-123m 3.9e-03 3.4e-03 3.9e-03 3.4e-03 3.9e-03 3.9e-03 3.4e-03 3.9e-03 3.9e-03 3.4e-03 3.9e-03

Te-127m 7.3e-03 6.4e-03 7.3e-03 6.4e-03 7.4e-03 7.3e-03 6.3e-03 7.3e-03 7.3e-03 6.3e-03 7.3e-03

I-125 5.3e-03 7.3e-03 5.3e-03 7.3e-03 5.3e-03 5.3e-03 7.3e-03 5.3e-03 5.3e-03 7.3e-03 5.3e-03

I-129 3.7e-02 5.1e-02 3.7e-02 5.1e-02 3.7e-02 3.7e-02 5.1e-02 3.7e-02 3.7e-02 5.1e-02 3.7e-02

I-131 7.6e-03 1.1e-02 7.6e-03 1.1e-02 7.6e-03 7.6e-03 1.1e-02 7.6e-03 7.6e-03 1.1e-02 7.6e-03

Cs-134 6.8e-03 9.6e-03 6.8e-03 9.6e-03 6.8e-03 6.8e-03 9.6e-03 6.8e-03 6.8e-03 9.6e-03 6.8e-03

Cs-135 7.1e-04 9.9e-04 7.1e-04 9.9e-04 7.1e-04 7.1e-04 9.9e-04 7.1e-04 7.1e-04 9.9e-04 7.1e-04

Cs-137 4.8e-03 6.7e-03 4.8e-03 6.7e-03 4.8e-03 4.8e-03 6.7e-03 4.8e-03 4.8e-03 6.7e-03 4.8e-03

Ba-133 1.5e-03 1.8e-03 1.5e-03 1.8e-03 1.5e-03 1.5e-03 1.8e-03 1.5e-03 1.5e-03 1.8e-03 1.5e-03

Ce-139 1.8e-03 1.4e-03 1.8e-03 1.4e-03 1.8e-03 1.8e-03 1.4e-03 1.8e-03 1.8e-03 1.4e-03 1.8e-03

Ce-141 3.6e-03 3.1e-03 3.6e-03 3.1e-03 3.6e-03 3.6e-03 3.1e-03 3.6e-03 3.6e-03 3.1e-03 3.6e-03

Ce-144 4.9e-02 2.9e-02 4.9e-02 2.9e-02 4.9e-02 4.9e-02 2.9e-02 4.9e-02 4.9e-02 2.9e-02 4.9e-02

Pm-147 4.6e-03 3.2e-03 4.7e-03 3.2e-03 4.6e-03 4.6e-03 3.2e-03 4.6e-03 4.7e-03 3.5e-03 4.7e-03
Appendix B Parameter Values

Table B.17 Dose coefficients for inhalation—effective dose (:Sv/Bq)

Nuclide Scrap

metal Concrete Iron/steel Copper Aluminum

Metal Slag/dust Airborne Metal Slag Dust/air Metal Dross Dust/air

B-29 NUREG-1640

Sm-151 3.7e-03 2.6e-03 3.7e-03 2.6e-03 3.7e-03 3.7e-03 2.6e-03 3.7e-03 3.7e-03 2.6e-03 3.7e-03

Eu-152 3.9e-02 2.7e-02 3.9e-02 2.7e-02 3.9e-02 3.9e-02 2.7e-02 3.9e-02 3.9e-02 2.7e-02 3.9e-02

Eu-154 5.0e-02 3.5e-02 5.0e-02 3.5e-02 5.0e-02 5.0e-02 3.5e-02 5.0e-02 5.0e-02 3.5e-02 5.0e-02

Eu-155 6.5e-03 4.7e-03 6.5e-03 4.7e-03 6.5e-03 6.5e-03 4.7e-03 6.5e-03 6.5e-03 4.7e-03 6.5e-03

Gd-153 1.9e-03 1.4e-03 2.1e-03 1.4e-03 1.9e-03 1.9e-03 1.4e-03 1.9e-03 2.1e-03 2.5e-03 2.1e-03

Tb-160 6.6e-03 5.4e-03 6.6e-03 5.4e-03 6.6e-03 6.6e-03 5.4e-03 6.6e-03 6.6e-03 5.4e-03 6.6e-03

Tm-170 6.6e-03 5.2e-03 6.6e-03 5.2e-03 6.6e-03 6.6e-03 5.2e-03 6.6e-03 6.6e-03 5.2e-03 6.6e-03

Tm-171 1.3e-03 9.1e-04 1.3e-03 9.1e-04 1.3e-03 1.3e-03 9.1e-04 1.3e-03 1.3e-03 9.1e-04 1.3e-03

Ta-182 9.7e-03 7.4e-03 9.7e-03 7.4e-03 9.7e-03 9.7e-03 7.4e-03 9.7e-03 9.7e-03 7.4e-03 9.7e-03

W-181 2.8e-05 4.3e-05 2.8e-05 4.3e-05 2.8e-05 2.8e-05 4.3e-05 2.8e-05 2.8e-05 4.3e-05 2.8e-05

W-185 1.4e-04 2.2e-04 1.4e-04 2.2e-04 1.4e-04 1.4e-04 2.2e-04 1.4e-04 1.4e-04 2.2e-04 1.4e-04

Os-185 1.5e-03 1.1e-03 1.5e-03 1.1e-03 1.5e-03 1.5e-03 1.1e-03 1.5e-03 1.5e-03 1.1e-03 1.5e-03

Ir-192 6.2e-03 4.9e-03 4.9e-03 4.9e-03 6.2e-03 4.9e-03 4.9e-03 6.2e-03 4.9e-03 4.9e-03 6.2e-03

Tl-204 4.4e-04 6.2e-04 4.4e-04 6.2e-04 4.4e-04 4.4e-04 6.2e-04 4.4e-04 4.4e-04 6.2e-04 4.4e-04

Pb-210 4.0e+00 3.4e+00 4.0e+00 3.4e+00 3.2e+00 4.0e+00 4.2e+00 4.0e+00 4.0e+00 4.2e+00 4.0e+00

Bi-207 5.2e-03 3.2e-03 5.2e-03 3.2e-03 5.2e-03 5.2e-03 3.2e-03 5.2e-03 5.2e-03 3.2e-03 5.2e-03

Po-210 3.0e+00 2.2e+00 3.0e+00 2.2e+00 3.0e+00 3.0e+00 2.2e+00 3.0e+00 3.0e+00 2.2e+00 3.0e+00

Ra-226 3.2e+00 2.2e+00 3.2e+00 2.2e+00 3.2e+00 3.2e+00 2.2e+00 3.2e+00 3.2e+00 2.2e+00 3.2e+00

Ra-228 2.6e+00 1.7e+00 2.6e+00 1.7e+00 2.6e+00 2.6e+00 1.7e+00 2.6e+00 2.6e+00 1.7e+00 2.6e+00

Ac-227 8.1e+01 5.9e+01 5.6e+02 6.0e+01 7.9e+01 8.2e+01 6.3e+01 8.2e+01 8.2e+01 1.7e+02 2.3e+02

Th-228 3.4e+01 2.6e+01 4.2e+01 3.5e+01 4.2e+01 4.2e+01 3.5e+01 4.2e+01 4.2e+01 2.6e+01 3.4e+01

Th-229 1.1e+02 8.0e+01 1.1e+02 5.9e+01 7.6e+01 7.9e+01 6.2e+01 7.9e+01 7.9e+01 8.2e+01 1.1e+02

Th-230 4.0e+01 2.8e+01 4.0e+01 7.2e+00 1.3e+01 1.3e+01 7.2e+00 1.3e+01 1.3e+01 2.8e+01 4.0e+01

Th-232 4.2e+01 2.9e+01 4.2e+01 1.2e+01 2.3e+01 2.3e+01 1.2e+01 2.3e+01 2.3e+01 2.9e+01 4.2e+01

Pa-231 1.3e+02 8.9e+01 1.3e+02 1.7e+01 3.2e+01 3.2e+01 1.7e+01 3.2e+01 3.2e+01 8.9e+01 1.3e+02

U-232 3.5e+01 2.6e+01 3.5e+01 2.6e+01 3.5e+01 3.5e+01 2.6e+01 3.5e+01 3.5e+01 2.6e+01 3.5e+01

U-233 8.7e+00 6.9e+00 8.7e+00 6.9e+00 8.7e+00 8.7e+00 6.9e+00 8.7e+00 8.7e+00 6.9e+00 8.7e+00

U-234 8.5e+00 6.8e+00 8.5e+00 6.8e+00 8.5e+00 8.5e+00 6.8e+00 8.5e+00 8.5e+00 6.8e+00 8.5e+00

U-235 7.7e+00 6.1e+00 7.7e+00 6.1e+00 7.7e+00 7.7e+00 6.1e+00 7.7e+00 7.7e+00 6.1e+00 7.7e+00

U-236 7.9e+00 6.3e+00 7.9e+00 6.3e+00 7.9e+00 7.9e+00 6.3e+00 7.9e+00 7.9e+00 6.3e+00 7.9e+00

U-238 7.3e+00 5.7e+00 7.3e+00 5.7e+00 7.3e+00 7.3e+00 5.7e+00 7.3e+00 7.3e+00 5.7e+00 7.3e+00

Np-237 2.1e+01 1.5e+01 2.1e+01 1.5e+01 2.1e+01 2.1e+01 1.5e+01 2.1e+01 2.1e+01 1.5e+01 2.1e+01

Pu-236 1.8e+01 1.3e+01 1.8e+01 7.4e+00 9.6e+00 9.6e+00 7.4e+00 9.6e+00 9.6e+00 1.3e+01 1.8e+01

Pu-238 4.3e+01 3.0e+01 4.3e+01 1.1e+01 1.5e+01 1.5e+01 1.1e+01 1.5e+01 1.5e+01 3.0e+01 4.3e+01

Pu-239 4.7e+01 3.2e+01 4.7e+01 8.3e+00 1.5e+01 1.5e+01 8.3e+00 1.5e+01 1.5e+01 3.2e+01 4.7e+01

Pu-240 4.7e+01 3.2e+01 4.7e+01 8.3e+00 1.5e+01 1.5e+01 8.3e+00 1.5e+01 1.5e+01 3.2e+01 4.7e+01

Pu-241 8.5e-01 5.8e-01 8.5e-01 8.4e-02 1.6e-01 1.6e-01 8.4e-02 1.6e-01 1.6e-01 5.8e-01 8.5e-01

Pu-242 4.4e+01 3.1e+01 4.4e+01 7.7e+00 1.4e+01 1.4e+01 7.7e+00 1.4e+01 1.4e+01 3.1e+01 4.4e+01

Pu-244 4.4e+01 3.0e+01 4.4e+01 7.4e+00 1.3e+01 1.3e+01 7.4e+00 1.3e+01 1.3e+01 3.0e+01 4.4e+01

Am-241 3.9e+01 2.7e+01 3.9e+01 2.7e+01 3.9e+01 3.9e+01 2.7e+01 3.9e+01 3.9e+01 2.7e+01 3.9e+01

Am-242m 3.9e+01 2.7e+01 3.9e+01 2.7e+01 3.8e+01 3.9e+01 2.8e+01 3.9e+01 3.9e+01 2.8e+01 3.9e+01

Am-243 3.9e+01 2.7e+01 3.9e+01 2.7e+01 3.9e+01 3.9e+01 2.7e+01 3.9e+01 3.9e+01 2.7e+01 3.9e+01

Cm-242 4.8e+00 3.7e+00 4.8e+00 3.7e+00 4.8e+00 4.8e+00 3.7e+00 4.8e+00 4.8e+00 3.7e+00 4.8e+00

Cm-243 2.9e+01 2.0e+01 2.9e+01 2.0e+01 2.9e+01 2.9e+01 2.0e+01 2.9e+01 2.9e+01 2.0e+01 2.9e+01

Cm-244 2.5e+01 1.7e+01 2.5e+01 1.7e+01 2.5e+01 2.5e+01 1.7e+01 2.5e+01 2.5e+01 1.7e+01 2.5e+01

Cm-245 4.0e+01 2.7e+01 4.0e+01 2.7e+01 4.0e+01 4.0e+01 2.7e+01 4.0e+01 4.0e+01 2.7e+01 4.0e+01

Cm-246 4.0e+01 2.7e+01 4.0e+01 2.7e+01 4.0e+01 4.0e+01 2.7e+01 4.0e+01 4.0e+01 2.7e+01 4.0e+01

Cm-247 3.6e+01 2.5e+01 3.6e+01 2.5e+01 3.6e+01 3.6e+01 2.5e+01 3.6e+01 3.6e+01 2.5e+01 3.6e+01

Cm-248 1.4e+02 9.5e+01 1.4e+02 9.5e+01 1.4e+02 1.4e+02 9.5e+01 1.4e+02 1.4e+02 9.5e+01 1.4e+02

Bk-249 1.5e-01 1.0e-01 1.5e-01 1.0e-01 1.5e-01 1.5e-01 1.0e-01 1.5e-01 1.5e-01 1.0e-01 1.5e-01

Cf-248 8.2e+00 6.1e+00 8.2e+00 6.1e+00 8.2e+00 8.2e+00 6.1e+00 8.2e+00 8.2e+00 6.1e+00 8.2e+00

Cf-249 6.6e+01 4.5e+01 6.6e+01 4.5e+01 6.6e+01 6.6e+01 4.5e+01 6.6e+01 6.6e+01 4.5e+01 6.6e+01

Cf-250 3.2e+01 2.2e+01 3.2e+01 2.2e+01 3.2e+01 3.2e+01 2.2e+01 3.2e+01 3.2e+01 2.2e+01 3.2e+01

Cf-251 6.7e+01 4.6e+01 6.7e+01 4.6e+01 6.7e+01 6.7e+01 4.6e+01 6.7e+01 6.7e+01 4.6e+01 6.7e+01

Cf-252 1.8e+01 1.3e+01 1.8e+01 1.3e+01 1.8e+01 1.8e+01 1.3e+01 1.8e+01 1.8e+01 1.3e+01 1.8e+01

Cf-254 3.7e+01 2.2e+01 3.7e+01 2.2e+01 3.7e+01 3.7e+01 2.2e+01 3.7e+01 3.7e+01 2.2e+01 3.7e+01

Es-254 8.0e+00 6.0e+00 8.0e+00 6.0e+00 8.0e+00 8.0e+00 6.0e+00 8.0e+00 8.0e+00 6.0e+00 8.0e+00
Parameter Values Appendix B

NUREG-1640 B-30

Table B.18 Dose conversion factors for ingestion—effective dose equivalent (:Sv/Bq)

Nuclide Scrap/

concrete

Food/

water

Metal product Dust/slag/dross

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

H-3 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05 1.73e-05

C-14 5.64e-04 5.64e-04 5.64e-04 5.64e-04 5.64e-04 5.64e-04 5.64e-04 5.64e-04

Na-22 3.10e-03 3.10e-03 3.10e-03 3.10e-03 3.10e-03 3.10e-03 3.10e-03 3.10e-03

P-32 2.37e-03 2.37e-03 2.37e-03 2.37e-03 2.37e-03 2.37e-03 2.37e-03 2.37e-03

S-35 1.21e-04 1.21e-04 1.21e-04 1.21e-04 1.21e-04 1.21e-04 1.21e-04 1.21e-04

Cl-36 8.18e-04 8.18e-04 8.18e-04 8.18e-04 8.18e-04 8.18e-04 8.18e-04 8.18e-04

K-40 5.02e-03 5.02e-03 5.02e-03 5.02e-03 5.02e-03 5.02e-03 5.02e-03 5.02e-03

Ca-41 3.44e-04 3.44e-04 3.44e-04 3.44e-04 3.44e-04 3.44e-04 3.44e-04 3.44e-04

Ca-45 8.55e-04 8.55e-04 8.55e-04 8.55e-04 8.55e-04 8.55e-04 8.55e-04 8.55e-04

Sc-46 1.73e-03 1.73e-03 1.73e-03 1.73e-03 1.73e-03 1.73e-03 1.73e-03 1.73e-03

Cr-51 3.93e-05 3.98e-05 3.93e-05 3.93e-05 3.93e-05 3.98e-05 3.98e-05 3.98e-05

Mn-53 2.92e-05 2.92e-05 2.92e-05 2.92e-05 2.92e-05 2.92e-05 2.92e-05 2.92e-05

Mn-54 7.48e-04 7.48e-04 7.48e-04 7.48e-04 7.48e-04 7.48e-04 7.48e-04 7.48e-04

Fe-55 1.64e-04 1.64e-04 1.64e-04 1.64e-04 1.64e-04 1.64e-04 1.64e-04 1.64e-04

Fe-59 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03 1.81e-03

Co-56 2.73e-03 2.73e-03 2.73e-03 2.73e-03 2.73e-03 2.73e-03 2.73e-03 2.73e-03

Co-57 2.01e-04 2.01e-04 2.01e-04 2.01e-04 2.01e-04 2.01e-04 2.01e-04 2.01e-04

Co-58 8.09e-04 8.09e-04 8.09e-04 8.09e-04 8.09e-04 8.09e-04 8.09e-04 8.09e-04

Co-60 2.77e-03 2.77e-03 2.77e-03 2.77e-03 2.77e-03 2.77e-03 2.77e-03 2.77e-03

Ni-59 5.67e-05 5.67e-05 5.67e-05 5.67e-05 5.67e-05 5.67e-05 5.67e-05 5.67e-05

Ni-63 1.56e-04 1.56e-04 1.56e-04 1.56e-04 1.56e-04 1.56e-04 1.56e-04 1.56e-04

Zn-65 3.90e-03 3.90e-03 3.90e-03 3.90e-03 3.90e-03 3.90e-03 3.90e-03 3.90e-03

As-73 1.91e-04 1.91e-04 1.91e-04 1.91e-04 1.91e-04 1.91e-04 1.91e-04 1.91e-04

Se-75 2.60e-03 2.60e-03 2.60e-03 2.60e-03 2.60e-03 2.60e-03 2.60e-03 2.60e-03

Sr-85 5.34e-04 5.34e-04 5.34e-04 5.34e-04 5.34e-04 5.34e-04 5.34e-04 5.34e-04

Sr-89 2.50e-03 2.50e-03 2.50e-03 2.50e-03 2.50e-03 2.50e-03 2.50e-03 2.50e-03

Sr-90 4.14e-02 4.14e-02 4.14e-02 4.14e-02 4.14e-02 4.14e-02 4.14e-02 4.14e-02

Y-91 2.57e-03 2.57e-03 2.57e-03 2.57e-03 2.57e-03 2.57e-03 2.57e-03 2.57e-03

Zr-93 4.48e-04 4.48e-04 4.48e-04 4.48e-04 4.48e-04 4.48e-04 4.48e-04 4.48e-04

Zr-95 1.03e-03 1.03e-03 1.03e-03 1.03e-03 1.03e-03 1.03e-03 1.03e-03 1.03e-03

Nb-93m 1.41e-04 1.41e-04 1.41e-04 1.41e-04 1.41e-04 1.41e-04 1.41e-04 1.41e-04

Nb-94 1.93e-03 1.93e-03 1.93e-03 1.93e-03 1.93e-03 1.93e-03 1.93e-03 1.93e-03

Nb-95 6.95e-04 6.95e-04 6.95e-04 6.95e-04 6.95e-04 6.95e-04 6.95e-04 6.95e-04

Mo-93 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04 3.64e-04

Tc-97 4.63e-05 4.63e-05 4.63e-05 4.63e-05 4.63e-05 4.63e-05 4.63e-05 4.63e-05

Tc-97m 3.36e-04 3.36e-04 3.36e-04 3.36e-04 3.36e-04 3.36e-04 3.36e-04 3.36e-04

Tc-99 3.95e-04 3.95e-04 3.95e-04 3.95e-04 3.95e-04 3.95e-04 3.95e-04 3.95e-04

Ru-103 8.27e-04 8.27e-04 8.27e-04 8.27e-04 8.27e-04 8.27e-04 8.27e-04 8.27e-04

Ru-106 7.40e-03 7.40e-03 7.40e-03 7.40e-03 7.40e-03 7.40e-03 7.40e-03 7.40e-03

Ag-108m 2.06e-03 2.06e-03 2.06e-03 2.06e-03 2.06e-03 2.06e-03 2.06e-03 2.06e-03

Ag-110m 2.92e-03 2.92e-03 2.92e-03 2.92e-03 2.92e-03 2.92e-03 2.92e-03 2.92e-03

Cd-109 3.55e-03 3.55e-03 3.55e-03 3.55e-03 3.55e-03 3.55e-03 3.55e-03 3.55e-03

Sn-113 8.61e-04 8.61e-04 8.61e-04 8.61e-04 8.61e-04 8.61e-04 8.61e-04 8.61e-04

Sb-124 2.74e-03 2.74e-03 2.74e-03 2.74e-03 2.74e-03 2.74e-03 2.74e-03 2.74e-03

Sb-125 9.83e-04 9.83e-04 9.83e-04 9.83e-04 9.83e-04 9.83e-04 9.83e-04 9.83e-04

Te-123m 1.53e-03 1.53e-03 1.53e-03 1.53e-03 1.53e-03 1.53e-03 1.53e-03 1.53e-03

Te-127m 2.41e-03 2.41e-03 2.41e-03 2.41e-03 2.41e-03 2.41e-03 2.41e-03 2.41e-03

I-125 1.04e-02 1.04e-02 1.04e-02 1.04e-02 1.04e-02 1.04e-02 1.04e-02 1.04e-02

I-129 7.46e-02 7.46e-02 7.46e-02 7.46e-02 7.46e-02 7.46e-02 7.46e-02 7.46e-02

I-131 1.44e-02 1.44e-02 1.44e-02 1.44e-02 1.44e-02 1.44e-02 1.44e-02 1.44e-02

Cs-134 1.98e-02 1.98e-02 1.98e-02 1.98e-02 1.98e-02 1.98e-02 1.98e-02 1.98e-02

Cs-135 1.91e-03 1.91e-03 1.91e-03 1.91e-03 1.91e-03 1.91e-03 1.91e-03 1.91e-03

Cs-137 1.35e-02 1.35e-02 1.35e-02 1.35e-02 1.35e-02 1.35e-02 1.35e-02 1.35e-02

Ba-133 9.19e-04 9.19e-04 9.19e-04 9.19e-04 9.19e-04 9.19e-04 9.19e-04 9.19e-04

Ce-139 3.09e-04 3.09e-04 3.09e-04 3.09e-04 3.09e-04 3.09e-04 3.09e-04 3.09e-04

Ce-141 7.83e-04 7.83e-04 7.83e-04 7.83e-04 7.83e-04 7.83e-04 7.83e-04 7.83e-04

Ce-144 5.71e-03 5.71e-03 5.71e-03 5.71e-03 5.71e-03 5.71e-03 5.71e-03 5.71e-03

Pm-147 2.83e-04 2.83e-04 2.83e-04 2.83e-04 2.83e-04 2.83e-04 2.83e-04 2.83e-04
Appendix B Parameter Values

Table B.18 Dose conversion factors for ingestion—effective dose equivalent (:Sv/Bq)

Nuclide Scrap/

concrete

Food/

water

Metal product Dust/slag/dross

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

B-31 NUREG-1640

Sm-151 1.05e-04 1.05e-04 1.05e-04 1.05e-04 1.05e-04 1.05e-04 1.05e-04 1.05e-04

Eu-152 1.75e-03 1.75e-03 1.75e-03 1.75e-03 1.75e-03 1.75e-03 1.75e-03 1.75e-03

Eu-154 2.58e-03 2.58e-03 2.58e-03 2.58e-03 2.58e-03 2.58e-03 2.58e-03 2.58e-03

Eu-155 4.13e-04 4.13e-04 4.13e-04 4.13e-04 4.13e-04 4.13e-04 4.13e-04 4.13e-04

Gd-153 3.17e-04 3.17e-04 3.17e-04 3.17e-04 3.17e-04 3.17e-04 3.17e-04 3.17e-04

Tb-160 1.82e-03 1.82e-03 1.82e-03 1.82e-03 1.82e-03 1.82e-03 1.82e-03 1.82e-03

Tm-170 1.43e-03 1.43e-03 1.43e-03 1.43e-03 1.43e-03 1.43e-03 1.43e-03 1.43e-03

Tm-171 1.16e-04 1.16e-04 1.16e-04 1.16e-04 1.16e-04 1.16e-04 1.16e-04 1.16e-04

Ta-182 1.76e-03 1.76e-03 1.76e-03 1.76e-03 1.76e-03 1.76e-03 1.76e-03 1.76e-03

W-181 7.74e-05 7.74e-05 7.74e-05 7.74e-05 7.74e-05 7.74e-05 7.74e-05 7.74e-05

W-185 4.28e-04 4.28e-04 4.28e-04 4.28e-04 4.28e-04 4.28e-04 4.28e-04 4.28e-04

Os-185 6.11e-04 6.11e-04 6.11e-04 6.11e-04 6.11e-04 6.11e-04 6.11e-04 6.11e-04

Ir-192 1.55e-03 1.55e-03 1.55e-03 1.55e-03 1.55e-03 1.55e-03 1.55e-03 1.55e-03

Tl-204 9.08e-04 9.08e-04 9.08e-04 9.08e-04 9.08e-04 9.08e-04 9.08e-04 9.08e-04

Pb-210 1.97e+00 1.97e+00 1.97e+00 1.97e+00 1.97e+00 1.97e+00 1.97e+00 1.97e+00

Bi-207 1.48e-03 1.48e-03 1.48e-03 1.48e-03 1.48e-03 1.48e-03 1.48e-03 1.48e-03

Po-210 5.14e-01 5.14e-01 5.14e-01 5.14e-01 5.14e-01 5.14e-01 5.14e-01 5.14e-01

Ra-226 3.58e-01 3.58e-01 3.58e-01 3.58e-01 3.58e-01 3.58e-01 3.58e-01 3.58e-01

Ra-228 3.89e-01 3.89e-01 3.89e-01 3.89e-01 3.89e-01 3.89e-01 3.89e-01 3.89e-01

Ac-227 3.99e+00 3.99e+00 3.99e+00 3.99e+00 3.99e+00 3.99e+00 3.99e+00 3.99e+00

Th-228 2.18e-01 2.18e-01 2.18e-01 2.18e-01 2.18e-01 2.18e-01 2.18e-01 2.18e-01

Th-229 1.09e+00 1.09e+00 1.09e+00 1.09e+00 1.09e+00 1.09e+00 1.09e+00 1.09e+00

Th-230 1.48e-01 1.48e-01 1.48e-01 1.48e-01 1.48e-01 1.48e-01 1.48e-01 1.48e-01

Th-232 7.38e-01 7.38e-01 7.38e-01 7.38e-01 7.38e-01 7.38e-01 7.38e-01 7.38e-01

Pa-231 2.86e+00 2.86e+00 2.86e+00 2.86e+00 2.86e+00 2.86e+00 2.86e+00 2.86e+00

U-232 3.54e-01 3.54e-01 3.54e-01 3.54e-01 3.54e-01 1.87e-02 1.87e-02 3.54e-01

U-233 7.81e-02 7.81e-02 7.81e-02 7.81e-02 7.81e-02 7.15e-03 7.15e-03 7.81e-02

U-234 7.66e-02 7.66e-02 7.66e-02 7.66e-02 7.66e-02 7.06e-03 7.06e-03 7.66e-02

U-235 7.23e-02 7.23e-02 7.23e-02 7.23e-02 7.23e-02 7.59e-03 7.59e-03 7.23e-02

U-236 7.26e-02 7.26e-02 7.26e-02 7.26e-02 7.26e-02 6.68e-03 6.68e-03 7.26e-02

U-238 7.25e-02 7.25e-02 7.25e-02 7.25e-02 7.25e-02 1.01e-02 1.01e-02 7.25e-02

Np-237 1.20e+00 1.20e+00 1.20e+00 1.20e+00 1.20e+00 1.20e+00 1.20e+00 1.20e+00

Pu-236 3.15e-01 3.15e-01 3.15e-01 3.15e-01 3.15e-01 3.15e-01 3.15e-01 3.15e-01

Pu-238 8.65e-01 8.65e-01 8.65e-01 8.65e-01 8.65e-01 8.65e-01 8.65e-01 8.65e-01

Pu-239 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01

Pu-240 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01 9.56e-01

Pu-241 1.85e-02 1.85e-02 1.85e-02 1.85e-02 1.85e-02 1.85e-02 1.85e-02 1.85e-02

Pu-242 9.08e-01 9.08e-01 9.08e-01 9.08e-01 9.08e-01 9.08e-01 9.08e-01 9.08e-01

Pu-244 8.98e-01 8.98e-01 8.98e-01 8.98e-01 8.98e-01 8.98e-01 8.98e-01 8.98e-01

Am-241 9.84e-01 9.84e-01 9.84e-01 9.84e-01 9.84e-01 9.84e-01 9.84e-01 9.84e-01

Am-242m 9.76e-01 9.76e-01 9.76e-01 9.76e-01 9.76e-01 9.76e-01 9.76e-01 9.76e-01

Am-243 9.80e-01 9.80e-01 9.80e-01 9.80e-01 9.80e-01 9.80e-01 9.80e-01 9.80e-01

Cm-242 3.10e-02 3.10e-02 3.10e-02 3.10e-02 3.10e-02 3.10e-02 3.10e-02 3.10e-02

Cm-243 6.79e-01 6.79e-01 6.79e-01 6.79e-01 6.79e-01 6.79e-01 6.79e-01 6.79e-01

Cm-244 5.45e-01 5.45e-01 5.45e-01 5.45e-01 5.45e-01 5.45e-01 5.45e-01 5.45e-01

Cm-245 1.01e+00 1.01e+00 1.01e+00 1.01e+00 1.01e+00 1.01e+00 1.01e+00 1.01e+00

Cm-246 1.00e+00 1.00e+00 1.00e+00 1.00e+00 1.00e+00 1.00e+00 1.00e+00 1.00e+00

Cm-247 9.24e-01 9.24e-01 9.24e-01 9.24e-01 9.24e-01 9.24e-01 9.24e-01 9.24e-01

Cm-248 3.68e+00 3.68e+00 3.68e+00 3.68e+00 3.68e+00 3.68e+00 3.68e+00 3.68e+00

Bk-249 3.24e-03 3.24e-03 3.24e-03 3.24e-03 3.24e-03 3.24e-03 3.24e-03 3.24e-03

Cf-248 9.04e-02 9.04e-02 9.04e-02 9.04e-02 9.04e-02 9.04e-02 9.04e-02 9.04e-02

Cf-249 1.28e+00 1.28e+00 1.28e+00 1.28e+00 1.28e+00 1.28e+00 1.28e+00 1.28e+00

Cf-250 5.76e-01 5.76e-01 5.76e-01 5.76e-01 5.76e-01 5.76e-01 5.76e-01 5.76e-01

Cf-251 1.31e+00 1.31e+00 1.31e+00 1.31e+00 1.31e+00 1.31e+00 1.31e+00 1.31e+00

Cf-252 2.93e-01 2.93e-01 2.93e-01 2.93e-01 2.93e-01 2.93e-01 2.93e-01 2.93e-01

Cf-254 6.55e-01 6.55e-01 6.55e-01 6.55e-01 6.55e-01 6.55e-01 6.55e-01 6.55e-01

Es-254 8.49e-02 8.49e-02 8.49e-02 8.49e-02 8.49e-02 8.49e-02 8.49e-02 8.49e-02
Parameter Values Appendix B

NUREG-1640 B-32

Table B.19 Dose coefficients for ingestion—effective dose (:Sv/Bq)

Nuclide Scrap/

concrete

Food/

water

Metal product Dust/slag/dross

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

H-3 1.8e-05 1.8e-05 1.8e-05 1.8e-05 1.8e-05 1.8e-05 1.8e-05 1.8e-05

C-14 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04

Na-22 3.2e-03 3.2e-03 3.2e-03 3.2e-03 3.2e-03 3.2e-03 3.2e-03 3.2e-03

P-32 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03

S-35 1.4e-04 1.4e-04 1.4e-04 1.4e-04 1.4e-04 1.4e-04 1.4e-04 1.4e-04

Cl-36 9.3e-04 9.3e-04 9.3e-04 9.3e-04 9.3e-04 9.3e-04 9.3e-04 9.3e-04

K-40 6.2e-03 6.2e-03 6.2e-03 6.2e-03 6.2e-03 6.2e-03 6.2e-03 6.2e-03

Ca-41 2.9e-04 2.9e-04 2.9e-04 2.9e-04 2.9e-04 2.9e-04 2.9e-04 2.9e-04

Ca-45 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04

Sc-46 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03

Cr-51 3.7e-05 3.8e-05 3.7e-05 3.7e-05 3.7e-05 3.8e-05 3.8e-05 3.8e-05

Mn-53 3.0e-05 3.0e-05 3.0e-05 3.0e-05 3.0e-05 3.0e-05 3.0e-05 3.0e-05

Mn-54 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04

Fe-55 3.3e-04 3.3e-04 3.3e-04 3.3e-04 3.3e-04 3.3e-04 3.3e-04 3.3e-04

Fe-59 1.8e-03 1.8e-03 1.8e-03 1.8e-03 1.8e-03 1.8e-03 1.8e-03 1.8e-03

Co-56 2.3e-03 2.5e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03

Co-57 1.9e-04 2.1e-04 1.9e-04 1.9e-04 1.9e-04 1.9e-04 1.9e-04 1.9e-04

Co-58 7.0e-04 7.4e-04 7.0e-04 7.0e-04 7.0e-04 7.0e-04 7.0e-04 7.0e-04

Co-60 2.5e-03 3.4e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03

Ni-59 6.3e-05 6.3e-05 6.3e-05 6.3e-05 6.3e-05 6.3e-05 6.3e-05 6.3e-05

Ni-63 1.5e-04 1.5e-04 1.5e-04 1.5e-04 1.5e-04 1.5e-04 1.5e-04 1.5e-04

Zn-65 3.9e-03 3.9e-03 3.9e-03 3.9e-03 3.9e-03 3.9e-03 3.9e-03 3.9e-03

As-73 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04

Se-75 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03

Sr-85 5.6e-04 5.6e-04 5.6e-04 5.6e-04 5.6e-04 5.6e-04 5.6e-04 5.6e-04

Sr-89 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03

Sr-90 3.1e-02 3.1e-02 3.1e-02 3.1e-02 3.1e-02 3.1e-02 3.1e-02 3.1e-02

Y-91 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03 2.4e-03

Zr-93 2.8e-04 2.8e-04 2.8e-04 2.8e-04 2.8e-04 2.8e-04 2.8e-04 2.8e-04

Zr-95 8.9e-04 8.9e-04 8.9e-04 8.9e-04 8.9e-04 8.9e-04 8.9e-04 8.9e-04

Nb-93m 1.2e-04 1.2e-04 1.2e-04 1.2e-04 1.2e-04 1.2e-04 1.2e-04 1.2e-04

Nb-94 1.7e-03 1.7e-03 1.7e-03 1.7e-03 1.7e-03 1.7e-03 1.7e-03 1.7e-03

Nb-95 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04 5.8e-04

Mo-93 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03 2.6e-03

Tc-97 8.3e-05 8.3e-05 8.3e-05 8.3e-05 8.3e-05 8.3e-05 8.3e-05 8.3e-05

Tc-97m 6.6e-04 6.6e-04 6.6e-04 6.6e-04 6.6e-04 6.6e-04 6.6e-04 6.6e-04

Tc-99 7.8e-04 7.8e-04 7.8e-04 7.8e-04 7.8e-04 7.8e-04 7.8e-04 7.8e-04

Ru-103 7.3e-04 7.3e-04 7.3e-04 7.3e-04 7.3e-04 7.3e-04 7.3e-04 7.3e-04

Ru-106 7.0e-03 7.0e-03 7.0e-03 7.0e-03 7.0e-03 7.0e-03 7.0e-03 7.0e-03

Ag-108m 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03 2.3e-03

Ag-110m 2.8e-03 2.8e-03 2.8e-03 2.8e-03 2.8e-03 2.8e-03 2.8e-03 2.8e-03

Cd-109 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03

Sn-113 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04 7.6e-04

Sb-124 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03

Sb-125 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03

Te-123m 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03

Te-127m 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03 2.5e-03

I-125 1.5e-02 1.5e-02 1.5e-02 1.5e-02 1.5e-02 1.5e-02 1.5e-02 1.5e-02

I-129 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01

I-131 2.2e-02 2.2e-02 2.2e-02 2.2e-02 2.2e-02 2.2e-02 2.2e-02 2.2e-02

Cs-134 1.9e-02 1.9e-02 1.9e-02 1.9e-02 1.9e-02 1.9e-02 1.9e-02 1.9e-02

Cs-135 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03

Cs-137 1.3e-02 1.3e-02 1.3e-02 1.3e-02 1.3e-02 1.3e-02 1.3e-02 1.3e-02

Ba-133 1.0e-03 1.0e-03 1.0e-03 1.0e-03 1.0e-03 1.0e-03 1.0e-03 1.0e-03

Ce-139 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04

Ce-141 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04 7.1e-04

Ce-144 5.3e-03 5.3e-03 5.3e-03 5.3e-03 5.3e-03 5.3e-03 5.3e-03 5.3e-03

Pm-147 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04 2.6e-04
Appendix B Parameter Values

Table B.19 Dose coefficients for ingestion—effective dose (:Sv/Bq)

Nuclide Scrap/

concrete

Food/

water

Metal product Dust/slag/dross

Iron/steel Copper Aluminum Iron/steel Copper Aluminum

B-33 NUREG-1640

Sm-151 9.8e-05 9.8e-05 9.8e-05 9.8e-05 9.8e-05 9.8e-05 9.8e-05 9.8e-05

Eu-152 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03

Eu-154 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03 2.0e-03

Eu-155 3.2e-04 3.2e-04 3.2e-04 3.2e-04 3.2e-04 3.2e-04 3.2e-04 3.2e-04

Gd-153 2.7e-04 2.7e-04 2.7e-04 2.7e-04 2.7e-04 2.7e-04 2.7e-04 2.7e-04

Tb-160 1.6e-03 1.6e-03 1.6e-03 1.6e-03 1.6e-03 1.6e-03 1.6e-03 1.6e-03

Tm-170 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03

Tm-171 1.1e-04 1.1e-04 1.1e-04 1.1e-04 1.1e-04 1.1e-04 1.1e-04 1.1e-04

Ta-182 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03 1.5e-03

W-181 7.6e-05 7.6e-05 7.6e-05 7.6e-05 7.6e-05 7.6e-05 7.6e-05 7.6e-05

W-185 4.4e-04 4.4e-04 4.4e-04 4.4e-04 4.4e-04 4.4e-04 4.4e-04 4.4e-04

Os-185 5.1e-04 5.1e-04 5.1e-04 5.1e-04 5.1e-04 5.1e-04 5.1e-04 5.1e-04

Ir-192 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03 1.4e-03

Tl-204 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03

Pb-210 9.2e-01 9.2e-01 9.2e-01 9.2e-01 9.2e-01 9.2e-01 9.2e-01 9.2e-01

Bi-207 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03 1.3e-03

Po-210 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01

Ra-226 2.8e-01 2.8e-01 2.8e-01 2.8e-01 2.8e-01 2.8e-01 2.8e-01 2.8e-01

Ra-228 6.7e-01 6.7e-01 6.7e-01 6.7e-01 6.7e-01 6.7e-01 6.7e-01 6.7e-01

Ac-227 1.2e+00 1.2e+00 1.2e+00 1.2e+00 1.2e+00 1.2e+00 1.2e+00 1.2e+00

Th-228 1.4e-01 1.4e-01 1.4e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.4e-01

Th-229 6.0e-01 6.0e-01 6.0e-01 3.2e-01 3.2e-01 3.2e-01 3.2e-01 6.0e-01

Th-230 2.1e-01 2.1e-01 2.1e-01 8.7e-02 8.7e-02 8.7e-02 8.7e-02 2.1e-01

Th-232 2.2e-01 2.2e-01 2.2e-01 9.2e-02 9.2e-02 9.2e-02 9.2e-02 2.2e-01

Pa-231 7.1e-01 7.1e-01 7.1e-01 7.1e-01 7.1e-01 7.1e-01 7.1e-01 7.1e-01

U-232 3.3e-01 3.3e-01 3.3e-01 3.3e-01 3.3e-01 3.7e-02 3.7e-02 3.3e-01

U-233 5.0e-02 5.0e-02 5.0e-02 5.0e-02 5.0e-02 8.5e-03 8.5e-03 5.0e-02

U-234 4.9e-02 4.9e-02 4.9e-02 4.9e-02 4.9e-02 8.3e-03 8.3e-03 4.9e-02

U-235 4.6e-02 4.6e-02 4.6e-02 4.6e-02 4.6e-02 8.6e-03 8.6e-03 4.6e-02

U-236 4.6e-02 4.6e-02 4.6e-02 4.6e-02 4.6e-02 7.9e-03 7.9e-03 4.6e-02

U-238 4.7e-02 4.7e-02 4.7e-02 4.7e-02 4.7e-02 1.1e-02 1.1e-02 4.7e-02

Np-237 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01 1.1e-01

Pu-236 8.6e-02 8.6e-02 8.6e-02 8.6e-02 8.6e-02 8.6e-02 8.6e-02 8.6e-02

Pu-238 2.3e-01 2.3e-01 2.3e-01 2.3e-01 2.3e-01 2.3e-01 2.3e-01 2.3e-01

Pu-239 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01

Pu-240 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01 2.5e-01

Pu-241 4.7e-03 4.7e-03 4.7e-03 4.7e-03 4.7e-03 4.7e-03 4.7e-03 4.7e-03

Pu-242 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01

Pu-244 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01 2.4e-01

Am-241 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01

Am-242m 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01

Am-243 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01

Cm-242 1.2e-02 1.2e-02 1.2e-02 1.2e-02 1.2e-02 1.2e-02 1.2e-02 1.2e-02

Cm-243 1.5e-01 1.5e-01 1.5e-01 1.5e-01 1.5e-01 1.5e-01 1.5e-01 1.5e-01

Cm-244 1.2e-01 1.2e-01 1.2e-01 1.2e-01 1.2e-01 1.2e-01 1.2e-01 1.2e-01

Cm-245 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01

Cm-246 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01 2.1e-01

Cm-247 1.9e-01 1.9e-01 1.9e-01 1.9e-01 1.9e-01 1.9e-01 1.9e-01 1.9e-01

Cm-248 7.7e-01 7.7e-01 7.7e-01 7.7e-01 7.7e-01 7.7e-01 7.7e-01 7.7e-01

Bk-249 9.7e-04 9.7e-04 9.7e-04 9.7e-04 9.7e-04 9.7e-04 9.7e-04 9.7e-04

Cf-248 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02

Cf-249 3.5e-01 3.5e-01 3.5e-01 3.5e-01 3.5e-01 3.5e-01 3.5e-01 3.5e-01

Cf-250 1.6e-01 1.6e-01 1.6e-01 1.6e-01 1.6e-01 1.6e-01 1.6e-01 1.6e-01

Cf-251 3.6e-01 3.6e-01 3.6e-01 3.6e-01 3.6e-01 3.6e-01 3.6e-01 3.6e-01

Cf-252 9.0e-02 9.0e-02 9.0e-02 9.0e-02 9.0e-02 9.0e-02 9.0e-02 9.0e-02

Cf-254 4.0e-01 4.0e-01 4.0e-01 4.0e-01 4.0e-01 4.0e-01 4.0e-01 4.0e-01

Es-254 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02 2.8e-02
Parameter Values Appendix B

NUREG-1640 B-34

Table B.20 Dose coefficients for external exposure to contaminated soil

Nuclide

Surface

(:Sv/h per Bq/m2)

Infinite depth

(:Sv/h per Bq/g) Nuclide

Surface

(:Sv/h per Bq/m2)

Infinite depth

(:Sv/h per Bq/g)

EDE Eff. dose EDE Eff. dose EDE Eff. dose EDE Eff. dose

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Sm-151 1.81e-11 1.28e-11 3.04e-08 2.09e-08

C-14 5.80e-11 4.61e-11 4.15e-07 3.40e-07 Eu-152 3.96e-06 3.85e-06 2.16e-01 2.04e-01

Na-22 7.56e-06 7.38e-06 4.22e-01 3.97e-01 Eu-154 4.28e-06 4.21e-06 2.37e-01 2.24e-01

P-32 1.05e-08 3.07e-07 3.63e-04 6.28e-04 Eu-155 2.12e-07 1.93e-07 5.62e-03 4.99e-03

S-35 6.05e-11 4.79e-11 4.59e-07 3.78e-07 Gd-153 3.82e-07 3.33e-07 7.55e-03 6.57e-03

Cl-36 2.42e-09 4.03e-08 7.37e-05 7.66e-05 Tb-160 3.89e-06 3.78e-06 2.13e-01 2.02e-01

K-40 5.26e-07 7.31e-07 3.21e-02 3.07e-02 Tm-170 2.13e-08 9.50e-08 4.61e-04 4.35e-04

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Tm-171 2.31e-09 2.00e-09 3.44e-05 2.90e-05

Ca-45 1.66e-10 1.36e-10 1.93e-06 1.65e-06 Ta-182 4.43e-06 4.28e-06 2.45e-01 2.32e-01

Sc-46 6.95e-06 6.77e-06 3.91e-01 3.70e-01 W-181 1.41e-07 1.24e-07 2.36e-03 2.01e-03

Cr-51 1.11e-07 1.07e-07 5.38e-03 4.99e-03 W-185 6.62e-10 6.16e-10 1.34e-05 1.18e-05

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Os-185 2.53e-06 2.45e-06 1.28e-01 1.20e-01

Mn-54 2.92e-06 2.84e-06 1.59e-01 1.50e-01 Ir-192 2.89e-06 2.79e-06 1.42e-01 1.32e-01

Fe-55 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Tl-204 5.33e-09 3.89e-08 1.25e-04 1.20e-04

Fe-59 4.03e-06 3.96e-06 2.36e-01 2.23e-01 Pb-210 1.27e-08 1.34e-07 1.88e-04 2.31e-04

Co-56 1.18e-05 1.16e-05 7.26e-01 6.91e-01 Bi-207 5.33e-06 5.22e-06 2.89e-01 2.72e-01

Co-57 4.14e-07 3.92e-07 1.54e-02 1.41e-02 Po-210 2.98e-11 2.91e-11 1.61e-06 1.52e-06

Co-58 3.42e-06 3.32e-06 1.84e-01 1.73e-01 Ra-226 5.98e-06 6.07e-06 3.45e-01 3.27e-01

Co-60 8.46e-06 8.28e-06 5.00e-01 4.75e-01 Ra-228 3.34e-06 3.38e-06 1.84e-01 1.75e-01

Ni-59 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Ac-227 1.39e-06 1.68e-06 6.20e-02 5.76e-02

Ni-63 0.00e+00 0.00e+00 0.00e+00 0.00e+00 Th-228 5.06e-06 5.18e-06 3.14e-01 2.98e-01

Zn-65 1.99e-06 1.94e-06 1.14e-01 1.08e-01 Th-229 1.14e-06 1.24e-06 4.90e-02 4.54e-02

As-73 2.14e-08 1.87e-08 2.90e-04 2.42e-04 Th-230 2.70e-09 2.29e-09 3.73e-05 3.30e-05

Se-75 1.36e-06 1.30e-06 6.11e-02 5.64e-02 Th-232 1.98e-09 1.64e-09 1.61e-05 1.41e-05

Sr-85 1.80e-06 1.74e-06 9.16e-02 8.52e-02 Pa-231 1.47e-07 1.36e-07 5.88e-03 5.44e-03

Sr-89 8.17e-09 2.47e-07 2.80e-04 4.66e-04 U-232 3.64e-09 2.91e-09 2.78e-05 2.45e-05

Sr-90 2.26e-07 2.19e-07 9.87e-03 9.06e-03 U-233 2.58e-09 2.16e-09 4.31e-05 3.90e-05

Y-91 2.07e-08 2.69e-07 1.00e-03 1.17e-03 U-234 2.69e-09 2.11e-09 1.24e-05 1.06e-05

Zr-93 0.00e+00 0.00e+00 0.00e+00 0.00e+00 U-235 5.99e-07 5.60e-07 2.34e-02 2.13e-02

Zr-95 2.61e-06 2.53e-06 1.40e-01 1.31e-01 U-236 2.34e-09 1.81e-09 6.62e-06 5.49e-06

Nb-93m 3.38e-09 2.46e-09 3.21e-06 2.27e-06 U-238 9.76e-08 4.28e-07 4.08e-03 4.24e-03

Nb-94 5.51e-06 5.36e-06 2.98e-01 2.81e-01 Np-237 8.05e-07 7.60e-07 3.39e-02 3.12e-02

Nb-95 2.69e-06 2.62e-06 1.45e-01 1.37e-01 Pu-236 3.53e-09 2.65e-09 7.03e-06 5.59e-06

Mo-93 1.92e-08 1.40e-08 1.82e-05 1.28e-05 Pu-238 3.02e-09 2.25e-09 4.67e-06 3.60e-06

Tc-97 2.33e-08 1.67e-08 2.49e-05 1.74e-05 Pu-239 1.32e-09 1.02e-09 9.10e-06 8.12e-06

Tc-97m 2.22e-08 1.61e-08 5.88e-05 4.73e-05 Pu-240 2.89e-09 2.16e-09 4.52e-06 3.47e-06

Tc-99 2.81e-10 2.34e-10 3.87e-06 3.35e-06 Pu-241 6.95e-12 6.19e-12 1.82e-07 1.64e-07

Ru-103 1.67e-06 1.62e-06 8.47e-02 7.89e-02 Pu-242 2.40e-09 1.79e-09 3.95e-06 3.06e-06

Ru-106 7.63e-07 1.24e-06 3.98e-02 3.84e-02 Pu-244 1.20e-06 1.41e-06 6.25e-02 5.90e-02

Ag-108m 5.77e-06 5.57e-06 2.98e-01 2.79e-01 Am-241 9.90e-08 8.39e-08 1.35e-03 1.15e-03

Ag-110m 9.54e-06 9.30e-06 5.29e-01 4.99e-01 Am-242m 7.87e-08 7.67e-08 2.07e-03 1.89e-03

Cd-109 1.16e-07 8.69e-08 8.18e-04 6.94e-04 Am-243 7.79e-07 7.27e-07 2.76e-02 2.51e-02

Sn-113 9.91e-07 9.34e-07 4.52e-02 4.19e-02 Cm-242 3.44e-09 2.53e-09 5.27e-06 3.97e-06

Sb-124 6.16e-06 6.12e-06 3.61e-01 3.42e-01 Cm-243 4.50e-07 4.25e-07 1.80e-02 1.65e-02

Sb-125 1.56e-06 1.49e-06 7.56e-02 7.04e-02 Cm-244 3.16e-09 2.32e-09 3.88e-06 2.76e-06

Te-123m 5.15e-07 4.79e-07 1.94e-02 1.77e-02 Cm-245 3.13e-07 2.90e-07 1.05e-02 9.45e-03

Te-127m 5.89e-08 6.72e-08 1.03e-03 9.33e-04 Cm-246 2.83e-09 2.07e-09 3.58e-06 2.56e-06

I-125 1.54e-07 1.14e-07 5.10e-04 3.68e-04 Cm-247 1.20e-06 1.16e-06 5.73e-02 5.32e-02

I-129 9.29e-08 7.06e-08 3.99e-04 2.96e-04 Cm-248 2.16e-09 1.58e-09 2.71e-06 1.93e-06

I-131 1.35e-06 1.31e-06 6.68e-02 6.22e-02 Bk-249 2.47e-11 1.93e-11 1.43e-07 1.16e-07

Cs-134 5.47e-06 5.33e-06 2.92e-01 2.74e-01 Cf-248 2.79e-09 2.01e-09 3.84e-06 2.71e-06

Cs-135 1.20e-10 9.68e-11 1.18e-06 9.91e-07 Cf-249 1.18e-06 1.13e-06 5.71e-02 5.30e-02

Cs-137 1.99e-06 1.98e-06 1.05e-01 9.84e-02 Cf-250 2.65e-09 1.92e-09 3.65e-06 2.56e-06

Ba-133 1.43e-06 1.34e-06 6.11e-02 5.61e-02 Cf-251 4.39e-07 4.07e-07 1.62e-02 1.48e-02

Ce-139 5.62e-07 5.15e-07 1.96e-02 1.79e-02 Cf-252 2.60e-09 1.89e-09 5.42e-06 4.20e-06

Ce-141 2.66e-07 2.49e-07 9.79e-03 8.93e-03 Cf-254 8.64e-12 6.23e-12 1.19e-08 8.35e-09

Ce-144 2.08e-07 6.45e-07 9.89e-03 1.01e-02 Es-254 3.11e-06 3.06e-06 1.71e-01 1.62e-01

Pm-147 1.23e-10 1.01e-10 1.54e-06 1.32e-06
Appendix B Parameter Values

B-35 NUREG-1640

Table B.21 Soil-water distribution coefficients and food transfer factors

Element Kd (cm3

/g) Plant (Biv) Meat (d/kg) Milk (d/L)

:g Fg Min Max :g Fg :g Fg :g Fg

H 6.02e-02 1.65 4.00e-02 2.82e-01 4.81e+00 3.00 1.20e-02 2.72 1.01e-02 2.46

C 1.10e+01 25.03 5.00e+00 3.90e+01 6.98e-01 2.46 3.11e-02 2.72 1.23e-02 2.46

Na 1.54e+02 25.03 4.40e+01 5.40e+02 4.98e-02 2.72 7.97e-02 1.22 4.00e-02 1.65

P 8.90e+01 — — — 1.00e+00 3.00 4.98e-02 1.22 2.00e-02 2.01

S 3.85e+01 25.03 1.84e-03 8.07e+05 6.01e-01 3.00 2.00e-01 2.72 2.00e-02 2.01

Cl 5.37e+00 25.03 1.50e+00 1.90e+01 2.01e+01 3.00 4.00e-02 2.01 2.00e-02 1.65

K 5.47e+00 1.63 1.20e+00 2.49e+01 3.01e-01 3.00 2.00e-02 1.22 7.01e-03 1.65

Ca 4.06e+00 2.18 1.20e+00 4.52e+01 5.02e-01 3.00 2.01e-03 1.22 3.00e-03 1.65

Sc 9.34e+02 25.03 4.46e-02 1.96e+07 2.01e-03 3.00 2.01e-03 2.72 5.98e-03 2.46

Cr 1.03e+02 15.80 1.20e+00 2.52e+03 9.95e-03 2.72 2.99e-02 1.49 2.01e-03 2.01

Mn 1.58e+02 9.87 2.00e-01 7.70e+04 3.01e-01 2.46 9.98e-04 2.01 3.01e-04 2.01

Fe 2.09e+02 14.44 1.40e+00 6.00e+03 9.98e-04 2.46 2.99e-02 1.49 3.01e-04 2.01

Co 2.35e+02 12.55 9.46e-02 1.40e+04 7.97e-02 2.46 2.99e-02 2.72 2.01e-03 2.01

Ni 4.24e+02 4.31 6.00e+01 4.70e+03 4.98e-02 2.46 4.99e-03 2.46 2.00e-02 2.01

Zn 1.07e+03 84.77 1.00e-01 1.00e+05 3.99e-01 2.46 1.00e-01 1.35 9.95e-03 2.46

As 1.10e+02 — — — 7.97e-02 3.00 2.00e-02 2.72 1.00e-04 2.46

Se 1.13e+02 1.77 1.95e+01 1.70e+02 1.00e-01 3.00 1.00e-01 2.46 9.95e-03 2.46

Sr 3.15e+01 8.33 4.50e-02 2.21e+04 3.01e-01 2.72 9.95e-03 1.49 2.01e-03 1.65

Y 7.94e+02 25.03 3.79e-02 1.66e+07 2.01e-03 3.00 2.01e-03 2.46 6.01e-05 2.46

Zr 1.38e+03 25.03 1.90e+01 2.89e+07 9.98e-04 3.00 9.96e-07 2.46 5.98e-07 2.01

Nb 3.80e+02 25.03 1.10e+02 1.30e+03 9.95e-03 3.00 9.96e-07 2.46 2.00e-06 2.01

Mo 2.63e+01 5.64 3.70e-01 4.00e+02 1.00e-01 3.00 9.96e-07 2.46 2.01e-03 2.01

Tc 5.12e-01 23.57 2.90e-03 3.40e+02 5.00e+00 2.46 1.00e-04 2.01 9.98e-04 2.01

Ru 1.59e+03 22.87 5.00e+00 8.70e+04 2.99e-02 2.46 2.01e-03 2.46 2.00e-05 1.82

Ag 2.17e+02 8.17 2.70e+00 3.30e+04 4.01e-03 2.46 2.01e-03 2.01 5.98e-03 2.01

Cd 3.38e+01 19.89 1.30e+00 1.70e+04 5.02e-01 3.00 9.98e-04 2.46 2.01e-03 2.46

Sn 8.29e+02 25.03 3.95e-02 1.74e+07 3.01e-01 3.00 9.95e-03 2.72 9.98e-04 2.46

Sb 1.74e+02 25.03 4.50e+01 1.30e+03 9.95e-03 2.72 9.98e-04 2.46 6.01e-05 2.46

Te 3.81e+01 25.03 1.82e-03 7.99e+05 1.00e-01 2.72 7.01e-03 2.46 5.00e-04 1.82

I 4.57e+00 8.94 4.00e-02 3.70e+02 2.00e-02 2.46 4.00e-02 1.49 9.95e-03 1.65

Cs 4.46e+02 10.28 3.33e-01 1.45e+05 4.00e-02 2.72 4.98e-02 1.49 9.95e-03 1.65

Ba 4.47e+01 3388 5.51e-10 3.62e+12 9.95e-03 3.00 1.99e-04 2.46 5.00e-04 2.01

Ce 2.00e+03 8.00 4.00e+01 5.60e+04 2.01e-03 2.72 2.00e-05 2.46 3.01e-05 2.01

Pm 8.29e+02 25.03 2.40e+02 2.90e+03 2.01e-03 3.00 2.01e-03 2.72 6.01e-05 2.46

Sm 8.29e+02 25.03 2.40e+02 2.90e+03 2.01e-03 3.00 2.01e-03 2.72 6.01e-05 2.46

Eu 8.29e+02 25.03 2.40e+02 2.90e+03 2.01e-03 3.00 2.01e-03 2.72 6.01e-05 2.46

Gd 8.29e+02 25.03 2.40e+02 2.90e+03 2.01e-03 3.00 2.01e-03 2.72 6.01e-05 2.46

Tb 1.59e+02 25.03 7.56e-03 3.32e+06 2.01e-03 3.00 2.01e-03 2.72 6.01e-05 2.46

Tm 1.59e+02 25.03 7.56e-03 3.32e+06 3.60e-03 — 3.26e-03 — 8.90e-05 —

Ta 2.57e+02 25.03 1.23e-02 5.39e+06 2.01e-03 3.00 4.98e-06 2.72 4.98e-06 2.46

W 1.59e+02 25.03 7.56e-03 3.32e+06 8.03e-01 2.72 4.00e-02 2.46 3.01e-04 2.46

Os 1.59e+02 25.03 7.56e-03 3.32e+06 5.36e-02 — 3.26e-03 — 2.97e-06 —

Ir 2.04e+02 25.03 9.75e-03 4.28e+06 2.99e-02 3.00 2.01e-03 2.72 2.00e-06 2.46

Tl 7.08e+01 25.03 2.00e+01 2.50e+02 2.00e-01 3.00 2.00e-02 2.72 3.00e-03 2.46

Pb 2.39e+03 15.80 4.50e+00 5.90e+04 4.01e-03 2.46 8.01e-04 2.01 3.01e-04 2.46

Bi 1.05e+02 25.03 3.00e+01 3.70e+02 1.00e-01 3.00 2.01e-03 2.72 9.98e-04 2.46

Po 1.81e+02 5.37 9.00e+00 3.26e+04 1.01e-03 2.46 4.99e-03 2.01 4.02e-04 2.01

Ra 3.53e+03 5.47 5.70e+01 5.30e+05 4.00e-02 2.46 9.98e-04 2.01 9.98e-04 1.65

Ac 8.29e+02 25.03 2.40e+02 2.90e+03 9.98e-04 3.00 2.00e-05 2.72 2.00e-06 2.46

Th 5.88e+03 37.34 2.07e+02 1.30e+07 9.98e-04 2.46 1.00e-04 2.72 4.98e-06 2.46

Pa 3.80e+02 25.03 1.10e+02 1.30e+03 9.95e-03 3.00 4.98e-06 2.72 4.98e-06 2.46

U 1.26e+02 22.87 3.00e-02 4.00e+05 2.01e-03 2.46 8.01e-04 2.01 4.02e-04 1.82

Np 1.71e+01 9.49 1.60e-01 2.60e+03 2.00e-02 2.46 9.98e-04 2.01 1.00e-05 2.01

Pu 9.53e+02 6.62 1.10e+01 3.00e+05 9.98e-04 2.46 1.00e-04 1.22 9.96e-07 1.65

Am 1.45e+03 23.34 1.00e+00 4.50e+05 9.98e-04 2.46 5.02e-05 1.22 2.00e-06 2.01

Cm 6.77e+03 6.17 9.30e+01 5.20e+04 9.98e-04 2.46 2.00e-05 2.72 2.00e-06 2.46

Bk 1.43e+03 — — — 1.48e-03 — 5.12e-05 — 2.54e-06 —

Cf 1.38e+03 25.03 1.90e+01 2.89e+07 9.98e-04 3.00 6.01e-05 2.72 2.00e-06 2.46

Es 1.38e+03 25.03 1.90e+01 2.89e+07 1.48e-03 — 5.12e-05 — 2.54e-06 —
Parameter Values Appendix B

NUREG-1640 B-36

Notes to Tables B.16 and B.18: Dose conversion factors from Eckerman and Ryman (1988)

Notes to Tables B.17 and B.19: Dose coefficients from ICRP (1994)

Notes to Table B.21:

:g = geometric mean of lognormal distribution, based on values presented by Yu et al. (2000)

Fg = geometric standard deviation of lognormal distribution (ibid.); if entry is blank, value in previous column is a fixed

value, as listed by Kennedy and Strenge (1992)
Appendix B Parameter Values

B-37 NUREG-1640

References

Eckerman, K. F., A. B. Wolbarst, and A. C. B. Richardson. 1988. “Limiting Values of

Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation,

Submersion, and Ingestion,” Federal Guidance Report No. 11, EPA-520/1-88-020. Washington,

DC: U.S. Environmental Protection Agency, Office of Radiation Programs.

Eckerman and Ryman. 1993. “External Exposure to Radionuclides in Air, Water, and Soil.” 

Federal Guidance Report No. 12. EPA 402-R-93-081. Washington, DC: U.S. Environmental

Protection Agency, Office of Radiation and Indoor Air.

Environmental Protection Agency (U.S.) (EPA). 1997. “Exposure Factors Handbook,”

EPA/600/P-95/002Fa. Washington, DC: Author.

International Commission on Radiation Protection (ICRP). 1987. “Data for Use in Protection

Against External Radiation,” ICRP Publication 51. Annals of the ICRP, 17 (2/3). Oxford:

Pergamon Press.

International Commission on Radiological Protection (ICRP). 1994. “Dose Coefficients for

Intakes of Radionuclides by Workers,” ICRP Publication 68. Annals of the ICRP, 24 (4). 

Tarrytown, NY: Elsevier Science, Inc.

International Commission on Radiological Protection (ICRP). 1996. “Conversion Coefficients

for use in Radiological Protection against External Radiation,” ICRP Publication 74. Annals of

the ICRP, 26 (3/4). Tarrytown, NY: Elsevier Science, Inc.

International Atomic Energy Agency (IAEA). 1989. “Evaluating the Reliability of Predictions

Made Using Environmental Transfer Models,” Safety Series 100. Vienna: Author.

Kennedy, W. E., and D. L. Strenge. 1992. “Residual Radioactive Contamination From

Decommissioning: Technical Basis for Translating Contamination Levels to Annual Total

Effective Dose Equivalent,” NUREG/CR-5512. Vol. 1. Washington, DC: U.S. Nuclear

Regulatory Commission.

Yu, C., et al. 2000. “Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0

Computer Codes,” NUREG/CR-6697, ANL/EAD/TM-98. Washington, DC: U.S. Nuclear

Regulatory Commission.
APPENDIX C

EXTERNAL EXPOSURE DOSE COEFFICIENTS

Appendix C External Exposure Dose Coefficients

C-iii NUREG-1640

CONTENTS

Page

Appendix C External Exposure Dose Coefficients . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1

C.1 Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1

C.1.1 Radiation Transport Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1

C.1.2 Calculational Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-2

C.1.2.1 Dose Coefficients for Individual Nuclides . . . . . . . . . . . . . . . . . . . . . . . . C-2

C.1.2.2 External Bremsstrahlung . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-3

C.1.2.3 Variance Reduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-4

C.1.2.4 Uncertainty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-4

C.2 Steel Scenarios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-5

C.2.1 Scrap Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-5

C.2.1.1 Exposure Geometry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-5

C.2.1.2 Results of Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-7

C.2.2 Slag Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-9

C.2.3 Dust Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-10

C.2.4 Baghouse . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-11

C.2.5 Large Metal Object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-12

C.2.6 Small Metal Object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-16

C.2.7 Small Object Next to Body . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-17

C.2.7.1 Analytical Approach . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-17

C.2.7.2 Results of Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-19

C.2.8 Truck Scenarios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-22

C.2.8.1 Scrap Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-23

C.2.8.2 Slag Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-26

C.2.8.3 Dry Bulk Trailer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-27

C.2.8.3.1 Worker Atop Dust Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-28

C.2.8.3.2 Dust in Dry Bulk Trailer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-30

C.2.8.4 Dust in Dump Trailer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-30

C.2.8.5 Truck With I-Beams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-31

C.2.9 Cement Basement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-34

C.2.10 House with Steel Studs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-35

C.2.11 Auto—Cast Iron Engine Block . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-38

C.2.12 Diesel Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-39

C.2.13 Hull Plate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-41

C.2.14 Steel Ship . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-42

C.2.14.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-43

C.2.14.2 Compartment Densities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-46

C.2.14.3 Specific Compartment Descriptions . . . . . . . . . . . . . . . . . . . . . . . . . . . C-47

C.2.14.3.1 Forward Compartment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-47

C.2.14.3.2 Fuel Oil Storage Compartment . . . . . . . . . . . . . . . . . . . . . . . . . . . C-47

C.2.14.3.3 Large Cargo . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-47
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-iv

Contents (continued)

Page

C.2.14.3.4 Ammunition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-47

C.2.14.3.5 Dry-Refrigerated Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-48

C.2.14.3.6 Engine Rooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-48

C.2.14.3.7 Auxiliary Rooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-48

C.2.14.3.8 Aft Compartment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-49

C.2.14.3.9 Superstructure Compartments . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-49

C.2.14.4 Exposure Geometry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-49

C.2.14.5 Composition of Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-53

C.2.14.6 Results of Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-53

C.3 Copper . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-54

C.3.1 Copper Scrap Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-56

C.3.2 Copper Slag Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-58

C.3.3 Truck Loaded with Metal Product . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-59

C.4 Aluminum . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-61

C.4.1 Aluminum Scrap Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-61

C.4.2 Dross Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-63

C.4.3 Large Aluminum Object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-64

C.4.4 Small Aluminum Object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-64

C.4.5 Aluminum Scrap Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-65

C.4.6 Dross Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-66

C.4.7 Aluminum Dust Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-68

C.4.8 Truck Loaded with Aluminum Product . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-69

C.4.9 Auto—Aluminum Engine Block . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-70

C.4.10 Aluminum Cooking Pot . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-71

C.5 Concrete . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-72

C.5.1 Concrete Pile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-73

C.5.2 Concrete Truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-73

C.6 External Exposure Dose Coefficients for Individual Radionuclides . . . . . . . . . . . . . C-75

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-102
Appendix C External Exposure Dose Coefficients

C-v NUREG-1640

Tables

Page

C.1 Composition of materials in steel analysis (wt. fraction) . . . . . . . . . . . . . . . . . . . . . . . . . . C-6

C.2 Concrete composition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-7

C.3 Dose rates from pile of steel scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-9

C.4 Dose rates from pile of steel slag . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-11

C.5 Effective dose equivalent rates from pile of EAF dust (Sv/s per Bq/g) . . . . . . . . . . . . . . C-13

C.6 Effective dose rates from pile of EAF dust (Sv/s per Bq/g) . . . . . . . . . . . . . . . . . . . . . . C-13

C.7 Baghouse geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-14

C.8 Dose rates in baghouse . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-14

C.9 Dose rates from large metal object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-15

C.10 Large metal object– bremsstrahlung (Sv/s per Bq/g) . . . . . . . . . . . . . . . . . . . . . . . . . C-15

C.11 Dose rates from small metal object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-16

C.12 Small metal object– bremsstrahlung . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-16

C.13 Tissue weighting factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-18

C.14 Organ masses of anthropomorphic phantoms (g) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-20

C.15 Dose rates from small object next to body . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-22

C.16 Small object next to body—uncertainty parameter . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-22

C.17 Small object next to body– bremsstrahlung . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-22

C.18 Scrap truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-23

C.19 Dose rates to scrap truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-25

C.20 Slag truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-26

C.21 Dose rates to slag truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-27

C.22 Dry bulk trailer exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-29

C.23 Dose rates to worker atop dust truck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-29

C.24 Dose rates to driver hauling EAF dust in dry bulk trailer . . . . . . . . . . . . . . . . . . . . . . . C-30

C.25 Dump trailer hauling EAF dust: exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . C-31

C.26 Hauling EAF dust in dump trailer: dose rates in driver’s seat . . . . . . . . . . . . . . . . . . . C-32

C.27 Hauling EAF dust in dump trailer: dose rates in sleeper berth . . . . . . . . . . . . . . . . . . . C-32

C.28 Dimensions of individual I-beam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-33

C.29 I-beam geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-33

C.30 Steel product truck driver exposure geometry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-33

C.31 Dose rates to truck driver hauling steel products . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-34

C.32 Basement dweller exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-35

C.33 Dose rates to cement basement dweller . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-36

C.34 Steel-studded house exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-37

C.35 Dose rates in steel-studded house . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-38

C.36 Engine block exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-39

C.37 Dose rates to driver of automobile with cast iron engine block . . . . . . . . . . . . . . . . . . . C-40

C.38 Diesel truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-41

C.39 Dose rates in driver’s seat of truck with cast iron diesel engine block . . . . . . . . . . . . . C-42

C.40 Dose rates in sleeper berth of truck with cast iron diesel engine block . . . . . . . . . . . . . C-43

C.41 Dose rates from steel hull plate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-44
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-vi

Tables (continued)

Page

C.42 Dose rates from  bremsstrahlung from steel hull plate . . . . . . . . . . . . . . . . . . . . . . . . C-44

C.43 Steel ship exposure geometry—structures (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-51

C.44 Steel ship exposure geometry—compartments (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . C-52

C.45 Taper of bow: coordinates of cylindrical shells . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-52

C.46 Composition of materials and compartments of ship . . . . . . . . . . . . . . . . . . . . . . . . . . . C-53

C.47 Dose rates in steel ship . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-54

C.48 Scoping calculation of intensity of photons emitted from Cu vs. Fe . . . . . . . . . . . . . . . C-55

C.49 Corresponding exposure geometries in copper and steel analyses . . . . . . . . . . . . . . . . C-56

C.50 Composition of materials unique to copper analysis (wt. fraction) . . . . . . . . . . . . . . . . C-56

C.51 Dose rates from pile of copper scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-57

C.52 Worker handling copper slag: exposure geometry . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-58

C.53 Dose rates to worker handling copper slag . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-59

C.54 Driver of tractor-trailer hauling copper tubes: exposure geometry . . . . . . . . . . . . . . . . C-60

C.55 Hauling copper tubes: dose rates in driver’s seat . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-60

C.56 Hauling copper tubes: dose rates in sleeper berth . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-61

C.57 Composition of materials unique to aluminum analysis (wt. fraction) . . . . . . . . . . . . . C-62

C.58 Dose rates from pile of aluminum scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-63

C.59 Dose rates from pile of aluminum dross . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-64

C.60 Dose rates from large aluminum object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-65

C.61 Dose rates from small aluminum object . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-66

C.62 Aluminum scrap truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . C-66

C.63 Dose rates to aluminum scrap truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-67

C.64 Dross truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-67

C.65 Dose rates to dross truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-68

C.66 Aluminum dust truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . C-68

C.67 Dose rates to aluminum dust truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-69

C.68 Aluminum products truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . C-70

C.69 Dose rates to aluminum product truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-70

C.70 Dose rates to driver of automobile with aluminum engine block . . . . . . . . . . . . . . . . . C-71

C.71 Cooking pot exposure geometry (cylindrical coordinates) (cm) . . . . . . . . . . . . . . . . . . C-72

C.72 Dose rates from aluminum cookware . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-72

C.73 Dose rates from pile of concrete rubble . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-73

C.74 Concrete truck driver exposure geometry (cm) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-74

C.75 Dose rates to concrete rubble truck driver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-74

C.76 Effective dose equivalent coefficients for steel scenarios–part 1 . . . . . . . . . . . . . . . . . C-76

C.77 Effective dose equivalent coefficients for steel scenarios–part 2 . . . . . . . . . . . . . . . . . C-78

C.78 Effective dose equivalent coefficients for steel scenarios–part 3 . . . . . . . . . . . . . . . . . C-80

C.79 Effective dose coefficients for external exposure in steel scenarios—part 1 . . . . . . . . C-82

C.80 Effective dose coefficients for external exposure in steel scenarios—part 2 . . . . . . . . C-84

C.81 Effective dose coefficients for external exposure in steel scenarios—part 3 . . . . . . . . C-86

C.82 Effective dose equivalent coefficients for copper scenarios—part 1 . . . . . . . . . . . . . . . C-88

C.83 Effective dose equivalent coefficients for copper scenarios—part 2 . . . . . . . . . . . . . . . C-90

C.84 Effective dose coefficients for external exposure in copper scenarios—part 1 . . . . . . . C-92
Appendix C External Exposure Dose Coefficients

C-vii NUREG-1640

Tables (continued)

Page

C.85 Effective dose coefficients for external exposure in copper scenarios—part 2 . . . . . . . C-94

C.86 Effective dose equivalent coefficients for aluminum scenarios . . . . . . . . . . . . . . . . . . . C-96

C.87 Effective dose coefficients for external exposure in aluminum scenarios . . . . . . . . . . . C-98

C.88 Dose coefficients for external exposure in concrete scenarios . . . . . . . . . . . . . . . . . . C-100
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-viii

Figures

Page

C.1 Layout of baghouse modules . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-12

C.2 Cross-sectional view of male anthropomorphic phantom . . . . . . . . . . . . . . . . . . . . . . . . C-19

C.3 Location of sources on the anthropomorphic phantoms . . . . . . . . . . . . . . . . . . . . . . . . . C-21

C.4 Location of phantom in concrete-walled room . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-21

C.5 Schematic of Heil Trailer International Super Jet Model 1040 aluminum dry bulk

trailer + tractor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-24

C.6 Cross-section of Heil Dry Bulk Trailer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-28

C.7 Arrangement of I-beams (not to scale) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-33

C.8Cross-section of steel stud(thickness not to scale) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-37

C.9 Floor plan of steel-studded house . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-37

C.10 Engine block exposure geometry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-39

C.11 AOE-6 class fast combat support ship (starboard view) . . . . . . . . . . . . . . . . . . . . . . . . C-43

C.12 Schematic diagrams of ship model . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-45

C.13 Typical arrangement of copper tubes—dimensions in cm . . . . . . . . . . . . . . . . . . . . . . . C-59

C.14 Aluminum cooking pot . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-71
Appendix C External Exposure Dose Coefficients

C-1 NUREG-1640

C EXTERNAL EXPOSURE DOSE COEFFICIENTS

External exposure dose coefficients are calculated for each of 41 source geometries (many of

which include two or more receptor locations) and for each of 112 of the 115 radionuclides

addressed by the present analysis. The dose coefficients for 3 radionuclides—H-3, Ca-41, and

Mn-53—are not assessed. H-3 (tritium) is an extremely weak -emitter which produces a

negligibly small external exposure. Ca-41 and Mn-43 decay by electron capture and emit lowenergy x rays (E < 10 keV) that are below the threshold for external exposure calculations in the

present analysis.

C.1 Methodology

C.1.1 Radiation Transport Methods

The external exposure dose coefficients were calculated by means of the Los Alamos Monte

Carlo code MCNP4C (LANL 2001). The code treats an arbitrary three-dimensional

configuration of materials in geometric cells, and allows for the specification of complex

geometries. Pointwise photo-atomic cross-section data are used. For photons, the detailed

physics modeling takes account of coherent and incoherent scattering with form factors, the

possibility of fluorescent emission after photoelectric absorption, absorption in pair production

with local emission of annihilation radiation, and secondary bremsstrahlung. The code utilizes a

collision cross-section library based on the Evaluated Nuclear Structure Data File (ENSDF),

maintained by the Brookhaven National Laboratory. 

MCNP4C was the latest version of this code at the time of these analyses. An earlier version

was one of the radiation transport codes used to calculate the dose conversion coefficients

presented in ICRP Publication 74 (ICRP 1996). ICRP found good agreement among the several

different codes used for this publication, which constitutes a benchmark and helps justify the use

of MCNP for the present analysis. Los Alamos National Laboratory has also conducted

extensive benchmarking studies of this code.

A condensed-history electron physics model is invoked as needed to transport electrons down to

a 1-keV cutoff. The model provides for the statistical treatment of energy straggling and angular

deflections. Bremsstrahlung photons, impact ionization K-shell x rays, and delta-rays are

produced and sampled during the electron’s random walk. Version 4C incorporates the updated

Sandia National Laboratory’s Integrated Tiger Series electron physics, ITS 3.0. The MCNP4C

code also provides a powerful general source, which allows for the specification of a complex

distributed source term. A rich collection of variance reduction techniques is supported.

The model for each scenario is sufficiently detailed to take into account self-absorption in the

source material matrix; transmission and attenuation by structural shielding; scatter from soil,

pavement, and surrounding structures; and skyshine.
External Exposure Dose Coefficients Appendix C

1

 The individual energies and the calculated dose rates are listed in Table C.3 and subsequent tables.

2

 This method was used for calculating all external exposure dose coefficients, except for the scenario that describes

the exposure to a small metal object close to the body. The method used in those calculations is described in

Section C.2.7.1.

NUREG-1640 C-2

C.1.2 Calculational Methods

Performing photon fluence and external exposure dose assessments for 112 radionuclides, many

of which have complex decay schemes as well as -ray spectra, in about 100 source and receptor

geometries, would require hundreds of thousands of separate calculations. To minimize this

effort while still preserving the desired level of precision, we adopt the approach used by

Eckerman and Ryman (1993) and calculate the dose rate from each of 12 monoenergetic photon

sources uniformly distributed within the source material, with an emission rate of 1 photon per

second per gram of material. In the ensuing discussion, the strength of these sources is referred

to in Bq/g. These sources span the energy range of 10 keV to 5 MeV.1

 

All of the calculated fluence rates are converted to effective dose equivalent (EDE) rates using

the fluence-to-dose conversion coefficients listed in ICRP Publication 51 (ICRP 1987, Table 2 ).2

Log-log interpolation was used for intermediate energies. Effective dose rates are calculated in a

similar manner, applying conversion coefficients in ICRP Publication 74 (ICRP 1996,

Tables A.1 and A.17). These conversion coefficients are defined for five irradiation geometries:

• Anteroposterior (AP)

• Posteroanterior (PA)

• Lateral (LAT)

• Rotational (ROT)

• Isotropic (ISO)

The most appropriate exposure geometry is chosen for each scenario, as indicated in Sections

C.2 – C.5.

C.1.2.1 Dose Coefficients for Individual Nuclides

The complete decay schemes of all the radionuclides in the present study have been compiled by

the Tokai Research Establishment, JAERI (2001). Included are the energies and relative

intensities of  rays, x rays, annihilation quanta, Auger electrons, internal conversion electrons,

and spontaneous fission, as well as detailed -ray spectra. A more complete description of these

data files is presented in Section O2.2 of Volume 4. These data are used to calculate the dose

coefficients for each nuclide in each exposure geometry, using the results of the MCNP

calculations for 12 discrete photon energies, as described below.

For each photon radiation, four sets of MCNP results, two above and two below the energy of

the given photon, are used to perform a log-log cubic spline interpolation. For photon energies

near the ends of the range (< 15 keV or > 2 Mev), a quadratic log-log interpolation is performed
Appendix C External Exposure Dose Coefficients

3

 Internal bremsstrahlung is produced within the radioactive atom emitting the electron and makes a relatively

insignificant contribution to external dose. It is neglected in the present study.

4

 A detailed discussion of the MCNP methodology is presented by Briesmeister (2000).

C-3 NUREG-1640

by fitting a quadratic function to the logs of the three nearest energies. The dose contribution of

each photon is multiplied by the intensity of that radiation and added to the dose contributions of

all the other radiations from the given nuclide.

C.1.2.2 External Bremsstrahlung

When charged particles, such as electrons, are decelerated, a fraction of the kinetic energy is

emitted as a continuous spectrum of x rays. Such radiation is called bremsstrahlung (German for

“braking radiation”). External bremsstrahlung is produced when electrons are scattered in the

surrounding medium and is strongly dependent on the atomic number of the medium.3 In the

present analysis, in which the activity is dispersed throughout the source material, the electrons

would lose all of their energy within this medium. In such a case, bremsstrahlung can make a

significant contribution to the dose from external exposure to radionuclides which emit energetic

electrons, especially nuclides which emit no significant photon radiation. We calculate the

external bremsstrahlung from each electron emitted by each radionuclide in each medium by the

methodology described by Eckerman and Ryman (1993, Appendix C), utilizing the data on

scaled bremsstrahlung spectra compiled by Dillman and Eckerman (Eckerman 2002). 

The energies and intensities of Auger and internal conversion electrons are taken directly from

JAERI 2001. JAERI divides the energy range of each  transition into a number of intervals of

varying widths. The corresponding value of the probability density function—expressed as the

number of  rays per MeV per decay—is listed for each energy interval. The  spectrum in the

present analysis is characterized by assigning to the  rays in each energy interval an energy

corresponding to the midpoint of that interval and an intensity corresponding to the product of

the density function and the width of the interval in MeV. The entire spectrum of each 

transition is thus included in the bremsstrahlung calculation.

A second set of calculations is performed for some  emitters that have no significant -ray

emission. MCNP is used in the coupled electron-photon mode4

 to calculate the dose coefficients

for such nuclides, using the  spectra discussed above. However, Auger and internal conversion

electrons are not included in these MCNP calculations. To ensure that no dose contributions are

neglected, the dose coefficient for each individual radionuclides calculated by this method is

compared to the coefficient calculated by the methodology described by Eckerman and Ryman,

and the coefficient with the higher value is adopted for the analysis. In most cases, the two dose

coefficients agree within a few percent. These calculations are discussed further in the following

sections of this appendix.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-4

C.1.2.3 Variance Reduction

Point, ring, or volume detectors are used for all fluence calculations to improve scoring

efficiency and provide for fine spatial resolution. Ring detectors are only employed in those

scenarios that possessed rotational symmetry. Geometry splitting and Russian roulette

techniques are used in some simulations to more efficiently control particle track populations.4

For some of the simulations of photon energies below 30 keV, the thickness of the source term is

constrained to several mean-free-paths (MFPs) in order to increase source particle sampling in

the outer layers of the source material. 

For scatter contributions from soil, pavement and skyshine, the air and soil volumes are

constrained in thickness to provide at least 2 MFPs of scattering material at all energies. This is

equivalent to 4 MFPs for photons that penetrate to a depth of 2 MFPs and then backscatter to the

detector. This strategy accounts for almost all of the scatter contribution while greatly reducing

the computing time per history. For most energies, the effective thickness of air and soil is

optically thick.

In general, coherent scatter was turned off to improve point detector convergence—a procedure

recommended by the MCNP code developers. Coherent scatter is unimportant for shielding

applications, but because it is highly forward directed it can perturb tally convergence whenever

the photon line of flight is aligned with a point-detector location.

Two additional strategies were used in conjunction with the -decay analyses. To improve the

sampling statistics, bremsstrahlung production was biased in such a way as to increase not only

the total bremsstrahlung produced, but also in favor of higher energy photons. In this way, the

penetrating portion of the x-ray spectrum was more efficiently sampled. Weighting factors were

adjusted to compensate for the increased production, yielding a neutral (unbiased) result. In

addition, the production of knock-on or delta-ray electrons was turned off to decrease the

computing time per history. The delta rays have low energies and contribute essentially nothing

to the total bremsstrahlung production.

C.1.2.4 Uncertainty

A single MCNP analysis incorporates uncertainty via the stochastic nature of radioactive decay

and the interaction of radiation with matter. With adequate running time, the uncertainties from

this source are minimal. Although the uncertainties for a very few very-low-energy photon

sources with significant shielding, or for the MCNP calculations of  bremsstrahlung from

individual nuclides using the coupled photon-electron mode, are as high as 50%, the vast

majority of the analyses have uncertainties well under 1%. In cases where the photon tally or the

calculated dose is too low to produce statistically meaningful results, such results are not

reported.

The labor- and computation-intensive nature of the MCNP analyses does not lend itself to the

thousands of runs that would be required for a comprehensive quantitative analysis of the

uncertainty due to variability in the exposure geometry. Limited analyses of the effect of the
Appendix C External Exposure Dose Coefficients

5

 Roy Sheely, U.S. Department of Energy, Oak Ridge Reservation, private communication with Robert Anigstein,

SC&A, Inc., November 14, 2001.

C-5 NUREG-1640

position of the exposed individual with respect to the source of radiation are performed for a

number of scenarios, as discussed in the following sections of this appendix. These results are

used to estimate the uncertainty parameter for external exposure (Ux). Values of Ux used in each

exposure scenario are listed in Tables B.8 – B.11. For the same reason, uncertainties due to

variability in the size, density, or chemical composition of the radiation source are not addressed

in the present analysis. These parameters are assigned fixed values, which are addressed in the

discussion of the various source geometries in the following sections of this appendix.

C.2 Steel Scenarios

As noted in Table 3.10 of the main report, the exposure scenarios for the steel scrap analysis

included 19 source geometries, in addition to those presented by Eckerman and Ryman (1993). 

The analysis of the external exposure to these sources is discussed in the following sections. The

results of the MCNP analyses are presented as part of the discussion of each exposure scenario.

The interaction of radiation with the source material and surrounding scattering media is strongly

dependent on the elemental composition of these media. The composition of the materials in the

steel scenarios is presented in Tables C.1 and C.2. 

C.2.1 Scrap Pile

C.2.1.1 Exposure Geometry

Scrap piles observed by members of the project team during visits to scrap metal dealers vary

widely in size and shape. A hemispherical pile was adopted for the present analysis. Such a pile

has rotational symmetry; thus, a worker would receive the same dose regardless of his angular

orientation with respect to the pile. Furthermore, a hemispherical pile is completely specified by

only one dimension—e.g., the volume. Consequently, a hemisphere is the simplest and therefore

the most generic shape.

The mass of the pile was based on the size of scrap piles at a large ferrous metal scrap dealer

who was visited by SC&A personnel. The piles ranged from 1,000 to 6,000 tons. The mid-point

of this range—3,500 tons—was adopted for this analysis. Bulk densities of ferrous scrap range

from 16 to 22 lb/ft3

 prior to compaction.5 Twenty pounds per cubic foot (0.32 g/cm3) was

adopted as the bulk density for the present analysis. The scrap is assumed to have the same

elemental composition as SAE 1020, a common carbon steel alloy, as listed in Table C.1. 

The volume and radius of the pile are calculated as follows:
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-6

C.1

V =

= 350,000 ft3 (9,911 m3)

M = 7,000 lb (3,175 kg)

'b = 20 lb/ft3 (320 kg/m3)

The radius is calculated by solving the expression for the volume of a hemisphere:

r = 55 ft (16.8 m)

Table C.1 Composition of materials in steel analysis (wt. fraction)

Element Moist

air

Soil SAE

1020

 Cast

iron 

Steel

slag 

Gypsum Wood EAF

Dust

Baghousea

Fiberglassb

H 6.32e-04 0.021 0.004 0.333 0.060 0.0002 0.019

B 0.0103 0.030

C 0.016 0.002 0.030 0.507 0.189

N 0.751 0.002 0.2331

O 0.235 0.577 0.344 0.500 0.426 0.281 0.3332 0.448

Na 0.012 0.0127 0.022

Mg 0.046 0.012 0.0052

Al 0.050 0.025 0.0027

Si 0.271 0.020 0.066 0.013 0.1025 0.284

P 7.5e-03 0.003 

S 1.5e-03 0.001 0.083 0.005 

Al 0.080

Cl 0.013 0.0055

Ar 0.013 0.0040

K 0.013 

Ca 0.041 0.290 0.083 0.109 0.0471

Mn 0.007 0.007 0.037 0.036 0.0156

Fe 0.011 0.991 0.934 0.184 0.387 0.1680

Zn 0.138 0.0599

Dc 1.20e-03 1.6 7.86 d 2.0 0.66 0.55 1.72 3.61e-03 2.0

a EAF Baghouse interior: EAF dust + fiberglass + moist air

b Fiberglass-resin compound

c Density ( g/cm3

), unless otherwise specified for individual exposure scenarios; bulk densities for aggregate materials

such as soil, slag, and EAF dust

d See descriptions of engine blocks in Sections C.2.11 and C.2.12 for effective densities used in analysis
Appendix C External Exposure Dose Coefficients

C-7 NUREG-1640

C.2

Table C.2 Concrete composition

Element Atom densitya

(cm-3)

Atomic

weight

Partial densityb

(g/cm3)

H 7.86e+21 1.008 0.013

O 4.38e+22 16.00 1.164

Na 1.05e+21 22.99 0.040

Mg 1.40e+20 24.305 0.006

Al 2.39e+21 26.98 0.107

Si 1.58e+22 28.086 0.737

K 6.90e+20 39.098 0.045

Ca 2.92e+21 40.078 0.194

Fe 3.10e+20 55.85 0.029

Total 2.334

a

 American Nuclear Society 1987

b

 Partial density = atom density × AW ÷ NA (NA = 6.02 × 1023 atoms per mole)

Since the worker’s orientation with respect to the pile may vary during the day, the rotational

geometry (ROT) was adopted for the MCNP analysis. The most likely distance from the edge of

the pile is assumed to be 2 m; however, the distance could vary from 1 m to 5 m. Eckerman and

Ryman (1993) assumed that the average height of the body was 1 m above ground level; the

same value was used for all exposure geometries in the present analysis in which the position of

the receptor is not otherwise specified. The analysis included backscatter from soil and moist

air. 

C.2.1.2 Results of Analysis

The results of the analysis are presented in Table C.3. The dose rates from the 12 monoenergetic

photon sources and from the bremsstrahlung from the  decay of 17 selected nuclides are

computed by MCNP at distances of 100 cm and 500 cm from the edge of the pile. These

represent the range of distances of the worker during the duration of his exposure and serve as

the basis of determining the uncertainty parameter (Ux) for this exposure scenario. 

To calculate the dose rate at 200 cm, the assumed likely position, we first calculate the distance

and strength of a fictitious equivalent point source that would produce the same exposure rates at

the same locations as those calculated for the real source. Applying the inverse square law, we

obtain:

R(x) = exposure rate at distance x from real source

Ao = strength of equivalent point source

xo = distance of equivalent point source from real source
External Exposure Dose Coefficients Appendix C

6

 The term “coefficient of variation” is given an expanded meaning in the present context. According to the usual

definition, , where : = mean of the values. R(x) is a derived quantity that is not equal to the mean.

NUREG-1640 C-8

C.3

C.4

To evaluate the constants Ao and xo, we substitute the calculated values of R(x) at two distances:

Solving Equations C.3, we obtain:

Substituting the expressions for Ao and xo from Equations C.4 into Equation C.2 allows us to

calculate the dose rate at a distance of 200 cm. The values of xo and Ao for each of the 12

monoenergetic photon sources and 17 -emitting nuclides are listed in Table C.3, along with the

calculated dose rates at 200 cm. The uncertainty parameter, Ux, is calculated as follows:

= average coefficient of variation6

= 0.64 (pile of steel scrap)

)Di = standard deviation of two MCNP-calculated dose rates (i.e., at 100 and 500 cm)

from source i

R(x) = dose rate from source i at distance x (i.e., 200 cm), calculated by

Equations C.2 – C.4 

n = number of sources analyzed by MCNP for this scenario

= 29

As shown in Table B.8, Ux for the scrap pile is assigned a uniform distribution: 0.4 # Ux # 1.6.

C.5
Appendix C External Exposure Dose Coefficients

C-9 NUREG-1640

Table C.3 Dose rates from pile of steel scrap

Energy

(MeV) or

nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm Cv

a 100 cm 500 cm xo (cm) Ao 200 cm Cva

0.010 1.98e-17 5.15e-19 23.08 1.17e-13 3.74e-18 3.64 1.65e-17 4.30e-19 23.00 9.78e-14 3.12e-18 3.64

0.015 2.61e-16 4.82e-17 -201.43 2.37e-11 1.47e-16 1.02 1.76e-16 3.24e-17 -200.60 1.59e-11 9.91e-17 1.02

0.020 1.09e-15 3.18e-16 -369.82 2.41e-10 7.41e-16 0.74 7.71e-16 2.24e-16 -367.70 1.69e-10 5.23e-16 0.74

0.030 6.14e-15 2.28e-15 -523.99 2.39e-09 4.56e-15 0.60 5.07e-15 1.88e-15 -522.86 1.97e-09 3.76e-15 0.60

0.050 3.96e-14 1.69e-14 -653.65 2.25e-08 3.09e-14 0.52 3.79e-14 1.61e-14 -648.66 2.12e-08 2.95e-14 0.52

0.070 1.28e-13 5.66e-14 -693.93 8.07e-08 1.01e-13 0.50 1.30e-13 5.73e-14 -690.14 8.12e-08 1.02e-13 0.50

0.100 4.23e-13 1.91e-13 -719.38 2.84e-07 3.36e-13 0.49 4.23e-13 1.91e-13 -719.38 2.84e-07 3.36e-13 0.49

0.200 2.66e-12 1.21e-12 -728.70 1.83e-06 2.12e-12 0.48 2.66e-12 1.20e-12 -718.25 1.78e-06 2.11e-12 0.49

0.500 1.21e-11 5.40e-12 -704.97 7.84e-06 9.57e-12 0.49 1.20e-11 5.36e-12 -706.02 7.80e-06 9.50e-12 0.49

1.0 2.86e-11 1.28e-11 -708.44 1.87e-05 2.27e-11 0.49 2.84e-11 1.26e-11 -697.89 1.81e-05 2.24e-11 0.50

2.0 6.22e-11 2.77e-11 -702.42 4.00e-05 4.92e-11 0.50 6.21e-11 2.76e-11 -700.00 3.97e-05 4.91e-11 0.50

5.0 1.43e-10 6.41e-11 -710.35 9.39e-05 1.13e-10 0.49 1.43e-10 6.40e-11 -708.44 9.35e-05 1.13e-10 0.49

C-14 4.60e-17 1.90e-17 -619.46 2.38e-11 3.55e-17 0.54 4.42e-17 1.83e-17 -621.86 2.30e-11 3.41e-17 0.54

P-32 1.21e-13 5.38e-14 -700.50 7.75e-08 9.56e-14 0.50 1.21e-13 5.35e-14 -693.83 7.62e-08 9.54e-14 0.50

S-35 4.57e-17 2.09e-17 -735.57 3.19e-11 3.65e-17 0.48 4.43e-17 2.03e-17 -738.14 3.11e-11 3.54e-17 0.48

Cl-36 1.35e-14 6.07e-15 -714.12 8.95e-09 1.07e-14 0.49 1.35e-14 6.06e-15 -712.09 8.90e-09 1.07e-14 0.49

Ca-45 2.90e-16 1.32e-16 -729.50 2.00e-10 2.31e-16 0.48 2.88e-16 1.30e-16 -718.97 1.93e-10 2.29e-16 0.49

Sr-89 9.15e-14 4.23e-14 -749.70 6.61e-08 7.32e-14 0.48 9.11e-14 4.21e-14 -749.22 6.57e-08 7.29e-14 0.48

Sr-90 5.08e-15 2.32e-15 -733.77 3.53e-09 4.05e-15 0.48 5.07e-15 2.32e-15 -736.31 3.55e-09 4.04e-15 0.48

Y-90 2.61e-13 1.14e-13 -679.57 1.59e-07 2.05e-13 0.51 2.59e-13 1.14e-13 -688.50 1.61e-07 2.04e-13 0.50

Y-91 9.73e-14 4.48e-14 -744.37 6.94e-08 7.78e-14 0.48 9.69e-14 4.47e-14 -746.85 6.95e-08 7.75e-14 0.48

Tc-99 6.64e-16 3.04e-16 -736.98 4.65e-10 5.30e-16 0.48 6.59e-16 3.03e-16 -742.53 4.68e-10 5.27e-16 0.48

Cs-135 4.56e-16 2.04e-16 -707.93 2.98e-10 3.61e-16 0.49 4.52e-16 2.02e-16 -706.66 2.94e-10 3.58e-16 0.49

Pm-147 1.58e-16 6.92e-17 -682.72 9.68e-11 1.24e-16 0.51 1.56e-16 6.83e-17 -682.31 9.55e-11 1.23e-16 0.51

Sm-151 1.57e-18 6.33e-19 -595.80 7.60e-13 1.20e-18 0.55 1.33e-18 5.42e-19 -606.11 6.63e-13 1.02e-18 0.55

Tm-171 3.35e-18 1.59e-18 -785.89 2.63e-12 2.70e-18 0.46 3.01e-18 1.42e-18 -777.34 2.32e-12 2.43e-18 0.46

W-185 1.83e-15 8.13e-16 -699.51 1.17e-09 1.45e-15 0.50 1.82e-15 8.10e-16 -701.65 1.17e-09 1.44e-15 0.50

Tl-204 1.23e-14 5.18e-15 -639.44 6.73e-09 9.54e-15 0.53 1.22e-14 5.17e-15 -646.05 6.79e-09 9.49e-15 0.52

Bk-249 1.19e-17 5.20e-18 -680.08 7.24e-12 9.35e-18 0.51 1.10e-17 4.85e-18 -690.51 6.87e-12 8.67e-18 0.50

Average 0.64 0.64

a

 Coefficient of variation—see text

C.2.2 Slag Pile

The analysis of the slag pile is modeled after that of the scrap pile described in Section C.2.1.1. 

Only the features that are unique to the slag pile are described here.
External Exposure Dose Coefficients Appendix C

7

 Rick West, Sales Manager, International Mill Services, private communication with William C. Thurber, SC&A,

Inc., August 22, 1996.

NUREG-1640 C-10

The mass of the slag pile is assumed to be 20 kt, as discussed in Section 3.7.1.7 in the main

report. The bulk density is 2 g/cm3,

7

 resulting in a volume of 10,000 m3. The radius, as

calculated by Equation C.1, is 16.8 m. The elemental composition of slag is listed in Table C.1. 

The results of the slag pile analysis are presented in Table C.4. The dose rates from the 12

monoenergetic photon sources and from the bremsstrahlung from the  decay of 13 selected

nuclides are computed by MCNP at distances of 100 cm and 500 cm from the edge of the pile. 

These 13 nuclides are isotopes of elements that partition strongly to steel slag. The results

presented in Table C.4 are calculated in the same manner as the results of the scrap pile analysis

discussed in Section C.2.1.2. As shown in this table, the values of Cv for the photon energies of

10 and 15 keV are considerably higher than for the other sources. Photons in this low-energy

range make only minor contributions to the dose coefficients of most of the radionuclides in the

present analysis. Including these Cv values in calculating would bias the uncertainty

analysis. Consequently, these two values are omitted in this calculation. Based on these

results, Ux for processing steel slag is assigned a uniform distribution: 0.6 # Ux # 1.4.

C.2.3 Dust Pile

The analysis of the dust pile is modeled after that of the scrap pile described in Section C.2.1.1. 

Only the features that are unique to the dust pile are described here.

The mass of the dust pile is assumed to be 8,000 tons (7,258 t), as discussed in Section 3.7.1.6 in

the main report. The bulk density is 1.72 g/cm3 (Logan 1993, p. 9). The resulting volume is

4,200 m3. The radius, as calculated by Equation C.1, is 12.63 m. The elemental composition of

EAF dust, listed in Table C.1, is based on data presented by McKenzie-Carter et al. (1995), as

cited in Section J.1.5 of Volume 4 of the present report. 

The results of the dust pile analysis are presented in Tables C.5 and C.6. The dose rates from the

12 monoenergetic photon sources and from the bremsstrahlung from the  decay of 3 selected

nuclides are computed by MCNP at distances of 100 cm and 500 cm from the edge of the pile. 

These 3 nuclides are among the isotopes of elements that partition strongly to EAF dust. 

The results presented in Tables C.5 and C.6 are calculated in the same manner as the results of

the scrap pile analysis discussed in Section C.2.1.2. However, a simpler approach was used to

evaluate the uncertainty parameter, Ux. For each photon source or nuclide listed in the tables, the

difference between dose rates at 100 cm and 200 cm is listed in the column marked 1. 

Similarly, the difference between the 200-cm and 500-cm dose rates is listed under 2. The

average of these two values, divided by the 200-cm dose rate, is listed under . The values

of for the 3 photon energies in the range of 10 – 20 keV are considerably higher than for

the other sources. Since, as was discussed in Section C.2.2, photons in this low-energy range
Appendix C External Exposure Dose Coefficients

C-11 NUREG-1640

make only minor contributions to the dose coefficients of most of the radionuclides in the present

analysis, these values are omitted in the calculation of the average , listed at the bottom of

the last column. Based on these results, Ux for EAF dust processing is assigned a uniform

distribution: 0.6 # Ux # 1.4.

Table C.4 Dose rates from pile of steel slag

Energy

(MeV) or

nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm Cv

a 100 cm 500 cm xo (cm) Ao 200 cm Cva

0.010 5.07e-17 1.23e-18 26.20 2.76e-13 9.14e-18 2.71 4.23E-17 1.03E-18 26.04 2.31e-13 7.65e-18 2.70

0.015 7.10e-16 1.21e-16 -181.23 5.62e-11 3.86e-16 0.76 4.78E-16 8.15E-17 -181.34 3.78e-11 2.60e-16 0.76

0.020 2.92e-15 8.48e-16 -367.49 6.38e-10 1.98e-15 0.52 2.06E-15 5.97E-16 -366.43 4.48e-10 1.40e-15 0.52

0.030 1.60e-14 6.16e-15 -553.97 6.84e-09 1.20e-14 0.41 1.33E-14 5.08E-15 -547.19 5.57e-09 9.98e-15 0.41

0.050 1.02e-13 4.33e-14 -647.92 5.71e-08 7.94e-14 0.37 9.70E-14 4.12E-14 -648.51 5.43e-08 7.55e-14 0.37

0.070 2.99e-13 1.32e-13 -692.01 1.88e-07 2.36e-13 0.35 3.04E-13 1.34E-13 -690.19 1.90e-07 2.40e-13 0.35

0.100 8.40e-13 3.75e-13 -705.38 5.45e-07 6.65e-13 0.35 8.41E-13 3.76E-13 -707.17 5.48e-07 6.66e-13 0.35

0.200 3.64e-12 1.61e-12 -694.25 2.30e-06 2.87e-12 0.35 3.64E-12 1.61E-12 -694.25 2.30e-06 2.87e-12 0.35

0.500 1.32e-11 5.73e-12 -672.53 7.88e-06 1.03e-11 0.36 1.31E-11 5.68E-12 -671.21 7.79e-06 1.03e-11 0.36

1.0 3.03e-11 1.29e-11 -651.04 1.71e-05 2.36e-11 0.37 3.01E-11 1.28E-11 -649.79 1.69e-05 2.34e-11 0.37

2.0 6.75e-11 2.77e-11 -612.97 3.43e-05 5.19e-11 0.38 6.74E-11 2.77E-11 -614.44 3.44e-05 5.19e-11 0.38

5.0 1.70e-10 6.98e-11 -613.50 8.65e-05 1.31e-10 0.38 1.70E-10 6.97E-11 -612.08 8.62e-05 1.31e-10 0.38

P-32 8.71e-14 3.67e-14 -639.99 4.77e-08 6.76e-14 0.37 8.68E-14 3.65E-14 -637.87 4.73e-08 6.73e-14 0.37

S-35 4.69e-17 2.15e-17 -738.65 3.30e-11 3.74e-17 0.34 4.40E-17 2.03E-17 -747.03 3.16e-11 3.52e-17 0.34

Cl-36 9.41e-15 4.27e-15 -725.59 6.41e-09 7.49e-15 0.34 9.38E-15 4.25E-15 -723.69 6.36e-09 7.46e-15 0.34

Ca-45 2.91e-16 1.61e-16 -1061.4 3.93e-10 2.47e-16 0.26 2.87E-16 1.58E-16 -1050.2 3.80e-10 2.43e-16 0.27

Sr-89 6.27e-14 2.78e-14 -697.13 3.98e-08 4.95e-14 0.35 6.25E-14 2.77E-14 -696.65 3.97e-08 4.93e-14 0.35

Sr-90 4.31e-15 1.86e-15 -665.94 2.53e-09 3.37e-15 0.36 4.29E-15 1.85E-15 -665.11 2.51e-09 3.36e-15 0.36

Y-90 1.79e-13 7.34e-14 -612.21 9.08e-08 1.38e-13 0.38 1.79E-13 7.31E-14 -608.18 8.98e-08 1.37e-13 0.39

Y-91 7.32e-14 3.25e-14 -698.77 4.67e-08 5.78e-14 0.35 7.29E-14 3.23E-14 -696.31 4.62e-08 5.75e-14 0.35

Cs-135 5.32e-16 2.08e-16 -567.47 2.37e-10 4.02e-16 0.40 5.27E-16 2.05E-16 -562.97 2.32e-10 3.98e-16 0.40

Pm-147 1.62e-16 7.97e-17 -839.63 1.43e-10 1.32e-16 0.31 1.59E-16 7.81E-17 -837.14 1.40e-10 1.30e-16 0.31

Sm-151 1.81e-18 6.52e-19 -500.46 6.53e-13 1.33e-18 0.44 1.54E-18 5.55E-19 -500.81 5.56e-13 1.13e-18 0.44

Tm-170 1.54e-14 6.98e-15 -724.13 1.05e-08 1.22e-14 0.34 1.54e-14 6.96E-15 -720.52 1.04e-08 1.22e-14 0.34

Bk-249 1.24e-17 5.00e-18 -595.89 6.00e-12 9.48e-18 0.39 1.13E-17 4.60E-18 -605.06 5.62e-12 8.67e-18 0.39

Averageb 0.37 0.37

a

 Coefficient of variation—see text

b

 Omits 0.010 and 0.015 MeV values—see text

C.2.4 Baghouse

The baghouse consists of 10 modules arranged in two rows of 5 modules each; each module is

15 ft × 15 ft × 30 ft high (~4.6 × 4.6 × 9.1 m) (see Figure C.1). Each module contains 66

fiberglass filters, each weighing 5.9 lb (2.67 kg) and containing 10 lb (4.54 kg) of EAF dust. 

Each module thus contains 176.6 kg of fiberglass (2.67 × 66 = 176.6) and 299 kg of dust,
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-12

Figure C.1 Layout of baghouse modules

uniformly mixed and distributed throughout its volume. The radiation sources are assumed to be

uniformly distributed throughout the dust.

In the case of the bremsstrahlung calculation for Pb-210, a low-energy  emitter, only the

radiation sources in module I4, the module containing the tally points, are included in the

calculations. Contributions from radiation sources outside this module would be effectively

shielded by the 1⁄2-inch-thick (1.2-cm) interior steel partitions. 

C.2.5 Large Metal Object

The large generic metal object is a SAE 1020 steel cylindrical shell with activity uniformly

distributed throughout the metal. The right circular cylinder, which stands upright in the center

of a room, is 1.7 m high with an inner radius of 29.2 cm and an outer radius of 30 cm. To

maintain rotational symmetry, the room is modeled as a 3-m-high right circular cylinder with a

radius of 5 m. The walls, floor, and ceiling are concrete which is optically thick, as discussed in

Section C.1.2.3. The MCNP analysis employs a ring detector to take advantage of the rotational

symmetry. Tally locations are distances of 100, 200, and 300 cm from the outer surface of the

steel cylinder, at a height of 100 cm above the floor. For photon energies # 100 keV, the room is

filled with moist air. Rotational irradiation geometry is assumed in the MCNP dose calculations.
Appendix C External Exposure Dose Coefficients

C-13 NUREG-1640

Table C.5 Effective dose equivalent rates from pile of EAF dust (Sv/s per Bq/g)

Energy (MeV)

or nuclide 100 cm 500 cm xo (cm) Ao 200 cm )1 )2

a

0.010 2.71e-17 6.66e-19 25.64 1.50e-13 4.93e-18 2.22e-17 4.26e-18 2.68

0.015 3.57e-16 5.92e-17 -174.78 2.70e-11 1.92e-16 1.65e-16 1.33e-16 0.78

0.020 1.49e-15 3.96e-16 -325.65 2.70e-10 9.77e-16 5.13e-16 5.81e-16 0.56

0.030 8.30e-15 2.81e-15 -456.60 2.57e-09 5.96e-15 2.34e-15 3.15e-15 0.46

0.050 5.23e-14 2.00e-14 -548.20 2.20e-08 3.93e-14 1.30e-14 1.93e-14 0.41

0.07 1.64e-13 6.46e-14 -574.16 7.45e-08 1.24e-13 3.96e-14 5.98e-14 0.40

0.100 5.15e-13 2.06e-13 -588.30 2.44e-07 3.93e-13 1.22e-13 1.87e-13 0.39

0.200 2.84e-12 1.12e-12 -575.23 1.29e-06 2.15e-12 6.85e-13 1.03e-12 0.40

0.500 1.20e-11 4.62e-12 -553.97 5.13e-06 9.03e-12 2.97e-12 4.41e-12 0.41

1.0 2.84e-11 1.07e-11 -535.75 1.15e-05 2.12e-11 7.20e-12 1.05e-11 0.42

2.0 6.26e-11 2.34e-11 -529.32 2.48e-05 4.66e-11 1.60e-11 2.32e-11 0.42

5.0 1.54e-10 5.73e-11 -525.59 6.03e-05 1.14e-10 3.95e-11 5.72e-11 0.42

Cl-36 1.02e-14 4.05e-15 -581.45 4.74e-09 7.76e-15 2.44e-15 3.71e-15 0.40

Cs-135 3.94e-16 1.66e-16 -639.90 2.16e-10 3.06e-16 8.82e-17 1.40e-16 0.37

Pb-210 3.22e-17 1.07e-17 -444.41 9.54e-12 2.30e-17 9.22e-18 1.23e-17 0.47

Averageb 0.41

a

 Average deviation—see text

b

 Omits 0.010 – 0.020 MeV values—see text

Table C.6 Effective dose rates from pile of EAF dust (Sv/s per Bq/g)

Energy (MeV)

or nuclide 100 cm 500 cm xo (cm) Ao 200 cm )left )right

a

0.010 2.26e-17 5.56e-19 25.59 1.25e-13 4.11e-18 1.85e-17 3.56e-18 2.68

0.015 2.40e-16 3.99e-17 -175.38 1.82e-11 1.29e-16 1.11e-16 8.93e-17 0.78

0.020 1.05e-15 2.79e-16 -325.55 1.90e-10 6.88e-16 3.62e-16 4.09e-16 0.56

0.030 6.86e-15 2.31e-15 -453.04 2.10e-09 4.92e-15 1.94e-15 2.61e-15 0.46

0.050 5.00e-14 1.90e-14 -542.87 2.07e-08 3.74e-14 1.26e-14 1.84e-14 0.41

0.070 1.68e-13 6.55e-14 -564.98 7.43e-08 1.27e-13 4.11e-14 6.14e-14 0.40

0.100 5.15e-13 2.06e-13 -588.30 2.44e-07 3.93e-13 1.22e-13 1.87e-13 0.39

0.200 2.84e-12 1.12e-12 -575.23 1.29e-06 2.15e-12 6.85e-13 1.03e-12 0.40

0.500 1.19e-11 4.58e-12 -553.69 5.09e-06 8.95e-12 2.95e-12 4.37e-12 0.41

1.0 2.82e-11 1.06e-11 -533.85 1.13e-05 2.10e-11 7.16e-12 1.04e-11 0.42

2.0 6.26e-11 2.33e-11 -525.87 2.45e-05 4.65e-11 1.61e-11 2.32e-11 0.42

5.0 1.54e-10 5.72e-11 -524.20 6.00e-05 1.14e-10 3.96e-11 5.72e-11 0.42

Cl-36 1.02e-14 4.04e-15 -579.18 4.71e-09 7.75e-15 2.45e-15 3.71e-15 0.40

Cs-135 3.91e-16 1.64e-16 -635.20 2.11e-10 3.03e-16 8.80e-17 1.39e-16 0.38

Pb-210 2.58e-17 8.75e-18 -457.77 8.03e-12 1.86e-17 7.25e-18 9.80e-18 0.46

Averageb 0.41

a

 Average deviation—see text

b

 Omits 0.010 – 0.020 MeV values—see text
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-14

Table C.7 Baghouse geometry (cm)

Location Thickness X YZ

Min Max Min Max Min Max

Inner wall

(i1 - i5)

1 1.3 -1145.5 1145.5 -0.6 0.6 0.0 914.4

2 1.3 -687.7 -686.4 -457.8 457.8 0.0 914.4

3 1.3 -229.9 -228.6 -457.8 457.8 0.0 914.4

4 1.3 228.6 229.9 -457.8 457.8 0.0 914.4

5 1.3 686.4 687.7 -457.8 457.8 0.0 914.4

Outer wall

(x1 - x4)

1 0.6 -1145.5 1145.5 229.2 229.9 0.0 914.4

2 0.6 -1145.5 1145.5 -229.9 -229.2 0.0 914.4

3 0.6 -1146.2 -1145.5 -458.5 458.5 0.0 914.4

4 0.6 1145.5 1146.2 -458.5 458.5 0.0 914.4

Ceiling 0.6 -1146.2 1146.2 -458.5 458.5 914.4 915.0

Floor 0.6 -1146.2 1146.2 -458.5 458.5 -0.6 0.0

Concrete slab 30.5 -  -  -731.5 -701.0

Tally points (TP) 1 0.0 229.2 100

2 128.6 100.6

Table C.8 Dose rates in baghouse

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g)a Effective dose (Sv/s per Bq/g)a

TP 1 TP 2 Ave. Cv

b TP 1 TP 2 Ave. Cvb

0.010 2.08e-16 2.11e-16 2.10e-16 0.010 1.90e-16 1.93e-16 1.92e-16 0.011

0.015 1.36e-15 1.38e-15 1.37e-15 0.010 9.28e-16 9.37e-16 9.33e-16 0.007

0.020 4.83e-15 4.84e-15 4.84e-15 0.001 3.23e-15 3.24e-15 3.24e-15 0.002

0.030 2.09e-14 1.90e-14 2.00e-14 0.067 1.56e-14 1.42e-14 1.49e-14 0.066

0.050 5.93e-14 5.05e-14 5.49e-14 0.113 5.42e-14 4.62e-14 5.02e-14 0.113

0.070 8.80e-14 7.50e-14 8.15e-14 0.113 8.42e-14 7.18e-14 7.80e-14 0.112

0.100 1.29e-13 1.12e-13 1.21e-13 0.100 1.26e-13 1.09e-13 1.18e-13 0.102

0.200 3.45e-13 3.13e-13 3.29e-13 0.069 3.34e-13 3.03e-13 3.19e-13 0.069

0.500 1.08e-12 1.02e-12 1.05e-12 0.040 1.05e-12 9.99e-13 1.02e-12 0.035

1.0 2.21e-12 2.13e-12 2.17e-12 0.026 2.17e-12 2.09e-12 2.13e-12 0.027

2.0 4.13e-12 4.02e-12 4.08e-12 0.019 4.07e-12 3.96e-12 4.02e-12 0.019

5.0 8.61e-12 8.47e-12 8.54e-12 0.012 8.42e-12 8.28e-12 8.35e-12 0.012

Cl-36 1.30e-15 1.13e-15 1.22e-15 0.099 1.22e-15 1.06e-15 1.14e-15 0.099

Cs-135 1.13e-16 9.77e-17 1.05e-16 0.103 1.01e-16 8.70e-17 9.40e-17 0.105

Pb-210 1.48e-19 1.32e-19 1.40e-19 0.081 1.12e-19 9.97e-20 1.06e-19 0.082

Average 0.058 0.057

a

 Normalized to 1 Bq/g in dust

b

 Coefficient of variation

The results of the analysis are presented in Tables C.9 and C.10. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the three location described above. 

The coefficient of variation is calculated in the conventional manner, based on the mean and
Appendix C External Exposure Dose Coefficients

C-15 NUREG-1640

standard deviation at each location. The values of Cv for the 3 photon sources with the lowest

energies are considerably higher than for the other sources. Since, as was discussed in

Section C.2.2, photons in this low-energy range make only minor contributions to the dose

coefficients of most of the radionuclides in the present analysis, is calculated on the basis of

the 9 sources, E  30 keV. Based on these results, Ux for the large metal object is assigned a

uniform distribution: 0.2 # Ux # 1.8. 

Table C.9 Dose rates from large metal object

Energy

 (MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 200 cm 300 cm CV

a 100 cm 200 cm 300 cm CVa

0.010 4.69e-18 8.57e-19 2.37e-19 1.25 3.92e-18 7.15e-19 1.98e-19 1.25

0.015 4.97e-17 1.46e-17 6.10e-18 0.98 3.35e-17 9.80e-18 4.10e-18 0.99

0.020 1.93e-16 6.24e-17 2.87e-17 0.92 1.36e-16 4.40e-17 2.02e-17 0.92

0.030 1.01e-15 3.44e-16 1.67e-16 0.88 8.33e-16 2.85e-16 1.38e-16 0.87

0.050 6.40e-15 2.31e-15 1.18e-15 0.83 6.14e-15 2.21e-15 1.13e-15 0.83

0.070 2.09e-14 7.83e-15 4.17e-15 0.80 2.14e-14 7.98e-15 4.23e-15 0.81

0.100 6.98e-14 2.70e-14 1.48e-14 0.78 6.98e-14 2.70e-14 1.49e-14 0.77

0.200 3.70e-13 1.43e-13 7.91e-14 0.77 3.70e-13 1.43e-13 7.91e-14 0.77

0.500 1.27e-12 4.73e-13 2.54e-13 0.80 1.25e-12 4.68e-13 2.52e-13 0.80

1.0 2.50e-12 9.05e-13 4.74e-13 0.83 2.48e-12 8.97e-13 4.70e-13 0.83

2.0 4.51e-12 1.60e-12 8.19e-13 0.84 4.52e-12 1.60e-12 8.19e-13 0.84

5.0 9.10e-12 3.17e-12 1.60e-12 0.86 9.09e-12 3.17e-12 1.60e-12 0.86

Averageb 0.82 0.82

a

 Coefficient of variation

b

 Omits 0.010 – 0.020 MeV values—see text

The bremsstrahlung from the six -emitting nuclides listed in Table C.10 is calculated only at the

nominal average position of the exposed individual, 200 cm from the outer surface of the

cylinder. These six nuclides are isotopes of elements that partition strongly to the molten steel. 

Table C.10 Large metal object–$ bremsstrahlung (Sv/s per Bq/g)

Nuclide EDE Effective dose

C-14 3.05e-18 2.95e-18

P-32 5.76e-15 5.73e-15

S-35 3.17e-18 3.07e-18

Tc-99 4.08e-17 4.05e-17

W-185 1.02e-16 1.02e-16

Tl-204 6.22e-16 6.20e-16

Note: distance = 200 cm
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-16

C.2.6 Small Metal Object

The small generic metal object is a hollow steel sphere with activity uniformly distributed

throughout the metal. The spherical shell has an inner radius of 12.24 cm and an outer radius of

13 cm. It is located in the center of a concrete room, the center of the sphere being 100 cm

above the floor. The room is modeled as a 2.5-m-high right circular cylinder with a 4-m radius. 

The materials of the sphere and the room are the same as for the large metal object scenario

described in Section C.2.5. The tally locations are 100, 200, and 300 cm from the center of

sphere, at a height of 100 cm above the floor.

The results of the analysis are presented in Tables C.11 and C.12. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the three location described above. 

Because of the large variation of dose rate with distance, Ux is assigned a specially constructed

distribution. By fitting parameters to the data, we derive the following Crystal Ball distribution: 

Ux = 0.1 + 9.9 × Beta(, , s), with  = 0.577,  = 5.77, s = 1.

Table C.11 Dose rates from small metal object

Energy

 (MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 200 cm 300 cm 100 cm 200 cm 300 cm

0.010 5.10e-19 6.56e-20 1.63e-20 4.26e-19 5.47e-20 1.36e-20

0.015 4.78e-18 1.01e-18 3.83e-19 3.22e-18 6.82e-19 2.58e-19

0.020 1.81e-17 4.27e-18 1.78e-18 1.27e-17 3.01e-18 1.25e-18

0.030 9.33e-17 2.34e-17 1.03e-17 7.73e-17 1.93e-17 8.54e-18

0.050 5.92e-16 1.58e-16 7.44e-17 5.67e-16 1.51e-16 7.11e-17

0.070 1.92e-15 5.44e-16 2.68e-16 1.97e-15 5.53e-16 2.71e-16

0.100 6.48e-15 1.91e-15 9.75e-16 6.48e-15 1.91e-15 9.77e-16

0.200 3.57e-14 1.06e-14 5.57e-15 3.57e-14 1.06e-14 5.57e-15

0.500 1.27e-13 3.57e-14 1.79e-14 1.26e-13 3.54e-14 1.78e-14

1.0 2.59e-13 6.92e-14 3.34e-14 2.56e-13 6.86e-14 3.31e-14

2.0 4.78e-13 1.24e-13 5.81e-14 4.78e-13 1.24e-13 5.81e-14

5.0 9.79e-13 2.50e-13 1.14e-13 9.78e-13 2.50e-13 1.14e-13

Table C.12 Small metal object–$ bremsstrahlung

Nuclide EDE (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

C-14 2.11e-19 2.04e-19

P-32 4.22e-16 4.20e-16

S-35 2.31e-19 2.22e-19

Tc-99 2.90e-18 2.88e-18

W-185 7.33e-18 7.30e-18

Tl-204 4.53e-17 4.52e-17

 Note: distance = 200 cm
Appendix C External Exposure Dose Coefficients

C-17 NUREG-1640

C.2.7 Small Object Next to Body

The exposure to a metal object directly on or next to the skin cannot be modeled by applying the

fluence-to-dose conversion coefficients used in the other scenarios. These coefficients were

derived for a plane wave of incident photons, and would produce highly distorted results for such

an intimate geometry. Therefore this scenario was modeled by means of anthropomorphic

phantoms—mathematical models that allow MCNP to directly calculate the doses to the various

organs of the human body. These doses are then combined, using the appropriate weighting

factors, to derive the doses to the whole body.

C.2.7.1 Analytical Approach

Effective dose equivalents and effective doses are calculated for a source placed at three

different locations on male and female anthropomorphic phantoms. The objective is to find the

one location which gives the maximum dose. The calculations are performed for the 12 discrete

photon energies at all three locations. Effective dose equivalent and effective dose are calculated

for 8 -emitting nuclides at the source location that yielded the highest dose from the photon

calculations.

Dosimetric Quantities

The effective dose equivalent (HE) is defined as the weighted average of the dose equivalents,

each weighted by a tissue or organ weighting factor, given by

where T represents a tissue or organ of the human body, HT is the dose equivalent in the tissue,

and wT is a tissue weighting factor specified by ICRP (1977). For the radiations of concern in

this analysis, the dose equivalent and the absorbed dose in a tissue are numerically equal (i.e. the

radiation quality factor is unity).

The effective dose (E) is defined as the sum of the weighted equivalent doses in all the tissues

and organs of the body (ICRP 1991). It is given by the expression:

where HT is the equivalent dose in tissue or organ T and wT1 is the weighting factor for tissue T.

Tissue weighting factors, defined by the ICRP for both effective dose equivalent (EDE) and

effective dose, are shown in Table C.13.

Methodology

Effective dose equivalents and effective dose are calculated using anthropomorphic phantoms

with the ICRP-specified tissues and organs. The MCNP is used to calculate the absorbed dose to
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-18

each organ in both a male and a female phantom. For photon energies # 1.5 MeV, secondary

electrons are not transported and the organ doses are calculated using a kerma approximation. 

For photon energies > 1.5 MeV and for the -emitting nuclides, secondary electrons were

transported and the organ doses were calculated using the energy deposited in each cell.

Since tissue and organ doses are calculated for both male and female phantoms, the effective

dose equivalent is determined using the following formula (ICRP 1991):

wbr = tissue-weighting factor for breast

Hbr = dose equivalent to breast

HT% = dose equivalent to tissue T of male phantom

HT& = dose equivalent to tissue T of female phantom

A corresponding formula is utilized to calculate the effective dose.

Table C.13 Tissue weighting factors

Tissue or organ wT (EDE) wT1(effective dose)

Gonads 0.25 0.2

Bone marrow (red) 0.12 0.12

Colon - 0.12

Lung 0.12 0.12

Stomach - 0.12

Bladder - 0.05

Breast 0.15 0.05

Liver - 0.05

Esophagus - 0.05

Thyroid 0.03 0.05

Skin - 0.01

Bone surface 0.03 0.01

Remainder 0.30a 0.05b

Total 1.00 1.00

Sources: ICRP 1977 (wT) and ICRP 1991 (wT1)

a The value of 0.30 is applied to the average dose among the five remaining organs or tissues receiving the highest dose,

excluding the skin, lens of eyes, and the extremities.

b The remainder is composed of the following tissues and organs: adrenals, brain, small intestines, kidney, muscle,

pancreas, spleen, thymus, and uterus. The value of 0.05 is applied to the average dose to the remainder tissues. 

However, if a member of the remainder receives a dose in excess of the highest dose in any of the twelve organs for

which a weighting factor is specified, a weighting factor of 0.025 is applied to that organ and a weighting factor of

0.025 is applied to the average dose in the rest of the remainder.

C.8
Appendix C External Exposure Dose Coefficients

8

 J. E. Tanner, Pacific Northwest National Laboratory, private communication with Michele Sutton Ferenci, SC&A,

Inc., ca. March, 2002.

C-19 NUREG-1640

Figure C.2 Cross-sectional view of male

anthropomorphic phantom

Phantoms

In this analysis, the Pacific Northwest National

Laboratory (PNNL) male and female versions of the

MIRD (Snyder et al. 1969, 1978) anthropomorphic

phantom were modified and used to calculate organ

absorbed dose (Tanner 1988).8

 Nabelssi (1993),

using the model reported by Zankl et al. (1992),

added the esophagus and skin to the PNNL

phantoms. The PNNL female phantom is a scaleddown version of the MIRD phantom with the

appropriate anatomy changes. The modified PNNL

phantoms are similar to the Adam and Eva phantoms

developed at Germany’s National Research Center

for Environment and Health, GSF (Kramer et al.

1982). A cross-sectional view of the male phantom

is shown in Figure C.2. 

A comparison of the masses of organs in the MIRD

and the modified PNNL male phantom is presented

in Table C.14.

Source and Exposure Geometry

The source is modeled as a cylindrical disk of SAE

1020 steel with a radius of 2.0 cm, a thickness of 0.456 cm, and a mass of 45 g. The activity is

uniformly distributed throughout the metal. As shown in Figure C.3, the source is modeled at

three different locations on each of the two phantoms: the waist, center of ventral side (5 cm

above the pelvic bone); the center of the sternum, ventral side; and the forehead, midway

between the eyes. Each phantom is located in a cylindrical room filled with moist air, illustrated

in Figure C.4. The walls, floor, and ceiling consist of 30-cm-thick concrete. The room has a

radius of 2 m and a height of 2.5 m.

C.2.7.2 Results of Analysis

The results of the analysis are presented in Table C.15, which lists the dose rates from the 12

monoenergetic photon sources in three locations on the anthropomorphic phantoms. The results

from the male and female phantoms were combined according to Equation C.8. The source on

the sternum yields the highest effective dose equivalent and effective dose rate for each photon

energy. These doses are adopted as the dose rates from the small object next to body in the

present analysis.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-20

In order to estimate the uncertainty parameter, separate calculations of effective dose equivalents

and effective doses from 0.1 MeV and 1 MeV photon sources on the sternum were performed for

the male and female phantoms. The results are listed in Table C.16. The average of the

coefficients of variation for the four pairs of values is listed at the bottom of the table. Based on

these results, Ux for the small object on body is assigned a uniform distribution: 0.7 # Ux # 1.3. 

The results for the eight -emitting nuclides (including Bi-210, a short-lived daughter of Pb-210)

located on the sternum are listed in Table C.17.

Table C.14 Organ masses of anthropomorphic phantoms (g)

Organs MIRD Phantom Modified PNNL Phantom

Adrenals 15.5 19.4

Bladder 245.13 245.2

Brain 1,451 1,452.2

Esophagus — 40.6

GI Tract

 Stomach 396.9 396.8

 Sm. Intestines 1,044 1,040.3

 Upper Lg. Intestines 429.2 429.7

 Lower Lg. Intestines 296.9 293.8

Kidneys (both) 284.2 284.9

Liver 1,809 1,810.8

Lungs (both) 999.2 999.6

Muscle 28,000 30,073.7

Ovaries 8.268 10.8

Pancreas 60.27 60.1

RBM 1,500 1169

Skeleton 10,470 10,423.5

Skin 2,833 1,810.4

Spleen 173.6 173.9

Testes 37.08 37

Thymus 24.8 24.8

Thyroid 19.63 29.9

Uterus 65.4 80.2

Total body 69,880 70,060 ± 0.01%
Appendix C External Exposure Dose Coefficients

C-21 NUREG-1640

Figure C.3 Location of sources on the anthropomorphic phantoms

Figure C.4 Location of phantom in concrete-walled room
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-22

Table C.15 Dose rates from small object next to body

Energy

 (MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

Forehead Sternum Waist Forehead Sternum Waist

0.010 6.57e-20 3.21e-18 1.01e-19 6.57e-20 3.21e-18 1.01e-19

0.020 8.24e-19 1.18e-17 5.49e-19 8.24e-19 1.18e-17 5.49e-19

0.020 3.70e-18 3.00e-17 2.37e-18 3.70e-18 3.00e-17 2.37e-18

0.030 2.70e-17 1.13e-16 2.61e-17 2.70e-17 1.13e-16 2.61e-17

0.050 1.85e-16 5.45e-16 2.49e-16 1.85e-16 5.45e-16 2.49e-16

0.070 5.27e-16 1.49e-15 8.15e-16 5.27e-16 1.49e-15 8.15e-16

0.100 1.21e-15 3.70e-15 2.15e-15 1.21e-15 3.70e-15 2.15e-15

0.200 3.83e-15 1.29e-14 6.80e-15 3.83e-15 1.29e-14 6.80e-15

0.500 1.16e-14 3.85e-14 1.89e-14 1.16e-14 3.85e-14 1.89e-14

1.0 2.28e-14 7.61e-14 3.72e-14 2.28e-14 7.61e-14 3.72e-14

2.0 4.24e-14 1.36e-13 7.11e-14 4.24e-14 1.36e-13 7.11e-14

5.0 8.42e-14 2.65e-13 1.35e-13 8.42e-14 2.65e-13 1.35e-13

Table C.16 Small object next to body—uncertainty parameter

Energy

(MeV)

EDE (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

Male Female Cv

a Male Female Cva

0.1 4.73e-17 7.68e-17 0.34 3.06e-17 4.10e-17 0.21

1.0 8.23e-16 1.59e-15 0.45 5.58e-16 8.08e-16 0.26

Average (EDE and effective dose ) 0.31

a

 Coefficient of variation

Table C.17 Small object next to body–$ bremsstrahlung

Nuclide EDE (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

C-14 1.67e-17 6.67e-18

P-32 7.75e-15 3.11e-15

S-35 1.69e-17 6.71e-18

Tc-99 1.13e-16 4.55e-17

Cs-135 8.56e-17 3.42e-17

W-185 2.23e-16 9.01e-17

Tl-204 1.02e-15 4.13e-16

Bi-210 2.71e-15 1.09e-15

C.2.8 Truck Scenarios

A number of the exposure scenarios involve material being transported by highway

trucks—specifically, tractor-trailer combinations. The descriptions of the trucks and trailers in

the present analysis are based on commercial vehicles that are likely to be used for particular

applications. Specific vehicles are selected for individual scenarios to provide a broad crosssection of makes and models of trucks in the analysis.
Appendix C External Exposure Dose Coefficients

9

 Al Johnson, Duratek, Inc., private communication with Robert Anigstein, SC&A, Inc., November 16, 2001.

10 According to the Federal Highway Administration, the maximum allowable weight of a loaded truck is 80,000 lb

(36.3 t). Accounting for the weight of a heavy-duty trailer, the tractor, and fuel, 20 t is a practical upper-end load.

C-23 NUREG-1640

Calculations of doses to an individual occupying the driver’s seat utilize the posteroanterior (PA)

irradiation geometry, since the radiation source is located behind the driver. Doses to an

individual in the sleeper berth utilize the rotational (ROT) geometry.

C.2.8.1 Scrap Truck

The truck used to transport steel scrap is based on a heavy-duty highway truck with a thickwalled trailer and steel cab, suitable for loading scrap at a scrap yard or demolition site. The

trailer is 8 ft wide × 5 ft high × 40 ft long (243.8 cm × 152.4 cm × 12.19 m), with sides and

bottom of 1⁄4-in (0.635-cm) steel.9 The mass of the scrap is 20 t, which is at the upper end of

loads that are permitted on public highways in the United States.10 Both the trailer and the scrap

consist of SAE 1020 steel. The load is assumed to fill the entire volume of the trailer—45.31

m3

—resulting in an average density of 0.4414 g/cm3. The distance between the driver and the

front of the load ranges from 8 ft to 11 ft (2.4 – 3.4 m).

The cab is modeled as a rectangular shell composed of SAE 1020 steel with a uniform wall

thickness of 0.060 in (0.15 cm). The dimensions of the cab, the position of the driver, and the

height of the truck above the pavement are scaled from an engineering drawing of the Heil

Trailer International Super Jet Model 1040 dry bulk trailer, shown in Figure C.5. Since the trips

are short (see Section 3.7.3.1 of the main report), the truck would be equipped with a day cab

(i.e., without a sleeper berth). The detailed dimensions are shown in Table C.18. The height

above ground of the two tally points is centered on the load.

Table C.18 Scrap truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load 0 -1219 -121.9 121.9 0 152.4

Trailer: 4 sides + bottom 0.635 0 -1219 -121.9 121.9 0 152.4

Truck cab: 6 walls 0.15 213 396 -107 107 0 152.4

Pavement — — -125

Tally points (TP)

1 244

53 76.2

2 335
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-24

Figure C.5 Schematic of Heil Trailer International Super Jet Model 1040 aluminum dry bulk trailer + tractor (note: xaxis reversed)
Appendix C External Exposure Dose Coefficients

C-25 NUREG-1640

The results of the analysis are presented in Table C.19. The dose rates from 10 of the 12

monoenergetic photon sources and 15 -emitting nuclides are computed by MCNP at the two

location specified in Table C.18. Because of the strong absorption of low-energy photons by the

walls of the truck cab, the dose rates from 10 and 15 keV sources are too low to be statistically

meaningful and are therefore not listed. Dose rates from bremsstrahlung from very low-energy

-emitting nuclides (i.e., Sm-151, Tm-171, Pu-241, and Bk-249) are also too low to be

statistically meaningful—these nuclides are therefore not listed. The average of the dose rates at

the two tally points is adopted as the dose rate from each of the 10 photon sources and 15 beta

spectra in this exposure geometry. is calculated on the basis of all 25 sources. Based on

these results, Ux for the driver of the scrap truck is assigned a uniform distribution: 0.7 # Ux

# 1.3.

Table C.19 Dose rates to scrap truck driver

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.020 3.01e-34 8.89e-34 5.95e-34 0.70 1.10e-34 3.21e-34 2.16e-34 0.69

0.030 5.35e-23 7.40e-23 6.38e-23 0.23 2.87e-23 4.01e-23 3.44e-23 0.23

0.050 5.04e-18 5.41e-18 5.23e-18 0.05 3.78e-18 4.06e-18 3.92e-18 0.05

0.070 3.21e-16 2.48e-16 2.85e-16 0.18 2.77e-16 2.13e-16 2.45e-16 0.18

0.100 1.02e-14 6.62e-15 8.41e-15 0.30 9.27e-15 6.01e-15 7.64e-15 0.30

0.200 2.35e-13 1.48e-13 1.92e-13 0.32 2.17e-13 1.37e-13 1.77e-13 0.32

0.500 1.37e-12 8.53e-13 1.11e-12 0.33 1.28e-12 7.97e-13 1.04e-12 0.33

1.0 3.31e-12 2.06e-12 2.69e-12 0.33 3.10e-12 1.93e-12 2.52e-12 0.33

2.0 7.04e-12 4.36e-12 5.70e-12 0.33 6.62e-12 4.11e-12 5.37e-12 0.33

5.0 1.57e-11 9.75e-12 1.27e-11 0.33 1.46e-11 9.05e-12 1.18e-11 0.33

C-14 4.10e-19 2.80e-19 3.45e-19 0.27 3.72e-19 2.53e-19 3.13e-19 0.27

P-32 1.26e-14 7.81e-15 1.02e-14 0.33 1.17e-14 7.27e-15 9.49e-15 0.33

S-35 4.94e-19 3.23e-19 4.09e-19 0.30 4.47e-19 2.92e-19 3.70e-19 0.30

Cl-36 9.82e-16 6.35e-16 8.09e-16 0.30 9.08e-16 5.87e-16 7.48e-16 0.30

Ca-45 9.43e-18 5.61e-18 7.52e-18 0.36 8.63e-18 5.12e-18 6.88e-18 0.36

Sr-89 9.69e-15 6.03e-14 3.50e-14 1.02 9.02e-15 5.61e-15 7.32e-15 0.33

Sr-90 3.26e-16 1.93e-16 2.60e-16 0.36 3.00e-16 1.78e-16 2.39e-16 0.36

Y-90 2.71e-14 1.71e-14 2.21e-14 0.32 2.52e-14 1.60e-14 2.06e-14 0.32

Y-91 1.07e-14 6.67e-15 8.69e-15 0.33 9.95e-15 6.20e-15 8.08e-15 0.33

Tc-99 2.42e-17 1.50e-17 1.96e-17 0.33 2.22e-17 1.37e-17 1.80e-17 0.33

Cs-135 1.50e-17 9.77e-18 1.24e-17 0.30 1.37e-17 8.93e-18 1.13e-17 0.30

Pm-147 3.06e-18 2.05e-18 2.56e-18 0.28 2.79e-18 1.87e-18 2.33e-18 0.28

Tm-170 1.84e-15 1.17e-15 1.51e-15 0.31 1.70e-15 1.08e-15 1.39e-15 0.32

W-185 8.79e-17 5.77e-17 7.28e-17 0.29 8.09e-17 5.30e-17 6.70e-17 0.29

Tl-204 9.06e-16 5.75e-16 7.41e-16 0.32 8.38e-16 5.32e-16 6.85e-16 0.32

Average 0.34 0.31

a

 Coefficient of variation
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-26

C.2.8.2 Slag Truck

Steel slag would also be transported by a tractor-trailer. A 20-t load of slag, with a density of

2 g/cm3

 (see Table C.1) has a volume of 10 m3. A dump trailer would be used to facilitate

unloading. The dimensions of the trailer are based on a Montone aluminum trailer that is 24 ft

long and 8 ft wide (7.3 × 2.4 m). The height of the load is calculated by dividing the volume of

the slag by the area of the trailer.

Both the trailer and the cab are made of aluminum, which has a density of 2.7 g/cm3

. The cab

has the same overall dimensions as the cab of the truck used to haul steel scrap, described in

Section C.2.8.1. However, the cab is made of c-in-thick (0.3175 cm) aluminum. The detailed

geometry specifications are shown in Table C.20. The height above ground of the two tally

points is centered on the height of the load.

The results of the analysis are presented in Table C.21. The dose rates from 11 of the 12

monoenergetic photon sources and 13 -emitting nuclides that partition to slag are computed by

MCNP at the two location specified in Table C.20. Because of the strong absorption of lowenergy photons by the walls of the cab, the dose rates from the 10 keV source are too low to be

statistically meaningful—this source is therefore not listed. Dose rates from the MCNPcalculated bremsstrahlung from very low-energy -emitting nuclides (i.e., Sm-151, Tm-171, Pu241, and Bk-249) are likewise very low—these nuclides are also not listed. The average of the

dose rates at the two tally points is adopted as the dose rate from each of the 11 photon sources

and 13 beta spectra in this exposure geometry. is calculated on the basis of all 24 sources. 

Based on these results, Ux for the driver of the slag truck is assigned a uniform distribution: 

0.7 # Ux # 1.3.

Table C.20 Slag truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -731.5 0.0 -121.9 121.9 137.2 193.0

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer

aluminum

floor 0.635 -731.5 0.0 -121.9 121.9 136.5 137.2

nose & taila 0.4826 -731.5 0.0 -121.9 121.9 137.2 259.1

sidesb 0.4064 -731.5 0.0 -121.9 121.9 137.2 259.1

Pavement—concrete 40.6 -40.6 0.0

Tally points (TP)

1 243.8

61.0 168.4

2 335.3

a

 x-min and x-max refer to tail and nose, respectively 

b

 y-min and y-max refer to right and left sides, respectively
Appendix C External Exposure Dose Coefficients

C-27 NUREG-1640

Table C.21 Dose rates to slag truck driver

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 3.19e-24 3.38e-24 3.29e-24 0.04 2.30e-23 1.81e-23 2.06e-23 0.17

0.020 1.62e-19 1.05e-19 1.34e-19 0.30 5.91e-20 3.84e-20 4.88e-20 0.30

0.030 1.10e-16 6.85e-17 8.93e-17 0.33 6.17e-17 3.83e-17 5.00e-17 0.33

0.050 4.37e-15 2.75e-15 3.56e-15 0.32 3.39e-15 2.12e-15 2.76e-15 0.33

0.070 1.88e-14 1.21e-14 1.55e-14 0.31 1.62e-14 1.03e-14 1.33e-14 0.31

0.100 6.12e-14 3.98e-14 5.05e-14 0.30 5.50e-14 3.57e-14 4.54e-14 0.30

0.200 2.81e-13 1.82e-13 2.32e-13 0.30 2.58e-13 1.67e-13 2.13e-13 0.30

0.500 9.47e-13 5.99e-13 7.73e-13 0.32 8.82e-13 5.58e-13 7.20e-13 0.32

1.0 2.00e-12 1.24e-12 1.62e-12 0.33 1.87e-12 1.16e-12 1.52e-12 0.33

2.0 4.03e-12 2.46e-12 3.25e-12 0.34 3.79e-12 2.31e-12 3.05e-12 0.34

5.0 9.48e-12 5.70e-12 7.59e-12 0.35 8.79e-12 5.29e-12 7.04e-12 0.35

P-32 6.12e-15 3.93e-15 5.03e-15 0.31 5.63e-15 3.61e-15 4.62e-15 0.31

S-35 2.97e-18 1.94e-18 2.46e-18 0.30 2.50e-18 1.63e-18 2.07e-18 0.30

Cl-36 7.72e-16 5.07e-16 6.40e-16 0.29 7.01e-16 4.60e-16 5.81e-16 0.29

Ca-45 1.99e-17 1.26e-17 1.63e-17 0.32 1.75e-17 1.10e-17 1.43e-17 0.32

Sr-89 4.92e-15 3.18e-15 4.05e-15 0.30 4.52e-15 2.91e-15 3.72e-15 0.31

Sr-90 2.79e-16 1.74e-16 2.27e-16 0.33 2.52e-16 1.57e-16 2.05e-16 0.33

Y-90 1.25e-14 8.15e-15 1.03e-14 0.30 1.15e-14 7.51e-15 9.51e-15 0.30

Y-91 5.25e-15 3.39e-15 4.32e-15 0.30 4.83e-15 3.12e-15 3.98e-15 0.30

Cs-135 2.85e-17 1.84e-17 2.35e-17 0.31 2.51e-17 1.61e-17 2.06e-17 0.31

Pm-147 9.45e-18 5.96e-18 7.71e-18 0.32 8.20e-18 5.17e-18 6.69e-18 0.32

Sm-151 2.94e-20 1.76e-20 2.35e-20 0.36 2.09e-20 1.25e-20 1.67e-20 0.36

Tm-170 1.15e-15 7.44e-16 9.47e-16 0.30 1.05e-15 6.78e-16 8.64e-16 0.30

Bk-249 5.75e-19 3.72e-19 4.74e-19 0.30 4.57e-19 2.95e-19 3.76e-19 0.30

Average 0.30 0.31

a

 Coefficient of variation

C.2.8.3 Dry Bulk Trailer

EAF baghouse dust is often transported in dry bulk trailers. These trailers, which typically have

two to four separate hoppers, are filled through hatches on top of each compartment and are

emptied by gravity through hatches on the bottom. The model adopted for the present analysis is

the Heil Trailer International Super Jet Model 1040 dry bulk trailer. Such a trailer was parked

under the baghouse at a steel mill during a visit by SC&A personnel. An overall schematic

diagram of this trailer is shown in Figure C.5, while Figure C.6 shows a cross-sectional view of

one hopper.

The cargo compartment consists of three hoppers, which are vertical, right circular cones. As

shown in Figure C.6, the cones are trimmed at their two internal intersections so that there is no

overlap. Each cone is also trimmed at its intersection with the barrel, which is a horizontal right
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-28

Figure C.6 Cross-section of Heil Dry Bulk Trailer (Yielding 2002)

circular cylinder. Each end hopper is also trimmed at its intersection with the end caps of the

cylindrical barrel. Each cone is truncated near the apex by the bottom hatch (Yielding 2002).

The detailed dimensions of the tractor-trailer combination are listed in Table C.22. The trailer is

assumed to contain 22 tons (20 t) of EAF dust. Based on the density of 1.72 g/cm3

, cited in

Section C.2.3, the dust occupies a volume of 11.6 m3. The level of the surface of the dust in the

trailer is calculated by an iterative process, based on the geometry.

C.2.8.3.1 Worker Atop Dust Truck

Two tally points are used in assessing doses to a worker standing on top of the trailer during the

transfer of dust from the baghouse. One location (TP 1 in Table C.22) is 2 feet (60.96 cm)

behind the center of the forward hatch, while the second (TP 2) is 2 feet behind the middle hatch. 

The dose rates from the 12 monoenergetic photon sources and 3 -emitting nuclides that

partition to the dust are listed in Table C.23. Because of the strong absorption of low-energy

photons by the walls of the trailer, the effective dose equivalent rate from the 10 keV source is

too low to be statistically meaningful and is therefore not listed. The coefficient of variation is

calculated in the conventional manner, based on the mean and standard deviation at each

location. The average of the dose rates at the two tally points is adopted as the dose rate from

each of the 11 photon sources and 3 beta spectra in this exposure geometry. is calculated on
Appendix C External Exposure Dose Coefficients

C-29 NUREG-1640

the basis of all sources. Based on these results, Ux for transferring EAF dust is assigned a

uniform distribution: 0.9 # Ux # 1.1. 

Table C.22 Dry bulk trailer exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -159.70 -1034.73 90.08 215.49

Cylindrical shella,b 0.476 -159.23 -1035.21 axis = 0.00 220.13 r = 116.21

Conesa

1

0.476 z axis:

-345.12 0.00

lower bounds = 90.08

2 -597.22 0.00

3 -849.31 0.00 apexc

 = 55.79 56.46

Truck caba,b 0.3175 153.04 363.86 -121.92 121.92 66.55 245.36

Pavement—concrete 40.64 -40.64 0.00

Tally points (TP)

1 -410.53 

0.00 436.65

2 -658.18 

3 213.36

60.96 147.32

4 304.80

a

 Aluminum

b

 Outer dimensions listed

c

 z-min and z-max refer to the apex of the outside and the inside of the cones, respectively

Table C.23 Dose rates to worker atop dust truck

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 — — — — 1.40e-33 1.35e-33 1.38e-33 0.026

0.015 7.82e-22 7.43e-22 7.63e-22 0.036 4.84e-22 4.41e-22 4.63e-22 0.066

0.020 3.26e-18 3.33e-18 3.30e-18 0.015 1.15e-18 1.17e-18 1.16e-18 0.012

0.030 6.88e-16 7.18e-16 7.03e-16 0.030 3.91e-16 4.08e-16 4.00e-16 0.030

0.050 1.69e-14 1.80e-14 1.75e-14 0.045 1.33e-14 1.42e-14 1.38e-14 0.046

0.070 6.56e-14 7.01e-14 6.79e-14 0.047 5.74e-14 6.13e-14 5.94e-14 0.046

0.100 2.21e-13 2.36e-13 2.29e-13 0.046 2.01e-13 2.15e-13 2.08e-13 0.048

0.200 1.29e-12 1.38e-12 1.34e-12 0.048 1.19e-12 1.28e-12 1.24e-12 0.052

0.500 5.58e-12 5.99e-12 5.79e-12 0.050 5.22e-12 5.60e-12 5.41e-12 0.050

1.0 1.33e-11 1.43e-11 1.38e-11 0.051 1.25e-11 1.34e-11 1.30e-11 0.049

2.0 2.85e-11 3.08e-11 2.97e-11 0.055 2.68e-11 2.89e-11 2.79e-11 0.053

5.0 6.67e-11 7.21e-11 6.94e-11 0.055 6.19e-11 6.69e-11 6.44e-11 0.055

Cl-36 4.56e-15 4.95e-15 4.76e-15 0.058 4.18e-15 4.55e-15 4.37e-15 0.060

Cs-135 1.56e-16 1.68e-16 1.62e-16 0.052 1.39e-16 1.49e-16 1.44e-16 0.049

Pb-210 8.02e-21 9.32e-21 8.67e-21 0.106 5.19e-21 6.28e-21 5.74e-21 0.134

Average 0.050 0.052

a

 Coefficient of variation
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-30

C.2.8.3.2 Dust in Dry Bulk Trailer

Two tally points are used in assessing doses to the driver hauling EAF dust in a dry bulk

trailer—TP 3 and TP 4 in Table C.22. Both place him in the driver’s seat at different distances

from the load. The height above ground is estimated from the truck depicted in Figure C.5. The

dose rates from 11 of the 12 monoenergetic photon sources and 2 -emitting nuclides that

partition to the dust are listed in Table C.24. Because of the strong absorption of low-energy

photons by the walls of the truck cab, the dose rates from the 10 keV source are too low to be

statistically meaningful and are therefore not listed. Dose rates from bremsstrahlung from

Pb-210, a very low-energy -emitting nuclide, are also too low to be statistically meaningful—

this nuclide is therefore not listed. The coefficient of variation is calculated in the conventional

manner, based on the mean and standard deviation at each location. Based on these results, Ux

for transporting EAF dust in a dry bulk trailer is assigned a uniform distribution: 0.8 # Ux # 1.2. 

Table C.24 Dose rates to driver hauling EAF dust in dry bulk trailer

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 3 TP 4 Mean Cv

a TP 3 TP 4 Mean Cva

0.015 4.64e-27 2.78e-27 3.71e-27 0.36 2.79e-27 1.70e-27 2.25e-27 0.34

0.020 4.80e-21 3.46e-21 4.13e-21 0.23 1.70e-21 1.23e-21 1.47e-21 0.23

0.030 1.57e-17 1.12e-17 1.35e-17 0.24 8.77e-18 6.24e-18 7.51e-18 0.24

0.050 1.08e-15 7.93e-16 9.37e-16 0.22 8.30e-16 6.11e-16 7.21e-16 0.21

0.070 5.47e-15 4.10e-15 4.79e-15 0.20 4.68e-15 3.50e-15 4.09e-15 0.20

0.100 2.08e-14 1.56e-14 1.82e-14 0.20 1.86e-14 1.40e-14 1.63e-14 0.20

0.200 1.21e-13 9.06e-14 1.06e-13 0.20 1.11e-13 8.31e-14 9.71e-14 0.20

0.500 4.61e-13 3.43e-13 4.02e-13 0.21 4.29e-13 3.20e-13 3.75e-13 0.21

1.0 1.01e-12 7.43e-13 8.77e-13 0.22 9.44e-13 6.96e-13 8.20e-13 0.21

2.0 2.06e-12 1.51e-12 1.79e-12 0.22 1.93e-12 1.42e-12 1.68e-12 0.22

5.0 4.75e-12 3.46e-12 4.11e-12 0.22 4.41e-12 3.21e-12 3.81e-12 0.22

Cl-36 4.18e-16 3.16e-16 3.67e-16 0.20 3.81e-16 2.88e-16 3.35e-16 0.20

Cs-135 1.50e-17 1.14e-17 1.32e-17 0.19 1.33e-17 1.01e-17 1.17e-17 0.19

Average 0.22 0.22

a

 Coefficient of variation

C.2.8.4 Dust in Dump Trailer

Another means of transporting EAF dust is by dump trailer. Such a trailer is described in

Section C.2.8.2, the only difference being the volume of the load, which is 11.6 m3

 (see Section

C.2.8.3.2). The height of the load is calculated by dividing the volume by the area of the trailer. 

The dimensions of the cab are based on the Kenworth Model T2000 (Kenworth 2001). The cab

is equipped with a sleeper berth, so the dose rates are calculated at four positions: two in the

driver’s seat and two in the sleeper. The two sets of positions span a range of distances between

the tractor and the load.
Appendix C External Exposure Dose Coefficients

C-31 NUREG-1640

Table C.25 Dump trailer hauling EAF dust: exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -811.8 -81.3 -121.5 121.5 137.2 202.5

Truck cab—aluminum 0.30 0.0 287.0 -106.7 106.7 127.0 391.2

Trailer

aluminum

floor 0.60 -811.8 -81.3 -121.9 121.9 136.5 137.2

nose & taila 0.48 -811.8 -81.3 -121.9 121.9 137.2 259.1

sidesb 0.40 -811.8 -81.3 -121.9 121.9 137.2 259.1

Pavement—concrete - 0.0

Tally points

driver’s seat

1 205.7

79.38 180.3

2 172.7

sleeper

3 95.3

0.00 203.2

4 114.3

a

 x-min and x-max refer to tail and nose, respectively 

b

 y-min and y-max refer to right and left sides, respectively

The results of the analysis are presented in Tables C.26 and C.27. The dose rates from 11 of the

12 monoenergetic photon sources and 13 -emitting nuclides that partition to slag are computed

by MCNP at the two location specified in Table C.25. Because of the strong absorption of lowenergy photons by the walls of the truck cab, the dose rates from the 10 keV source are too low

to be statistically meaningful and are therefore not listed. The average of the dose rates at the

two tally points is adopted as the dose rate from each of the 11 photon sources and 3 beta spectra

in this exposure geometry. is calculated on the basis of all 14 sources. Based on these

results, Ux is assigned a uniform distribution. In the driver’s seat, 0.88 # Ux # 1.12, while in the

sleeper, 0.91 # Ux # 1.09.

C.2.8.5 Truck With I-Beams

The truck used to transport I-beams, a representative steel product, consists of a tractor hauling a

flat-bed trailer. The cab is the same as that of the slag truck described in Section C.2.8.2. The

bed of the trailer is 40 ft long by 8 ft wide (12.19 m × 2.44 m), and is made of aluminum

honeycomb. The load consists of 22 I-beams, made of SAE 1020 steel. The dimensions of a

single I-beam, listed in Table C.28, are taken from a manufacturer’s on-line catalog (South St.

Paul Steel Supply Co. 2004). These dimensions are adjusted so that a simplified model, using a

rectilinear geometry, yields the weight of 50 lb/ft (74.41 kg/m) specified by the manufacturer.

The I-beams are furnished in lengths of 20 ft and 40 ft (6.56 and 13.12 m). The 40-ft length is

adopted for the present analysis. A schematic diagram showing an end view of the I-beams

arranged on the trailer is shown in Figure C.7. Each I-beam weighs 2,000 lb (907.2 kg). The

detailed geometry of the load is specified in Table C.29. The remaining details of the exposure

geometry are shown in Table C.30.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-32

Table C.26 Hauling EAF dust in dump trailer: dose rates in driver’s seat

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 6.94e-24 6.13e-24 6.54e-24 0.09 2.49e-23 2.43e-23 2.46e-23 0.02

0.020 9.24e-20 1.03e-19 9.77e-20 0.08 3.39e-20 3.77e-20 3.58e-20 0.08

0.030 5.20e-17 6.24e-17 5.72e-17 0.13 2.92e-17 3.51e-17 3.22e-17 0.13

0.050 2.12e-15 2.55e-15 2.34e-15 0.13 1.65e-15 1.98e-15 1.82e-15 0.13

0.070 9.78e-15 1.17e-14 1.07e-14 0.13 8.41e-15 1.01e-14 9.26e-15 0.13

0.100 3.61e-14 4.29e-14 3.95e-14 0.12 3.25e-14 3.87e-14 3.56e-14 0.12

0.200 2.09e-13 2.48e-13 2.29e-13 0.12 1.93e-13 2.28e-13 2.11e-13 0.12

0.500 8.05e-13 9.61e-13 8.83e-13 0.13 7.50e-13 8.95e-13 8.23e-13 0.13

1.0 1.74e-12 2.09e-12 1.92e-12 0.13 1.63e-12 1.95e-12 1.79e-12 0.13

2.0 3.52e-12 4.23e-12 3.88e-12 0.13 3.30e-12 3.98e-12 3.64e-12 0.13

5.0 8.01e-12 9.67e-12 8.84e-12 0.13 7.43e-12 8.98e-12 8.21e-12 0.13

Cl-36 7.43e-16 8.68e-16 8.06e-16 0.11 6.78e-16 7.92e-16 7.35e-16 0.11

Cs-135 2.34e-17 2.67e-17 2.51e-17 0.09 1.98e-17 2.36e-17 2.17e-17 0.12

Pb-210 8.22e-22 1.03e-21 9.26e-22 0.16 5.47e-22 6.84e-22 6.16e-22 0.16

Average 0.12 0.12

a

 Coefficient of variation

Table C.27 Hauling EAF dust in dump trailer: dose rates in sleeper berth

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 3 TP 4 Mean Cv

a TP 3 TP 4 Mean Cva

0.015 5.50e-24 7.08e-24 6.29e-24 0.18 3.36e-23 3.72e-23 3.54e-23 0.07

0.020 1.70e-19 1.63e-19 1.67e-19 0.03 6.24e-20 5.98e-20 6.11e-20 0.03

0.030 1.17e-16 1.03e-16 1.10e-16 0.09 6.59e-17 5.81e-17 6.20e-17 0.09

0.050 4.66e-15 4.06e-15 4.36e-15 0.10 3.64e-15 3.16e-15 3.40e-15 0.10

0.070 2.06e-14 1.80e-14 1.93e-14 0.10 1.78e-14 1.56e-14 1.67e-14 0.09

0.100 7.36e-14 6.46e-14 6.91e-14 0.09 6.65e-14 5.83e-14 6.24e-14 0.09

0.200 4.23e-13 3.71e-13 3.97e-13 0.09 3.90e-13 3.42e-13 3.66e-13 0.09

0.500 1.68e-12 1.46e-12 1.57e-12 0.10 1.56e-12 1.36e-12 1.46e-12 0.10

1.0 3.73e-12 3.23e-12 3.48e-12 0.10 3.50e-12 3.03e-12 3.27e-12 0.10

2.0 7.74e-12 6.67e-12 7.21e-12 0.11 7.27e-12 6.27e-12 6.77e-12 0.10

5.0 1.79e-11 1.54e-11 1.67e-11 0.11 1.66e-11 1.43e-11 1.55e-11 0.11

Cl-36 1.51e-15 1.33e-15 1.42e-15 0.09 1.38e-15 1.21e-15 1.30e-15 0.09

Cs-135 4.71e-17 4.13e-17 4.42e-17 0.09 4.20e-17 3.68e-17 3.94e-17 0.09

Pb-210 1.62e-21 1.41e-21 1.52e-21 0.10 1.08e-21 9.37e-22 1.01e-21 0.10

Average 0.09 0.09

a

 Coefficient of variation
Appendix C External Exposure Dose Coefficients

C-33 NUREG-1640

Figure C.7 Arrangement of I-beams (not to scale)

Table C.28 Dimensions of individual I-beam

Dimension Weight Effectivea Recalculated weightb

Symbol in cm lb/ft kg/m cm lb/ft kg/m

A 12.19 30.96 13.75c 20.46 30.96 14.02 20.86

B 0.37 0.94 0.96

C 8.08 20.52 35.24d 52.44 20.52 35.99 53.56

D 0.64 1.63 1.66

Total 48.99 72.91 50.00 74.41

Source: South St. Paul Steel Supply Co. 2004

a

 Adjusted to yield 50 lb/ft, as specified by manufacturer

b

 Calculated weight per unit length, based on effective dimensions

c

 Calculated weight per foot of web, based on listed dimensions

d

 Calculated weight per foot of two flanges, based on listed dimensions

Table C.29 I-beam geometry (cm)

Location

X

Y-center of beams

Z

Min Max Min Max

I-beams

1 – 6

-1219 0.0

-108.0 -86.4 -64.8 -43.2 -21.6 0.0

137.2 168.3

7 – 11 21.6 43.2 64.8 86.4 108.0 0.0

12 – 17 -108.0 -86.4 -64.8 -43.2 -21.6 0.0

168.3 199.4

18 – 22 21.6 43.2 64.8 86.4 108.0 0.0

Table C.30 Steel product truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer floor—aluminuma 3.175 -1219.2 0.0 -121.9 121.9 134.0 137.2

Pavement—concrete 40.64 -40.6 0.0

Tally points (TP)

1 243.8

61.0 168.4

2 335.3

a

 Floor is extruded aluminum honeycomb, estimated effective density = 1 g/cm3
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-34

The results of the analysis are presented in Table C.31. The dose rates from the 12

monoenergetic photon sources and 6 -emitting nuclides that partition to steel are computed by

MCNP at the two locations specified in Table C.30. Because of the strong absorption of lowenergy photons by the walls of the truck cab, the effective dose equivalent rates from the 10 keV

source are too low to be statistically meaningful and are therefore not listed. The average of the

dose rates at the two tally points is adopted as the dose rate from each of the sources. is

calculated on the basis of all the sources. Based on these results, Ux for the driver of the steel

truck is assigned a uniform distribution: 0.7 # Ux # 1.3.

Table C.31 Dose rates to truck driver hauling steel products

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 — — — — 6.46e-29 4.21e-29 5.34e-29 0.30

0.015 6.65e-21 4.17e-21 5.41e-21 0.32 4.01e-21 2.52e-21 3.27e-21 0.32

0.020 2.71e-18 1.63e-18 2.17e-18 0.35 9.55e-19 5.74e-19 7.65e-19 0.35

0.030 1.49e-16 8.96e-17 1.19e-16 0.35 8.41e-17 5.04e-17 6.73e-17 0.35

0.050 2.42e-15 1.49e-15 1.96e-15 0.34 1.89e-15 1.16e-15 1.53e-15 0.34

0.070 9.74e-15 6.23e-15 7.99e-15 0.31 8.40e-15 5.35e-15 6.88e-15 0.31

0.100 3.59e-14 2.33e-14 2.96e-14 0.30 3.23e-14 2.09e-14 2.66e-14 0.30

0.200 2.38e-13 1.55e-13 1.97e-13 0.30 2.19e-13 1.42e-13 1.81e-13 0.30

0.500 9.78e-13 6.20e-13 7.99e-13 0.32 9.12e-13 5.77e-13 7.45e-13 0.32

1.0 2.12e-12 1.32e-12 1.72e-12 0.33 1.99e-12 1.23e-12 1.61e-12 0.33

2.0 4.23e-12 2.59e-12 3.41e-12 0.34 3.98e-12 2.43e-12 3.21e-12 0.34

5.0 9.16e-12 5.52e-12 7.34e-12 0.35 8.50e-12 5.13e-12 6.82e-12 0.35

C-14 3.34e-18 2.61e-18 2.98e-18 0.17 2.83e-18 2.17e-18 2.50e-18 0.19

P-32 1.04e-14 6.79e-15 8.60e-15 0.30 9.58e-15 6.26e-15 7.92e-15 0.30

S-35 3.55e-18 2.19e-18 2.87e-18 0.34 2.97e-18 1.84e-18 2.41e-18 0.33

Tc-99 5.50e-17 3.56e-17 4.53e-17 0.30 4.90e-17 3.18e-17 4.04e-17 0.30

W-185 1.49e-16 9.70e-17 1.23e-16 0.30 1.35e-16 8.73e-17 1.11e-16 0.30

Tl-204 9.45e-16 5.94e-16 7.70e-16 0.32 8.64e-16 5.42e-16 7.03e-16 0.32

Average 0.31 0.32

a

 Coefficient of variation

C.2.9 Cement Basement

The cement basement is 24 ft × 24 ft (7.3 × 7.3 m) on the inside, with 8-ft (2.4-m) high walls. 

The floor and exterior walls are 8-in (20-cm) thick concrete; the radiation sources are uniformly

distributed throughout the concrete. The basement is divided into four rooms of equal size; the

interior walls are made of 1⁄2-inch-thick gypsum board, for a total effective thickness of 1 inch

(2.54 cm). The ceiling is also 1⁄2-inch (1.3 cm) gypsum board, above which is a 71⁄2-inch (19-cm)

air space and a 3⁄4-inch (1.9 cm) wood floor. The floor and outer walls are surrounded by soil. 

The details of the exposure geometry are presented in Table C.32. The dose rates are assessed at

two tally points. One is in the center of one of the rooms, while the other is nearer to the center
Appendix C External Exposure Dose Coefficients

C-35 NUREG-1640

of the basement, 1 m from each of the two interior walls. Since the person is surrounded by the

walls, the rotational geometry (ROT) is used in the MCNP analysis. 

Table C.32 Basement dweller exposure geometry (cm)

Location Thickness

X YZ

Min Max Min Max Min Max

Floor—concrete 20.3 -386.0 386.1 -386.0 386.1 -20.0 0.0

Exterior

walls—

concrete

1 20.3 -386.0 386.1 -386.0 -365.8 0.0 243.8

2 20.3 -386.0 -365.8 -386.0 386.1 0.0 243.8

3 20.3 -386.0 386.1 365.8 386.1 0.0 243.8

4 20.3 365.8 386.1 -386.0 386.1 0.0 243.8

Interior

wall—

gypsum

1 2.54 -365.8 365.8 -1.3 1.3 0.0 243.8

2 2.54 -1.3 1.3 -365.8 365.8 0.0 243.8

Ceiling gypsum 1.3 -365.8 365.8 -365.8 365.8 243.8 245.1

wood 1.9 -365.8 365.8 -365.8 365.8 259.1 261.0

Soil (outside) - 243.8

Tally points

1 100 100

100

2 166 166

The results of the analysis are presented in Table C.33, which lists the dose rates from the 12

monoenergetic photon sources and from the bremsstrahlung from the  decay of 14 selected

nuclides. These 14 nuclides are isotopes of elements that partition strongly to steel slag. The

average of the dose rates at the two tally points is adopted as the dose rate from each of the

sources. is calculated on the basis of all the sources. Based on these results, Ux for the

cement basement is assigned a uniform distribution: 0.9 # Ux # 1.1.

C.2.10 House with Steel Studs

The model for the house built with steel studs is a small single-story house that is similar to the

cement basement in size and construction. It measures 24 ft × 24 ft (7.3 × 7.3 m) with 8-ft (2.4-

m) high walls, and is divided into four rooms of equal size. The ceiling and the walls of each

room consist of 1⁄2-in (1.3-cm) gypsum board. The attic floor, consisting of 3⁄4-in (1.9-cm)

plywood, is 8 inches (20 cm) above the ceiling. The outside of the exterior walls is covered with

3⁄4-inch particle board (modeled as plywood). This stylized house resembles a garage that was

turned into living space. 

Both the interior and exterior walls are attached to a total of 109 studs made of SAE 1020 steel,

mounted on 16-inch (40-cm) centers. The studs are U-channels, 3.62 in (9.2 cm) across the base

and 1.62 in (4.12 cm) on the sides; the metal is 0.098 cm thick. The radiation sources are

uniformly distributed throughout the steel. A cross-sectional view of one stud is shown in Figure

C.8. A simplified floor plan of the house, showing the locations of the studs, is shown in

Figure C.9. 
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-36

Table C.33 Dose rates to cement basement dweller

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 1.53e-16 2.11e-16 1.82e-16 0.23 1.27e-16 1.76e-16 1.52e-16 0.23

0.015 2.55e-15 3.45e-15 3.00e-15 0.21 1.71e-15 2.32e-15 2.02e-15 0.21

0.020 1.14e-14 1.51e-14 1.33e-14 0.20 8.02e-15 1.06e-14 9.31e-15 0.20

0.030 6.58e-14 8.62e-14 7.60e-14 0.19 5.44e-14 7.13e-14 6.29e-14 0.19

0.050 4.77e-13 5.68e-13 5.23e-13 0.12 4.55e-13 5.42e-13 4.99e-13 0.12

0.070 1.38e-12 1.55e-12 1.47e-12 0.08 1.39e-12 1.56e-12 1.48e-12 0.08

0.100 3.33e-12 3.61e-12 3.47e-12 0.06 3.34e-12 3.62e-12 3.48e-12 0.06

0.200 1.09e-11 1.16e-11 1.13e-11 0.04 1.09e-11 1.16e-11 1.13e-11 0.04

0.500 3.39e-11 3.60e-11 3.50e-11 0.04 3.36e-11 3.57e-11 3.47e-11 0.04

1.0 7.22e-11 7.63e-11 7.43e-11 0.04 7.15e-11 7.56e-11 7.36e-11 0.04

2.0 1.45e-10 1.53e-10 1.49e-10 0.04 1.45e-10 1.53e-10 1.49e-10 0.04

5.0 3.36e-10 3.51e-10 3.44e-10 0.03 3.36e-10 3.51e-10 3.44e-10 0.03

P-32 1.77e-13 1.89e-13 1.83e-13 0.05 1.76e-13 1.88e-13 1.82e-13 0.05

S-35 1.61e-16 1.86e-16 1.74e-16 0.10 1.54e-16 1.77e-16 1.66e-16 0.10

Cl-36 2.30e-14 2.54e-14 2.42e-14 0.07 2.29e-14 2.53e-14 2.41e-14 0.07

Ca-45 8.70e-16 9.86e-16 9.28e-16 0.09 8.52e-16 9.62e-16 9.07e-16 0.09

Sr-89 1.34e-13 1.48e-13 1.41e-13 0.07 1.34e-13 1.47e-13 1.41e-13 0.07

Sr-90 9.46e-15 1.08e-14 1.01e-14 0.09 9.40e-15 1.07e-14 1.01e-14 0.09

Y-90 3.37e-13 3.78e-13 3.58e-13 0.08 3.35e-13 3.76e-13 3.56e-13 0.08

Y-91 1.49e-13 1.62e-13 1.56e-13 0.06 1.48e-13 1.62e-13 1.55e-13 0.06

Cs-135 1.18e-15 1.29e-15 1.24e-15 0.06 1.16e-15 1.27e-15 1.22e-15 0.06

Pm-147 4.28e-16 4.84e-16 4.56e-16 0.09 4.16e-16 4.69e-16 4.43e-16 0.08

Sm-151 4.91e-18 5.76e-18 5.34e-18 0.11 4.22e-18 4.77e-18 4.50e-18 0.09

Tm-171 1.36e-17 1.75e-17 1.56e-17 0.18 1.22e-17 1.54e-17 1.38e-17 0.16

W-185 3.65e-15 4.09e-15 3.87e-15 0.08 3.61e-15 4.05e-15 3.83e-15 0.08

Bk-249 4.17e-17 4.65e-17 4.41e-17 0.08 3.86e-17 4.27e-17 4.07e-17 0.07

Average 0.10 0.09

a

 Coefficient of variation

The details of the exposure geometry are presented in Table C.34. The dose rates are assessed at

two tally points. One is in the center of one of the rooms, while the other is nearer to the center

of the house, 1 m from each of the two interior walls. Since the studs surround each room, the

rotational geometry (ROT) is used in the MCNP analysis. 

The results of the analysis are presented in Table C.35, which lists the dose rates from the 12

monoenergetic photon sources and from the bremsstrahlung from the  decay of 6 selected

nuclides. These 6 nuclides are isotopes of elements that partition strongly to steel. The average

of the dose rates at the two tally points is adopted as the dose rate from each of the sources. 
Appendix C External Exposure Dose Coefficients

C-37 NUREG-1640

is calculated on the basis of all the sources. Based on these results, Ux for the home with steel

studs is assigned a uniform distribution: 0.9 # Ux # 1.1.

Table C.34 Steel-studded house exposure geometry (cm)

Location Thickness

X YZ

Min Max Min Max Min Max

Wall—gypsum 

1 1.3 -363.7 363.7 -361.2 -359.9 0.0 243.8

2 1.3 -361.2 -359.9 -363.7 363.7 0.0 243.8

3 1.3 -363.7 363.7 359.9 361.2 0.0 243.8

4 1.3 359.9 361.2 359.9 361.2 0.0 243.8

5 1.3 -363.7 363.7 -5.9 -4.6 0.0 243.8

6 1.3 -5.9 -4.6 -363.7 363.7 0.0 243.8

7 1.3 -363.7 363.7 5.9 4.6 0.0 243.8

8 1.3 5.9 4.6 -363.7 363.7 0.0 243.8

Ceiling gypsum 1.3 -370.4 -361.2 -370.4 -361.2 243.8 245.1

Attic floor—wood 1.9 -370.4 -361.2 -370.4 -361.2 265.4 267.3

Wall—wood

1 1.9 -372.3 372.3 -372.3 -370.4 0.0 267.3

2 1.9 -372.3 -370.4 -372.3 372.3 0.0 267.3

3 1.9 -372.3 372.3 370.4 372.3 0.0 267.3

4 1.9 370.4 372.3 -372.3 372.3 0.0 267.3

Concrete base slab 20.3 -372.3 372.3 -372.3 372.3 -20.3 0.0

Tally points (TP) 1 106 106 100

2 160 160

Figure C.8 Cross-section of steel stud

(thickness not to scale)

Figure C.9 Floor plan of steel-studded house
External Exposure Dose Coefficients Appendix C

11 Used to estimate overall distance between driver and engine. The lightweight insulating material is not included

in the MCNP calculation. 

NUREG-1640 C-38

Table C.35 Dose rates in steel-studded house

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 1.75e-31 1.65e-31 1.70e-31 0.04 1.46e-31 1.38e-31 1.42e-31 0.04

0.015 3.41e-21 3.59e-21 3.50e-21 0.04 2.29e-21 2.41e-21 2.35e-21 0.04

0.020 4.12e-18 4.28e-18 4.20e-18 0.03 2.90e-18 3.02e-18 2.96e-18 0.03

0.030 5.79e-16 5.48e-16 5.64e-16 0.04 4.79e-16 4.53e-16 4.66e-16 0.04

0.050 1.29e-14 1.13e-14 1.21e-14 0.09 1.23e-14 1.08e-14 1.16e-14 0.09

0.070 4.39e-14 3.75e-14 4.07e-14 0.11 4.47e-14 3.81e-14 4.14e-14 0.11

0.100 1.04e-13 8.75e-14 9.58e-14 0.12 1.04e-13 8.76e-14 9.58e-14 0.12

0.200 2.93e-13 2.44e-13 2.69e-13 0.13 2.93e-13 2.44e-13 2.69e-13 0.13

0.5 7.49e-13 6.13e-13 6.81e-13 0.14 7.41e-13 6.07e-13 6.74e-13 0.14

1.0 1.37e-12 1.12e-12 1.25e-12 0.14 1.36e-12 1.11e-12 1.24e-12 0.14

2.0 2.35e-12 1.91e-12 2.13e-12 0.15 2.35e-12 1.91e-12 2.13e-12 0.15

5.0 4.70e-12 3.72e-12 4.21e-12 0.16 4.70e-12 3.72e-12 4.21e-12 0.16

C-14 1.12e-17 9.95e-18 1.06e-17 0.08 1.09e-17 9.70e-18 1.03e-17 0.08

P-32 1.09e-14 9.21e-15 1.01e-14 0.12 1.09e-14 9.17e-15 1.00e-14 0.12

S-35 1.26e-17 1.06e-17 1.16e-17 0.12 1.24e-17 1.04e-17 1.14e-17 0.12

Tc-99 1.45e-16 1.22e-16 1.34e-16 0.12 1.44e-16 1.22e-16 1.33e-16 0.12

W-185 3.20e-16 2.72e-16 2.96e-16 0.11 3.19e-16 2.71e-16 2.95e-16 0.12

Tl-204 1.43e-15 1.22e-15 1.33e-15 0.11 1.42e-15 1.22e-15 1.32e-15 0.11

Average 0.10 0.10

a

 Coefficient of variation

C.2.11 Auto—Cast Iron Engine Block

The exposure geometry of an automobile with a cast iron engine block is based on a 2002 model

Chevrolet Impala sedan, a vehicle commonly used as a taxicab. The overall dimensions are

based on information presented by the General Motors Corp. (n/d). In this simplified model, the

cabin of the automobile is represented by a rectangular box made of 0.03-in (0.076-cm) sheet

metal. The top and sides of the hood are made of the same sheet metal—the front is open while

the back abuts the wall of the cabin. Underneath the engine is a c-in (0.32-cm) oil pan. The

sheet metal and oil pan are SAE 1020 steel.

The following detailed information on the dimensions and location of the engine block are based

on measurements by an SC&A staff member. These observations are illustrated in Figure C.10.

• The distance between the engine block and the firewall is approximately 8.5 in (21.6 cm). 

• The firewall is about 1.5 inches (3.8 cm) thick.11
Appendix C External Exposure Dose Coefficients

C-39 NUREG-1640

Figure C.10 Engine block exposure geometry

• The distance from the firewall to the center of the driver’s torso is approximately 39 inches

(99 cm) with the seat in the forward-most position and 43 inches (109 cm) with the seat in

the rear-most position. Total distance between the engine block and the driver, therefore,

ranges between approximately 49 and 53 inches (~125 – 135 cm).

The mass of the engine block is 163 lb (73.9

kg) (GMPartsDirect.com [n/d]). The

dimensions of the block, as shown in Figure

C.10 are 22 × 16 × 19 inches (56 × 40 × 48

cm). The effective density, = 0.688 g/cm3. 

The radiation sources are uniformly distributed

throughout the volume of the block.

The detailed geometry is presented in Table

C.36. The tally points for the MCNP analysis

correspond to the forward and rear positions of

the driver. Since the engine is in front of the

driver, the anteroposterior (AP) irradiation geometry is used in the analysis.

Table C.36 Engine block exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Block 102.0 142.0 -28.0 28 30.48 78.5

Hood 0.076 0.0 167.6 -91.4 91.44 15.24 91.44

Oil pan 0.32 101.6 142.2 -28.0 27.94 14.9225 15.24

Cabin 0.076 167.6 381.0 -91.4 91.44 15.24 142.24

Concrete  - 0

Tally points 1 226 35.6 55.9

2 236

The results of the analysis are presented in Table C.37, which lists the dose rates from the 12

monoenergetic photon sources and from the bremsstrahlung from the  decay of 6 selected

nuclides. These 6 nuclides are isotopes of elements that partition strongly to cast iron. The

average of the dose rates at the two tally points is adopted as the dose rate from each of the

sources. is calculated on the basis of all the sources. Based on these results, Ux for the driver

of an automobile with a cast iron engine block is assigned a uniform distribution: 0.9 # Ux # 1.1.

C.2.12 Diesel Truck

The diesel truck, like the automobile in the preceding section, has a cast iron engine block. The

dimensions of this truck are partially based on the Kenworth Model T2000 (Kenworth 2001). 

The truck is equipped with a sleeper berth, as are most operator-owned highway trucks used for

long-distance hauls. Detailed mechanical specifications for the Model T2000 were not readily
External Exposure Dose Coefficients Appendix C

12 The Golden Casting Corporation is now in bankruptcy. An auction of its gray iron casting facility in Columbus,

IN was held on May 4, 2004.

13 Mike Kell, Cummins, Inc., private communication with Kathleen Behling, SC&A, Inc., March 27, 2002.

NUREG-1640 C-40

available. Specifications for a comparable truck, the Peterbilt Model 362, are used to construct

the model in the present analysis (Peterbilt and Kenworth are both divisions of PACCAR, Inc.) 

At the time of this analysis, one of Peterbilt’s engine suppliers was Cummins, Inc., which in turn

obtained engine blocks from Golden Casting.12 Golden Casting made 12 L to 15 L engine

blocks, the heaviest of which weighed 800 lb (362.9 kg) (Brezonick 1999). The Cummins

Signature (15 L) engine block is 41 inches long, 21.75 inches wide, and 30 inches high (104.1 ×

55.25 × 76.2 cm).13 Such a block has an effective density of 0.8277 g/cm3.

Table C.37 Dose rates to driver of automobile with cast iron engine block

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 1.28e-33 1.28e-33 1.28e-33 0.00 1.64e-33 1.63e-33 1.64e-33 0.00

0.015 2.69e-32 2.67e-32 2.68e-32 0.01 3.39e-32 3.36e-32 3.38e-32 0.01

0.020 2.39e-23 2.25e-23 2.32e-23 0.04 2.77e-23 2.61e-23 2.69e-23 0.04

0.030 6.30e-18 5.59e-18 5.95e-18 0.08 6.91e-18 6.13e-18 6.52e-18 0.08

0.050 1.62e-15 1.38e-15 1.50e-15 0.11 1.74e-15 1.48e-15 1.61e-15 0.11

0.070 1.01e-14 8.51e-15 9.31e-15 0.12 1.03e-14 8.71e-15 9.51e-15 0.12

0.100 4.05e-14 3.44e-14 3.75e-14 0.12 4.17e-14 3.54e-14 3.86e-14 0.12

0.200 2.50e-13 2.13e-13 2.32e-13 0.11 2.57e-13 2.19e-13 2.38e-13 0.11

0.500 8.65e-13 7.38e-13 8.02e-13 0.11 8.92e-13 7.61e-13 8.27e-13 0.11

1.0 1.67e-12 1.42e-12 1.55e-12 0.11 1.71e-12 1.46e-12 1.59e-12 0.11

2.0 2.93e-12 2.49e-12 2.71e-12 0.12 2.99e-12 2.54e-12 2.77e-12 0.12

5.0 5.63e-12 4.79e-12 5.21e-12 0.11 5.86e-12 4.97e-12 5.42e-12 0.12

C-14 3.17e-18 2.68e-18 2.93e-18 0.12 3.29e-18 2.79e-18 3.04e-18 0.12

P-32 1.02e-14 8.67e-15 9.44e-15 0.12 1.05e-14 8.94e-15 9.72e-15 0.11

S-35 3.33e-18 2.82e-18 3.08e-18 0.12 3.46e-18 2.93e-18 3.20e-18 0.12

Tc-99 3.48e-17 2.96e-17 3.22e-17 0.11 3.60e-17 3.05e-17 3.33e-17 0.12

W-185 1.55e-16 1.32e-16 1.44e-16 0.11 1.60e-16 1.36e-16 1.48e-16 0.12

Tl-204 1.02e-15 8.69e-16 9.45e-16 0.11 1.05e-15 8.96e-16 9.73e-16 0.11

Average 0.10 0.10

a

 Coefficient of variation

The truck in the present analysis has an aluminum cab and a hood made of a fiberglass-resin

composite (composites and aluminum are used in the Peterbilt Model 387). The radiator grille is

aluminum with an assumed effective thickness of c inch (0.32 cm). The oil pan is c-inch-thick

SAE 1020 steel.
Appendix C External Exposure Dose Coefficients

C-41 NUREG-1640

Dose rates are calculated for a total of four positions. Two (TP 1 and 2) correspond to the driver

position in the driver’s seat, at the closest and furthest distance from the engine, while the other

two (TP 3 and 4) are for the corresponding positions in the sleeper. Since the driver faces the

engine while driving, the dose calculations for the driver’s seat utilize the anteroposterior (AP)

irradiation geometry. The driver’s orientation in the sleeper berth corresponds to the rotational

(ROT) geometry. 

Table C.38 Diesel truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Engine block 312.7 368.0 -52.1 52.1 45.7 121.9

Truck cab—aluminum 0.32 0.0 287.0 -106.7 106.7 127.0 391.2

Hood—composite 0.318 287.0 467.4 -76.2 76.2 31.8 200.7

Radiator grille—aluminum 0.318 467.0 467.4 -76.2 76.2 31.8 200.7

Oil pan—SAE 1020 steel 0.318 312.7 368.0 -52.1 52.1 45.4 45.7

Pavement—concrete 40.6 -40.6 0.0

Tally points (TP)

1 205.7

79.38 180.3

2 172.7

3 95.3

0.00 203.2

4 114.3

Note: All dimensions are external

The results of the analysis for the driver’s seat are presented in Table C.39, while the

corresponding analysis for the sleeper is shown in Table C.40. The structure of these tables is

similar to that of Table C.37, which is discussed in the previous section. Based on the present

results, Ux for the driver’s seat is assigned a uniform distribution: 0.8 # Ux # 1.2, while for the

sleeper berth, 0.9 # Ux # 1.1.

C.2.13 Hull Plate

The exposure to a steel hull plate on a ship is based on the model described by Anigstein et. al

(2001, Appendix H2). The plate is 20 ft wide, 10 ft high, and d inch thick (6.1 m × 3.05 m

× 0.95 cm). The exposed individual is in a compartment that is 7.5 ft high, and 20 × 20 ft square

(2.29 × 6.1 × 6.1 m). The other five sides are 1⁄4 inch (0.63 cm) thick. The compartment is

centered on the hull plate. The hull and the sides of the compartment (bulkheads and decks) are

made of SAE 1020 steel. Radioactive sources are uniformly distributed throughout the steel hull

plate—the rest of the compartment is not made from cleared material. In assessments of sources

with energies # 0.1 MeV, the compartment is filled with moist air. This simple model ignores

scattering of radiation from the rest of the ship and from the environment outside the hull.

Three tally points—corresponding to a sailor sleeping on a bunk next to the hull—are centered

on the plate at distances of 18, 24, and 30 inches (46, 61, and 76 cm). Another tally location,

corresponding to a lounge area, is in the center of the compartment, 1 m above the floor. Since
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-42

the sailor’s orientation to the hull plate would vary, rotational (ROT) geometry is utilized in the

dose calculations.

Table C.39 Dose rates in driver’s seat of truck with cast iron diesel engine block

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 1.21e-29 2.15e-29 1.68e-29 0.40 9.43e-30 1.68e-29 1.31e-29 0.40

0.015 1.08e-20 8.75e-21 9.78e-21 0.15 8.59e-21 6.97e-21 7.78e-21 0.15

0.020 4.91e-18 3.12e-18 4.02e-18 0.32 4.23e-18 2.69e-18 3.46e-18 0.32

0.030 3.26e-16 2.22e-16 2.74e-16 0.27 2.97e-16 2.02e-16 2.50e-16 0.27

0.050 4.50e-15 3.37e-15 3.94e-15 0.20 4.18e-15 3.13e-15 3.66e-15 0.20

0.070 1.56e-14 1.20e-14 1.38e-14 0.18 1.52e-14 1.16e-14 1.34e-14 0.19

0.100 5.02e-14 3.91e-14 4.47e-14 0.18 4.87e-14 3.79e-14 4.33e-14 0.18

0.200 2.82e-13 2.22e-13 2.52e-13 0.17 2.75e-13 2.16e-13 2.46e-13 0.17

0.500 1.07e-12 8.44e-13 9.57e-13 0.17 1.04e-12 8.19e-13 9.30e-13 0.17

1.0 2.23e-12 1.74e-12 1.99e-12 0.18 2.17e-12 1.70e-12 1.94e-12 0.17

2.0 4.15e-12 3.24e-12 3.70e-12 0.17 4.05e-12 3.16e-12 3.61e-12 0.18

5.0 8.47e-12 6.59e-12 7.53e-12 0.18 8.14e-12 6.34e-12 7.24e-12 0.18

C-14 5.17e-18 3.96e-18 4.57e-18 0.19 4.93e-18 3.78e-18 4.36e-18 0.19

P-32 1.13e-14 8.97e-15 1.01e-14 0.16 1.09e-14 8.70e-15 9.80e-15 0.16

S-35 5.60e-18 4.20e-18 4.90e-18 0.20 5.34e-18 4.00e-18 4.67e-18 0.20

Tc-99 7.19e-17 5.57e-17 6.38e-17 0.18 6.94e-17 5.38e-17 6.16e-17 0.18

W-185 1.81e-16 1.43e-16 1.62e-16 0.17 1.75e-16 1.38e-16 1.57e-16 0.17

Tl-204 1.15e-15 9.08e-16 1.03e-15 0.17 1.12e-15 8.80e-16 1.00e-15 0.17

Average 0.20 0.20

a

 Coefficient of variation

The results of the analysis are presented in Tables C.41 and C.42. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the three locations corresponding to

the sailor in the bunk, as well as in the lounge area. The average of the dose rates at the three

tally points is adopted as the dose rate in the bunk from each of the 12 photon sources. for

this location is calculated on the basis of all 12 sources. Based on these results, Ux for the sailor

in the bunk is assigned a uniform distribution: 0.87 # Ux # 1.13. Ux for the center location is

assigned the fixed value, Ux = 1.

The bremsstrahlung from the six -emitting nuclides listed in Table C.42 is calculated only at the

middle position in the bunk and in the lounge area. These six nuclides are isotopes of elements

that partition strongly to the steel. 

C.2.14 Steel Ship

The AOE-6 fast combat support ship, illustrated in Figure C.11, serves as the basis for the steel

ship model. Although far more complex and sophisticated than the simple model employed in
Appendix C External Exposure Dose Coefficients

C-43 NUREG-1640

Figure C.11 AOE-6 class fast combat support ship (starboard view)

the assessment of a single hull plate, described in Section C.2.13, the model employed in the

present analysis is still a vast simplification of the actual ship. Figure C.12 illustrates the

simplified model used in the present analysis.

Table C.40 Dose rates in sleeper berth of truck with cast iron diesel engine block

Energy (MeV)

or nuclide

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 2.19e-29 2.14e-29 2.17e-29 0.02 1.83e-29 1.79e-29 1.81e-29 0.02

0.015 3.57e-21 4.24e-21 3.91e-21 0.12 2.40e-21 2.85e-21 2.63e-21 0.12

0.020 8.89e-19 1.14e-18 1.01e-18 0.18 6.27e-19 8.02e-19 7.15e-19 0.17

0.030 6.36e-17 7.86e-17 7.11e-17 0.15 5.26e-17 6.50e-17 5.88e-17 0.15

0.050 1.15e-15 1.34e-15 1.25e-15 0.11 1.10e-15 1.28e-15 1.19e-15 0.11

0.070 4.46e-15 5.13e-15 4.80e-15 0.10 4.54e-15 5.23e-15 4.89e-15 0.10

0.100 1.57e-14 1.79e-14 1.68e-14 0.09 1.57e-14 1.79e-14 1.68e-14 0.09

0.200 9.52e-14 1.08e-13 1.02e-13 0.09 9.52e-14 1.08e-13 1.02e-13 0.09

0.500 3.88e-13 4.41e-13 4.15e-13 0.09 3.85e-13 4.37e-13 4.11e-13 0.09

1.0 8.42e-13 9.57e-13 9.00e-13 0.09 8.34e-13 9.48e-13 8.91e-13 0.09

2.0 1.63e-12 1.86e-12 1.75e-12 0.09 1.63e-12 1.86e-12 1.75e-12 0.09

5.0 3.44e-12 3.91e-12 3.68e-12 0.09 3.44e-12 3.91e-12 3.68e-12 0.09

C-14 1.44e-18 1.67e-18 1.56e-18 0.11 1.42e-18 1.64e-18 1.53e-18 0.10

P-32 3.99e-15 4.54e-15 4.27e-15 0.09 3.97e-15 4.52e-15 4.25e-15 0.09

S-35 1.51e-18 1.75e-18 1.63e-18 0.10 1.49e-18 1.72e-18 1.61e-18 0.10

Tc-99 2.23e-17 2.55e-17 2.39e-17 0.09 2.22e-17 2.54e-17 2.38e-17 0.10

W-185 5.81e-17 6.62e-17 6.22e-17 0.09 5.80e-17 6.61e-17 6.21e-17 0.09

Tl-204 3.83e-16 4.36e-16 4.10e-16 0.09 3.82e-16 4.35e-16 4.09e-16 0.09

Average 0.10 0.10

a

 Coefficient of variation

C.2.14.1 General Description

A general description of the AOE-6 class ship is provided in this section. Not all of the features

discussed below are included in the model.

• The main propulsion system (LM2500 gas turbines) is housed in two engine rooms, which

are located directly below the fore and aft gas turbine exhaust stacks. 
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-44

Table C.41 Dose rates from steel hull plate

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

41 cm 61 cm 76 cm Mean Cv

a Center 41 cm 61 cm 76 cm Mean Cva Center

0.010 4.74e-17 3.65e-17 2.88e-17 3.76e-17 0.25 1.86e-18 3.96e-17 3.05e-17 2.40e-17 3.14e-17 0.25 1.56e-18

0.015 4.13e-16 3.58e-16 3.13e-16 3.61e-16 0.14 5.67e-17 2.79e-16 2.41e-16 2.11e-16 2.44e-16 0.14 3.81e-17

0.020 1.55e-15 1.38e-15 1.22e-15 1.38e-15 0.12 2.77e-16 1.10e-15 9.71e-16 8.62e-16 9.78e-16 0.12 1.96e-16

0.030 7.95e-15 7.10e-15 6.35e-15 7.13e-15 0.11 1.61e-15 6.59e-15 5.89e-15 5.26e-15 5.91e-15 0.11 1.33e-15

0.050 4.87e-14 4.37e-14 3.92e-14 4.39e-14 0.11 1.03e-14 4.68e-14 4.20e-14 3.77e-14 4.22e-14 0.11 9.89e-15

0.070 1.54e-13 1.39e-13 1.25e-13 1.39e-13 0.10 3.33e-14 1.58e-13 1.42e-13 1.28e-13 1.43e-13 0.11 3.41e-14

0.100 5.02e-13 4.52e-13 4.07e-13 4.54e-13 0.10 1.08e-13 5.02e-13 4.52e-13 4.07e-13 4.54e-13 0.10 1.08e-13

0.200 2.56e-12 2.29e-12 2.05e-12 2.30e-12 0.11 5.27e-13 2.56e-12 2.29e-12 2.05e-12 2.30e-12 0.11 5.27e-13

0.500 8.88e-12 7.86e-12 6.96e-12 7.90e-12 0.12 1.67e-12 8.78e-12 7.77e-12 6.88e-12 7.81e-12 0.12 1.66e-12

1.0 1.80e-11 1.57e-11 1.38e-11 1.58e-11 0.13 3.14e-12 1.78e-11 1.56e-11 1.37e-11 1.57e-11 0.13 3.11e-12

2.0 3.30e-11 2.85e-11 2.48e-11 2.88e-11 0.14 5.43e-12 3.30e-11 2.86e-11 2.48e-11 2.88e-11 0.14 5.44e-12

5.0 6.69e-11 5.74e-11 4.96e-11 5.80e-11 0.15 1.07e-11 6.69e-11 5.73e-11 4.96e-11 5.79e-11 0.15 1.06e-11

Average 0.13 0.13

a

 Coefficient of variation

Table C.42 Dose rates from $ bremsstrahlung from steel hull plate

Nuclide Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

Bunk (61 cm) Lounge (center) Bunk (61 cm) Lounge (center)

C-14 6.01e-17 1.29e-17 5.80e-17 1.24e-17

P-32 9.40e-14 2.06e-14 9.35e-14 2.05e-14

S-35 5.81e-17 1.39e-17 5.62e-17 1.35e-17

Tc-99 6.82e-16 1.61e-16 6.76e-16 1.60e-16

W-185 1.69e-15 3.95e-16 1.69e-15 3.92e-16

Tl-204 1.02e-14 2.34e-15 1.02e-14 2.35e-15

• Additional engineering spaces and some auxiliary spaces are located forward and aft of the

engine rooms. 

• The areas forward of the engineering spaces, and below the main deck, are dedicated

primarily to combat stores.

• Crew berthing is located in the forward superstructure and in the uppermost deck area below

the forward superstructure.

• The aft superstructure, aft of the exhaust stacks, houses the ship’s three helicopters.

• Ship operations, communications, and other command and control functions are directed

from watch stations in the forward superstructure, above the berthing compartments.

• The ship, below the main deck, may be modeled as a series of similarly-structured (generic)

compartments. Specific compartments will vary in some structural details.
Appendix C External Exposure Dose Coefficients

C-45 NUREG-1640 Figure C.12 Schematic diagrams of ship model
External Exposure Dose Coefficients Appendix C

14 General information related to compartment size and ship construction details provided by U.S. Navy personnel

from Naval Warfare Support Center (NWSC) Carderock Division (hereafter Carderock) during a meeting with NRC and

SC&A staff, January 30, 2003.

15 NWSC Carderock Division personnel, private communications with John Harrop, SC&A, Inc., February 14 and

February 25, 2003.

NUREG-1640 C-46

Each generic compartment extends across the beam (107 ft [32.6 m] at the waterline) of the ship,

and is 50 ft [15 m] long. The compartment height from keel to main deck is 70 ft (21 m). The

ship comprises six such compartments. One large compartment is devoted to cargo fuel oil

storage, and is 200 ft (61 m) long. Two compartments house the engine rooms—each is 75 ft

(23 m) long. Additional compartments forward and aft have smaller dimensions as the ship’s

beam tapers.14 Each compartment contains a number of decks below the main deck. Nominal

deck-to-overhead height is 10 feet (3.05 m). Spaces below the bottom (fourth) deck are usually

filled with propulsion fuel for the ship, lubricating and hydraulic fluids, potable water, sanitary

tanks, and other fluids, and to an inner-bottom void.

C.2.14.2 Compartment Densities

Specific compartments can be characterized in terms of the density of materials (specific gravity)

and components (“objects”) contained therein, as follows:15

• Berthing and superstructure watch station areas: 95% air, 5% objects. The objects (bunks,

lockers, desks, chairs, and tables) comprise 50% aluminum and 20% steel by weight. The

remaining 30% of objects (linens, clothes, insulation) have a specific gravity of 1.5.

• Shops, pump rooms, steerage: 90% air, 10% objects. The objects comprise 90% steel and

10% aluminum by weight.

• Auxiliary, engine room, and forward and aft compartments: 85% air, 15% objects. The

objects comprise 90% steel and 10% aluminum by weight. 

• The area of the aft superstructure through which the gas exhaust stacks pass contains a gas

exhaust stack, which is steel, about c inch (0.3 cm) thick. The remaining part of the aft

superstructure forward of the hangar is 90% air, 10% objects; the objects are 80% steel, 10%

aluminum, and 10% miscellaneous, including nylon ropes, wood, lubricants. 

• Dry-refrigerated storage: 85% air, 15% objects. The objects have a specific gravity of 1.5. 

The objects are primarily food and associated packaging, which is typically aluminum, steel

and cardboard containers.

• Cargo storage: 60% air, 40% objects. The objects comprise 95% steel and 5% packing (e.g.,

wood) by weight.
Appendix C External Exposure Dose Coefficients

C-47 NUREG-1640

• Ammunition storage: 85% air, 15% objects. The objects comprise 50% steel and 50%

explosives, by weight. The explosives are high energy PBX.

• Fuel oil storage: 100% fuel oil (average specific gravity = .72). 

C.2.14.3 Specific Compartment Descriptions

This section provides more specific descriptions of the dimensions and contents of the various

compartments than is presented in the preceding sections. 

C.2.14.3.1 Forward Compartment

A forward compartment at the ship’s bow contains the anchor, anchor motor, shot locker, and

various voids. The compartment is 25 ft (7.6 m) long and is tapered. The compartment is

accessible, but normally is not manned at sea or in port.

C.2.14.3.2 Fuel Oil Storage Compartment

Fuel storage can accommodate various types of fuel oil as cargo. One compartment is structured

as fuel tanks to accommodate this fuel oil, as well as fuel oil for the ship. Located one deck

below the main deck is a crew’s berthing area. The berthing area comprises the same mix of

materials as present in other crew’s berthing areas, described below. 

The fuel oil storage compartment is 40 ft deep, 100 ft wide, and 200 ft long (12 × 30.5 × 61 m). 

The compartment contains one deck below the crew’s berthing area that is devoted to various

pumps and piping systems needed to transfer the fuel oil to the ship’s propulsion system, or to

the underway replenishment system (for cargo fuel oil). Located on a deck above the fuel oil

tanks is a fuel oil transfer station, which contains pumps, motors, valves, and piping to transfer

oil from the fuel oil tanks to other ships during underway replenishment. The fuel oil transfer

station is manned during underway replenishment operations and fuel loading operations. 

Otherwise, the compartment is unmanned.

C.2.14.3.3 Large Cargo

One large cargo compartment, structured as an open hold, is dedicated to storage of large

components, such as vehicles, turbines, and the like. The compartment is accessible, but is not

normally manned. 

C.2.14.3.4 Ammunition

An ammunition compartment is located forward of the forward-most dry-refrigerated storage

compartment, and is structured as an open hold. Ammunition ranges from missiles (air-to-air;

surface-to-air), to 5-inch (127-mm) and smaller projectiles, to small arms ammunition. The gun

munitions are generally densely packed, while missile storage is much less dense. The

ammunition compartment is manned during some underway replenishment operations and during
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-48

ship loading operations (in port–at sea). This compartment is filled to within 10 – 15 feet

(~3 – 5 m) of the top. 

The "open holds" are filled from the bottom up, but are usually fairly full—the materials in these

holds will be boxed, palletized, or otherwise packaged, with the result that most of the space will

be filled. Furthermore, the different "packages" will be separated by some amount of space to

allow personnel to work around the shipping containers (the containers are lashed to the

bulkheads or other structural members so they don't flop around when the ship pitches, rolls, and

yaws). To allow access and facilitate unloading, both the ammunition and large cargo

compartments are typically filled to within 10 – 15 feet of the top.

C.2.14.3.5 Dry-Refrigerated Storage

One dry-refrigerated storage compartment is located forward and aft of the engineering spaces. 

The dry-refrigerated storage compartment contains 500 tons (~450 t) of cargo dry stores, 250

tons (~225 t) of cargo refrigerated stores, and approximately 1,350 tons (1,225 t) of other stores

for use by the ship’s crew. This compartment includes three decks. The compartment is manned

during underway replenishment, and during ship loading operations (in port), and is toured

periodically (e.g., hourly for 15 minutes) in port and at sea. 

C.2.14.3.6 Engine Rooms

Two compartments, starting aft of an auxiliary compartment, are structured as engine rooms

(ER1 and ER2 in Figure C.12). Each engine room includes two LM2500 propulsion modules,

electrical generating components, and various other auxiliary components. The engine rooms

include a deck at the second deck level. The LM2500 modules are mounted on a third deck

approximately 30 feet (9.1 m) below the second deck level. The volume below the third deck is

not normally accessible to the crew, and houses various tanks and voids. The engine rooms are

manned at sea and in port. At sea, most of the engine room watchstanders are in an enclosed

operating space located at the aft bulkhead of the engine room. Some watchstanders will

periodically tour through the engine room to check operation of the gas turbines and other engine

room systems.

C.2.14.3.7 Auxiliary Rooms

Two compartments are structured as auxiliary rooms. One (AMR1—see Figure C.12) is located

forward of the forward engine room (ER1) and one (AMR2) is located aft of the aft engine room

(ER2). These compartments contain various engineering system components such as lubricating

oil pumps and sumps, hydraulic oil pumps, accumulators and tanks, evaporators, seawater

cooling systems, fire fighting pumps, air compressors, and other engineering components and

systems. Each of these two compartments contains three decks, separated by about 10 feet

(~3 m). Below the third deck is a system of tanks and other inner-bottom spaces not normally

accessible to the crew. The auxiliary rooms are manned at sea.
Appendix C External Exposure Dose Coefficients

C-49 NUREG-1640

C.2.14.3.8 Aft Compartment

One aft compartment, 75 feet (23 m) long, tapers toward the stern. The aft compartment has a

specific density of 10%, comprising steel objects (e.g., shafts, rudder stock, steering gear). The

aft compartment is toured periodically, and for a limited time, by a single watchstander.

C.2.14.3.9 Superstructure Compartments

The ship comprises a forward and an aft superstructure. The aft superstructure accommodates

the gas turbine exhaust and the ship’s helicopters. The forward superstructure accommodates

most of the ship’s command and control operations, and crew berthing and messing facilities.

Exterior bulkheads of the superstructure are formed from thin steel plate (d inch [9.5 mm]). 

Interior bulkheads that serve to separate living spaces and working spaces are formed from thin

aluminum sheet (typically inch [1.6 mm]), reinforced with steel supports. The bulkheads are

insulated.

Aft Superstructure

The aft superstructure includes a hangar to house three Sea Knight helicopters, and shops to

repair the helicopters. The hanger and shops are aft of the gas turbine exhausts. This area of the

ship is approximately 75 ft long, 40 ft high, and 87 ft wide (23 × 12 × 26.5 m), and is normally

manned while the ship is underway.

Forward Superstructure

The forward superstructure includes two decks of berthing (O-1 and O-2) for the officers, chief

petty officers, and more senior petty officers (other crew berthing is provided below the main

deck, above the fuel oil storage area). The O-4 level is 87 ft wide by 90 ft long (26.5 m ×

27.4 m). O-3 is the same size. The O-5 level is slightly narrower (67 ft [20.4 m]), but has two

"wings" at its forward end. The O-1 and O-2 levels are 87 ft wide and 125 ft long (26.5 ×

38.1 m). 

The O-1 and O-2 decks also accommodate messing facilities for the petty officers and other

enlisted personnel, and a wardroom for the officers. The O-3 – O-5 decks of the forward

superstructure house the ship’s command and control stations (e.g., navigation, steering, radar,

sonar, combat control [only for commissioned ships]), and are continuously manned at sea. The

spaces are manned with a reduced crew while the ship is in port or at anchor.

C.2.14.4 Exposure Geometry

The cross-sectional view in Figure C.12 shows the modified outline of the hull. The vertical

profile is modeled as a rectangle. The coordinate system used in the model has its origin at the

bottom surface of the deck forming the bottom of the main berthing area. The x-axis is parallel
External Exposure Dose Coefficients Appendix C

16 The use of a volume detector greatly increases the computational efficiency of MCNP, which is highly desirable

in this case, given the complexity of the model.

17 The actual MCNP analysis utilized a very thin volume detector for these two tallies.

NUREG-1640 C-50

to the midline of the ship, as shown in the plan view. The z-axis is in the plane forming the aft

surface of the transverse bulkhead marked T4 in the cross-sectional view.

The transverse bulkheads (running port to starboard) are marked T1 – T10. T4 marks the

location of two bulkheads: T41 is below decks, while T42 is part of the forward superstructure. 

The decks in the forward superstructure are numbered according to the compartment above that

deck: e.g., deck O2 is between the compartments marked O1 and O2. Deck O6 forms the top of

the superstructure. Lateral bulkheads, marked L1 – L4 in the plan view in Figure C.12, run fore

and aft. L1 marks the position of two bulkheads: L11, which forms the port side of

compartments O1 and O2, and L12, which forms the port side of compartments O3 – O5. 

Similarly, L2 shows the location of bulkheads L21 and L22, which form the starboard sides of

the same compartments. The detailed geometry specifications are listed in Tables C.43 and

C.44.

The radiation sources are uniformly distributed throughout the steel structures of the ship, which

comprise the hull, the decks, and the bulkheads. Dose rates are calculated at four locations: (1)

the berthing compartment; (2) the O1 compartment, which includes the mess and lounge areas;

(3) the O4 compartment, which is part of the operations area; and (4) the area of the main deck

occupied by the UNREP watchstander, marked “WS 2" in Figure C.12. In the first two

locations, the crew members would occupy various locations throughout a given volume within

the compartment. For instance, in the berthing compartment, the bunks are triple-decked, so an

individual can be at various heights above the deck, depending on which bunk he occupies,

whether he is lying, sitting, or standing, etc. Similarly, in the mess and lounge area, the

individual could be sitting, standing, or reclining. For these areas, the analysis employs a

“volume detector”—i.e., the dose rates are integrated over the occupied volume of each

compartment, as specified in Table C.44.16 In the other two locations, the individual is assumed

to be standing, so the doses are calculated at a height of 1 m above the deck, but integrated over

the entire occupied area. Therefore, the tally is specified as an “area detector.”17

The bow of the ship is formed by two intersecting cylindrical shells, with axes in the z-direction. 

The x-coordinate of the axes is indicated by “X” in the table, and is the same for both axes. The

two y-coordinates are shown as “Y-left” and “Y-right” in the first row of data in Table C.45. 

The cylinders are delimited by an intersecting x-z plane passing through the origin, a y-z plane

passing through the x-coordinate of the axis, and two x-y planes. The lower one forms the

lowermost surface of the hull, while the upper one forms the uppermost surface of the main deck. 

Another pair of cylindrical shells, with the same centers but smaller radii, forms the inner surface

of the hull. The difference between the outer and inner radii—1.91 cm—is the thickness of the

hull. A third pair of cylinders, again concentric with the first two sets, delimits the tally region

in the berthing compartment. The difference between these radii and those of the inner surface
Appendix C External Exposure Dose Coefficients

C-51 NUREG-1640

of the hull is the separation of the nearest occupied location from the edge of the hull, 56.83 cm. 

The cylinders are intersected by x-y planes specified by z-min and z-max of the tally cell.

Table C.43 Steel ship exposure geometry—structures (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Hull—bottom 1.91 -16002 a -1630 1630 -1829 -1827

Decks — 

forward

compartments

Level 1 0.95 0.95 6096 -1630 1630 0 0.95

Main 1.27 -16002 a -1630 1630 305 306

O2 0.95 0.95 3810 -1325 1325 610 611

O3 0.95 0.95 3810 -1325 1325 914 915

O4 0.95 0.95 2743 -1325 1325 1219 1220

O5 0.95 0.95 2743 -1325 1325 1524 1525

O6 0.95 0.95 2743 -1325 1325 1829 1830

Decks — Aft

Level 1 0.95 -7620 -4572 -1630 1630 0 0.95

O5A 0.95 -12953 -6858 -1325 1325 1524 1525

Transverse

bulkheads

T41 0.95 0 0.95 -1630 1630 -1827 305

T42 0.95 0 0.95 -1325 1325 306 1830

T1 0.95 6096 6097 -1129 1129 -1827 305

T2 0.95 3810 3811 -1325 1325 306 915

T3 0.95 2743 2744 -1325 1325 915 1830

T5 0.95 -1524 -1523 -1630 1630 -1827 305

T6 0.95 -3048 -3047 -1630 1630 -1827 305

T7 0.95 -4572 -4571 -1630 1630 -1827 305

T8 0.95 -6096 -6095 -1630 1630 -1827 305

T9 0.95 -6858 -6857 -1325 1325 306 1525

T10 0.95 -12954 -12953 -1325 1325 306 1525

Hull-aft 1.91 -16002 -16000 -1630 1630 -1827 305

Hull & lateral

bulkheads

Hull-left 1.91 -16002 a 1630 1632 -1829 306

Hull-rgt 1.91 -16002 a -1632 -1630 -1829 306

L11 0.95 0 3811 1325 1326 306 915

L21 0.95 0 3811 -1326 -1325 306 915

L12 0.95 0 2744 1325 1326 915 1830

L22 0.95 0 2744 -1326 -1325 915 1830

L3 0.95 -12954 -6857 1325 1326 306 1525

L4 0.95 -12954 -6857 -1326 -1325 306 1525

a For rectangular portion of cell (except forward compartment), x-max = 4136 cm, which also begins curved portion. 

Actual x-max of curved portion determined by intersection of cylindrical arcs.

These cylindrical shells form the bow portion of the main deck, the hull (both sides and bottom),

parts of the berthing and fuel transfer compartments, the forward compartment, and the tally

region inside the berthing compartment. The actual limits of these cells are determined by the
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-52

cylindrical shells and their intersection with the median plane of the ship. The bulkhead T1 is

also delimited by the cylinders; however, the y-dimensions shown in Table C.43 were obtained

by solving for the position of the arc at that point.

Table C.44 Steel ship exposure geometry—compartments (cm)

Location Compartment Content

X YZ

Min Max Min Max Min Max

Tallies

Berthing Volume

detector

57 6040 -1573 1573 46 229

O1 46 3764 -1279 1279 359 406

O4 Area

detector

46 1265 578 1279 1320 —

WS-2 -6706 -5182 900 1601 406 —

Waterline -671

Forward

Fuel Fuel 0.95 6096 -1630 1630 -1827 -305

Level 2 Fuel transfer 0.95 6096 -1630 1630 -305 0

Level 1

Berthing &

forward 

superstructure

0.95 6096 -1630 1630 0.95 305

O1 0.95 3810 -1325 1325 306 610

O2 0.95 3810 -1325 1325 611 914

O3 0.95 2743 -1325 1325 915 1219

O4 0.95 2743 -1325 1325 1220 1524

O5 0.95 2743 -1325 1325 1525 1829

Forward Misc. 6097 aaa -1827 305

Midship

& aft

Cargo-1

Air

-1523 0 -1630 1630 0 305

Ammo-11 -3047 -1524 -1630 1630 0 305

Ammo-21 -4571 -3048 -1630 1630 0 305

Cargo-2 Cargo -1523 0 -1630 1630 -1827 0

Ammo-12

Ammo

-3047 -1524 -1630 1630 -1827 0

Ammo-22 -4571 -3048 -1630 1630 -1827 0

Dry-1 Dry

stores

-6095 -4572 -1630 1630 0.95 305

Dry-2 -6095 -4572 -1630 1630 -1827 0

AMR-11

Misc.

-7620 -6096 -1630 1630 0.95 305

AMR-12 -7620 -6096 -1630 1630 -1827 0

Aft-below -16000 -7620 -1630 1630 -1827 305

Aft SS -12953 -6858 -1325 1325 306 1524

a For rectangular portion of cell (except forward compartment), x-max = 4136 cm, which also begins curved portion. 

Actual x-max of curved portion determined by intersection of cylindrical arcs.

Table C.45 Taper of bow: coordinates of cylindrical shells (cm)

Center Radius (cm)

X Y—left Y—right Outer hull Inner hull Tally

4136.14 -2906.21 2906.21 4536.89 4534.98 4478.15
Appendix C External Exposure Dose Coefficients

C-53 NUREG-1640

C.2.14.5 Composition of Materials

The ship is constructed of DH-36 steel, an alloy commonly used in shipbuilding. The elemental

composition of this alloy is listed in Table C.46. The table also lists the composition and

average density of each major compartment that is included in the ship model, based on the

description in Section C.2.14.2.

Table C.46 Composition of materials and compartments of ship (wt. fraction)

Element DH-36

steel

SeawaterBerthingfwd SSa

Fuel Cargo Ammo Fuel

transfer

Dry

stores

Misc. Aft SSa

H 0.1082 0.0185 0.144 3.11e-03 0.0111 1.03e-06 0.0557 6.50e-07 6.20e-03

C 0.002 0.1321 0.856 0.0222 0.1847 0.3982 0.0444

N 0.0070 1.50e-04 0.0938 1.23e-03 0.0034 7.72e-04 1.66e-03

O 0.8586 0.1488 0.0247 0.2114 3.84e-04 0.4431 2.42e-04 0.0498

Na 0.0108 

Mg 1.27e-03 

Al 0.4954 0.0998 0.0498 0.0999 0.0998

Si 0.004 

S 9.07e-04 

Cl 0.0194 

Ar 1.19e-04 2.57e-06 2.56e-05 2.09e-05 5.79e-05 1.32e-05 2.84e-05

K 4.00e-04 

Ca 4.13e-04 

Mn 0.0145 

Fe 0.980 0.1981 0.9498 0.499 0.8985 0.0498 0.8991 0.7982

D (g/cm3) 7.86 0.998 0.123 0.720 3.11 0.493 0.661 0.226 0.991 0.488

a

 Superstructure

C.2.14.6 Results of Analysis

The results of the analysis are presented in Table C.47. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the four tally locations described in

Section C.2.14.4. Doses inside the compartments from the lower-energy photon sources are

extremely low due to shielding by the material filling the compartments. Since the fill material

is distributed throughout the volume of the compartment, and since the tally volume is typically

0.5 – 1 m from the nearest steel structure, the intervening material essentially absorbs the lowenergy photons. These dose rates are too low to be statistically meaningful and are therefore not

listed. Since the doses are integrated over the entire occupied space in each of the three

compartments and over the occupied area of the main deck, there is no basis for determining

uncertainty based on variation of location. Ux for the steel ship scenarios is therefore assigned

the fixed value, Ux = 1.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-54

Table C.47 Dose rates in steel ship

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

Berthing O1 O4 Main deck Berthing O1 O4 Main deck

0.010 — — — 2.19e-17 — — — 2.00e-17

0.015 — — — 3.35e-16 — — — 2.26e-16

0.020 — — — 1.50e-15 — — — 1.00e-15

0.030 — — — 8.74e-15 — — — 6.51e-15

0.050 5.17e-17 1.09e-16 — 6.66e-14 4.71e-17 9.97e-17 — 6.04e-14

0.070 3.17e-15 6.01e-15 2.43e-15 1.99e-13 3.02e-15 5.73e-15 2.32e-15 1.89e-13

0.100 5.04e-14 7.93e-14 5.03e-14 6.42e-13 4.90e-14 7.70e-14 4.88e-14 6.25e-13

0.200 8.51e-13 1.14e-12 8.47e-13 3.36e-12 8.22e-13 1.11e-12 8.19e-13 3.25e-12

0.500 4.98e-12 6.20e-12 4.86e-12 1.24e-11 4.84e-12 6.02e-12 4.72e-12 1.21e-11

1.0 1.31e-11 1.59e-11 1.28e-11 2.64e-11 1.28e-11 1.55e-11 1.26e-11 2.59e-11

2.0 3.12e-11 3.75e-11 3.13e-11 5.26e-11 3.06e-11 3.67e-11 3.07e-11 5.18e-11

5.0 8.31e-11 9.95e-11 8.60e-11 1.15e-10 8.13e-11 9.73e-11 8.41e-11 1.13e-10

MCNP analyses of bremsstrahlung from the  decay of individual nuclides are not performed for

this model. The bremsstrahlung contribution is calculated as part of the derivation of external

exposure coefficients of all the nuclides, as discussed in Section C.1.2.2.

C.3 Copper

Most of the geometries in the copper scrap exposure scenarios closely resemble the geometries

in the corresponding iron and steel scenarios. New MCNP analyses for copper are required only

if differences in the exposure geometry or the source material would produce significantly

different results. 

There are two reasons why radioactive sources distributed in copper could produce different

dose rates than the same sources distributed in the same configuration of iron or steel. One is

differences in photon cross-sections of copper and iron; the other is the increased intensity of

bremsstrahlung from -emitting nuclides in copper. 

In a one-dimensional approximation, the intensity of electromagnetic radiation from a photon

source uniformly distributed in a material can be calculated by the following expression:

I = total intensity of emitted photons

a = specific activity of photon source in material (photons/s per g)

: = mass absorption coefficient (cm2/g)

' = density of material (g/cm3)
Appendix C External Exposure Dose Coefficients

C-55 NUREG-1640

x = thickness of material (cm)

Table C.48 lists the total absorption cross-section ()tot H), in barns/atom, for iron and copper and

for a range of photon energies from 10 keV to 5 MeV (Storm and Israel 1970). The massabsorption coefficient (:), in cm2

/g, is calculated by multiplying )tot H by the conversion factor

:/) specific to each element. I is calculated for two different thicknesses: 0.8 cm, the thickness

of the cylindrical shell used to represent a large metal object, and 12.19 m (40 ft), the length of

trailer transporting various metal products. These two values span the range of exposure

geometries in the copper analysis. As seen in Table C.48, the intensity of emitted radiation from

copper ranges from 13% greater to 30% less than the corresponding radiation from iron. It is

therefore reasonable to use these dose rates for cases where the exposure geometry is the same

for copper as for iron and steel.

Table C.48 Scoping calculation of intensity of photons emitted from Cu vs. Fe

E

a

(MeV)

Fe Cu

Ratio 

(Cu ÷ Fe) D = 7.86 g/cm3 :/F = 0.01078 D = 8.96 g/cm3 :/F = 0.009478

Ftot H

:

(cm2/g)

I (cm-2 s-1) Ftot H

:

(cm2/g)

I (cm-2 s-1)

0.8 cm 1219 cm 0.8 cm 1219 cm 0.8 cm 1219 cm

0.01 15700 169.25 0.0059 0.006 22600 214.20 0.00467 0.00467 0.79 0.79

0.02 2310 24.90 0.0402 0.0402 3480 32.98 0.0303 0.0303 0.76 0.76

0.05 156 1.68 0.595 0.595 245 2.32 0.431 0.431 0.72 0.72

0.06 91.1 0.982 1.016 1.018 145 1.37 0.728 0.728 0.72 0.71

0.08 39 0.420 2.21 2.38 61 0.578 1.70 1.73 0.77 0.73

0.10 20.5 0.221 3.40 4.53 32 0.303 2.92 3.30 0.86 0.73

0.20 4.51 0.0486 5.42 20.57 6.19 0.0587 5.85 17.04 1.08 0.83

0.50 2.72 0.0293 5.74 34.1 3.13 0.0297 6.46 33.7 1.12 0.99

1.0 2.55 0.0275 5.77 36.4 2.74 0.0260 6.54 38.5 1.13 1.06

2.0 2.16 0.0233 5.85 43.0 2.42 0.0229 6.61 43.6 1.13 1.02

5.0 2.12 0.0229 5.86 43.8 3.45 0.0327 6.39 30.6 1.09 0.70

Source: Storm and Israel 1970

a

 These energies span the same range as the energy grid used for the MCNP calculations. The lower-energy values were

selected to test the dependency of )tot H on E. Some of the energies are different than the ones in the MCNP analysis.

Table C.49 lists the external exposure geometries for which the dose coefficients used in the

copper analysis utilize the dose rates from the 12 photon energies calculated by MCNP for

corresponding geometries in the steel analysis. The bremsstrahlung contributions to the dose

coefficients for individual nuclides are calculated from the scaled bremsstrahlung spectra

discussed in Section C.1.2.2, using the elemental composition of the materials in the copper

analysis. The composition of materials unique to the copper analysis is listed in Table C.50.

The MCNP analyses of copper exposure geometries that do not correspond closely to exposure

geometries in the steel analysis are discussed in the following sections. However, there are no

separate calculations of bremsstrahlung from the -ray spectra of individual radionuclides. The
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-56

calculations using the scaled bremsstrahlung spectra are found to agree with the MCNP

bremsstrahlung calculations in the steel analysis. The computationally intensive MCNP

calculations can only be performed for selected nuclides, while the calculations using the scaled

bremsstrahlung spectra are readily applied to all nuclides and all emitted electrons, not just 

rays. MCNP bremsstrahlung calculations for individual nuclides are therefore not performed for

the copper, aluminum, and concrete analyses.

Table C.49 Corresponding exposure geometries in copper and steel analyses

Coppera Steelb

No. Exposure geometry No. Exposure geometry

22 Baghouse 4 Baghouse

23 Large metal mass 5 Large metal object

24 Small metal mass 6 Small metal object

25 Small object on body 7 Small object next to body

26 Scrap truck 8 Scrap truck

27 Dust truck 11 Dust in dump trailer

28 Slag truck 9 Slag truck

a

 As listed in Table 4.7 in main report

b

 As listed in Table 3.10 in main report

Table C.50 Composition of materials unique to copper analysis (wt. fraction)

Element Copper Baghousea Cu slag Cu dust 

H 1.96e-04 

B 0.0103 

N 0.233 

O 0.299 0.285 0.201 

Na 7.60e-03 

Al 2.71e-03 

Si 0.097 0.075

Ar 3.98e-03 

Fe 0.200

Cu 1.00 0.347 0.400 0.799 

Zn 0.010 

Pb 0.030

Db 8.96 3.61e-03 2.0 n/a

a Baghouse interior: Cu dust + fiberglass + moist air

b Density ( g/cm3

), unless otherwise specified for individual exposure scenarios; bulk densities

for aggregate materials such as slag

C.3.1 Copper Scrap Pile

The analysis of the copper scrap pile is modeled after that of the steel scrap pile described in

Section C.2.1.1. Only the features that are unique to copper are described here.
Appendix C External Exposure Dose Coefficients

C-57 NUREG-1640

The bulk density of the scrap is estimated on the basis of the bulk density of ferrous scrap. As

discussed in Section C.2.1.1, the bulk density of ferrous scrap can range from 16 to 22 lb/ft3 prior

to compaction. Since copper is about 14% denser than steel, it is assumed that the bulk density

of copper-base scrap would be at the upper end of the range cited for ferrous scrap, or 22 lb/ft3

(0.35 g/cm3).

The mass of the pile is based on the average size of a scrap pile at a copper scrap dealer. As

shown in Table 4.1 of the main report, 334 kt of copper-base old scrap was recovered in the

United States in 2000. According to Section D.3.1, there are estimated to be 770 copper scrap

dealers in the United States. Each dealer would have at most two-weeks’ inventory on hand,

which is calculated to be 16.68 t (334,000 t ÷ 770 dealers ÷ 52 wks × 2 wks = 16.68 t). 

Assuming this inventory is in one pile, the radius, as calculated by Equation C.1, is 2.83 m. 

The results of the copper scrap pile analysis are presented in Table C.51. The dose rates from

the 12 monoenergetic photon sources are computed by MCNP at distances of 100 cm and

500 cm from the edge of the pile. A slightly modified method was used to calculate the average

effective coefficient of variation: 

= average standard deviation of dose rates at 100 and 500 cm

= average dose rate at 200 cm

Table C.51 Dose rates from pile of copper scrap

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm FD 100 cm 500 cm xo (cm) Ao 200 cm FD

0.010 1.39e-17 1.56e-19 52.6 3.12e-14 1.44e-18 6.87e-18 1.66e-17 1.88e-19 52.4 3.77e-14 1.73e-18 8.21e-18

0.015 8.95e-17 8.19e-18 -73.5 2.69e-12 3.60e-17 4.07e-17 1.32e-16 1.22e-17 -74.7 4.03e-12 5.34e-17 5.99e-17

0.020 3.58e-16 5.19e-17 -145.9 2.17e-11 1.81e-16 1.53e-16 5.06e-16 7.36e-17 -146.6 3.08e-11 2.56e-16 2.16e-16

0.030 2.18e-15 4.00e-16 -199.7 1.96e-10 1.23e-15 8.90e-16 2.63e-15 4.85e-16 -201.1 2.38e-10 1.48e-15 1.07e-15

0.050 1.57e-14 3.22e-15 -231.1 1.72e-09 9.26e-15 6.24e-15 1.64e-14 3.37e-15 -231.7 1.80e-09 9.68e-15 6.52e-15

0.070 5.40e-14 1.14e-14 -240.0 6.24e-09 3.22e-14 2.13e-14 5.28e-14 1.12e-14 -241.5 6.16e-09 3.16e-14 2.08e-14

0.100 1.81e-13 3.88e-14 -244.9 2.15e-08 1.09e-13 7.11e-14 1.81e-13 3.88e-14 -244.9 2.15e-08 1.09e-13 7.11e-14

0.200 1.31e-12 2.81e-13 -245.1 1.56e-07 7.87e-13 5.15e-13 1.31e-12 2.81e-13 -245.1 1.56e-07 7.87e-13 5.15e-13

0.500 6.51e-12 1.40e-12 -245.9 7.79e-07 3.92e-12 2.56e-12 6.58e-12 1.42e-12 -247.0 7.92e-07 3.97e-12 2.58e-12

1.0 1.57e-11 3.41e-12 -249.1 1.91e-06 9.49e-12 6.15e-12 1.59e-11 3.44e-12 -247.9 1.92e-06 9.59e-12 6.23e-12

2.0 3.40e-11 7.44e-12 -251.6 4.20e-06 2.06e-11 1.33e-11 3.40e-11 7.44e-12 -251.6 4.20e-06 2.06e-11 1.33e-11

5.0 7.61e-11 1.67e-11 -252.5 9.46e-06 4.62e-11 2.97e-11 7.62e-11 1.68e-11 -254.1 9.55e-06 4.63e-11 2.97e-11

Averagea 7.38e-12 0.65b 7.40e-12 0.64b

a

 Omits 0.010 MeV values—see text

b

 Average effective coefficient of variation

The standard deviation of the 10 keV dose rates is much greater than the calculated dose rate at

200 cm. Since, as was discussed in Section C.2.2, photons in this low-energy range make only

minor contributions to the dose coefficients of most of the radionuclides in the present analysis,
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-58

the 10 keV doses are not used in calculating . Based on these results, Ux for the scrap yard is

assigned a uniform distribution: 0.36 # Ux # 1.64.

C.3.2 Copper Slag Pile

As discussed in Section 4.6.3 of the main report, copper slag is spread out in a thin layer on the

floor in the refinery for recovery of metallic copper (the term “slag pile” is used for consistency

with the steel analysis). The slag is produced during the melting of one heat in the 200-ton

(180-t) furnace at Reading Tube, which is the reference fire refinery in the present analysis. 

Since, as noted in Section 4.2.3.1, about 25% of the melt is left in the furnace as a heel for the

subsequent heat, the actual output of one furnace heat is about 150 tons (135 t). The mass

fraction of slag is estimated to be 2 – 2.5% of the charge weight (see Section 4.3.1.1). 

Consequently, the average mass of slag produced from one heat is about 3.375 tons (3,062 kg)

(150 tons × 2.25% = 3.375 tons).

The slag would be spread out in a 5-cm thick layer to allow visual identification of any copper

nuggets embedded in the slag (Anigstein et al. 2001, Section 9.3.3). In the present analysis,

copper slag is assigned a density of 2 g/cm3

, the same as steel slag. The “pile” of slag thus

occupies an area of 30.62 m2 (3,062 kg ÷ [0.05 m × 2,000 kg/m3] = 30.62 m2). The radius of this

disk is given by = 3.12 m. The slag “pile” is located near a corner of a steel building

that is 200 ft long × 40 ft wide × 40 ft high (61× 12.2 × 12.2 m) and stands on a thick concrete

slab. Since the slag processing worker would be moving over the entire area of the slag, the

doses are integrated over this area, at a height of 1 m. Since the radiation is incident from many

different directions, the isotropic (ISO) irradiation geometry is used in the MCNP analysis. The

detailed exposure geometry is presented in Table C.52.

Table C.52 Worker handling copper slag: exposure geometry (cm)

Location Thickness

X YZ

Min or radius Max or center Min Max or center Min Max

Source—Cu slag 312 412 412 0 5

walls—steel 0.159 0 6096 0 1219 0 1219

roof—steel 0.159 0 6096 0 1219 1219 1219

Floor—concrete  3 MFPs 0

Tally (area detector) 312 412 412 100

The results of the analysis are presented in Table C.53. The dose rates from the 12

monoenergetic photon sources are computed by MCNP over the area of the slag. Since the doses

are integrated over the entire area, there is no basis for determining uncertainty based on

variation of location. Ux for the slag handling scenario is therefore assigned the fixed value,

Ux = 1.
Appendix C External Exposure Dose Coefficients

C-59 NUREG-1640

Figure C.13 Typical arrangement of

copper tubes—dimensions in cm

Table C.53 Dose rates to worker handling copper slag

Energy (MeV) EDE (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

0.010 2.35e-17 2.15e-17

0.015 2.76e-16 1.87e-16

0.020 1.08e-15 7.22e-16

3.00e-02 5.58e-15 4.16e-15

0.050 3.24e-14 2.96e-14

0.070 9.95e-14 9.52e-14

0.100 2.49e-13 2.43e-13

0.200 1.40e-12 1.35e-12

0.500 5.76e-12 5.62e-12

1.0 1.25e-11 1.22e-11

2.0 2.39e-11 2.35e-11

5.0 4.99e-11 4.88e-11

C.3.3 Truck Loaded with Metal Product

The exposed individual in the scenario describing the transportation of copper products is a truck

driver hauling copper tubes. The standard length of straight copper tubes is 20 ft (6.1 m). The

tubes in this scenario have a 2.5-in (6.35 cm) O.D., a wall thickness of 0.2356 cm, and weigh

54.5 lb (24.72 kg) each. A 20-t load comprises 809 tubes. 

The tubes are transported in an enclosed trailer that

is 20 ft long, 8.5 ft wide, and 109 inches high (610

× 259 × 277 cm) on the inside—the dimensions of

the trailer are based on a Montone aluminum

trailer. The tubes are in alternating layers of 39 –

38 tubes wide: bottom layer 39, next 38, etc.—a

total of 21 layers. The arrangement of the tubes is

illustrated in Figure C.13.

The load is modeled as a rectangular solid. The

height of the load, based on the dimensions shown

in Figure C.13, is 244 cm (5.499 × 20 + 3.175 × 2

 244). The total volume of the load is 1.756 × 107

cm3; the effective density, 'eff = = 1.139 g/cm3.

The truck hauling the trailer—the same as the one hauling EAF dust in a dump trailer, described

in Section C.2.8.4—is equipped with a sleeper. Doses to the driver in both driver’s seat and in

the sleeper are calculated by MCNP. The assessments of the two locations utilize the

posteroanterior (PA) and rotational (ROT) exposure geometries, respectively. Details of the

exposure geometry are presented in Table C.54.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-60

Table C.54 Driver of tractor-trailer hauling copper tubes: exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -812.8 -203.2 -123.8 123.8 127.6 244.0

Truck cab—aluminum 0.3175 0.0 287.0 -106.7 106.7 127.0 391.2

Trailer—

aluminum*

floor 0.635 -812.8 -203.2 -129.5 129.5 127.0 127.6

nose & taila 0.476 -812.8 -203.2 -129.5 129.5 127.6 404.5

sidesb 0.4064 -812.8 -203.2 -129.5 129.5 127.6 404.5

top 0.3175 -812.8 -203.2 -129.5 129.5 404.5 404.8

Pavement—concrete 0.0

Tally points

1 205.7

79.38 180.3

2 172.7

3 95.3

0.0 203.2

4 114.3

a x-min and x-max refer to tail and nose, respectively 

b y-min and y-max refer to right and left sides, respectively

The results of the analysis are presented in Tables C.55 and C.56. The dose rates from 11 of the

12 monoenergetic photon sources are computed by MCNP at the two locations specified in

Table C.54. Because of the strong absorption of low-energy photons by the walls of the truck

cab, the dose rates from the 10 keV source are too low to be statistically meaningful and are

therefore not listed. The average of the dose rates at the two tally points is adopted as the dose

rate from each of the 11 photon sources in this exposure geometry. is calculated on the basis

of all 11 sources. Based on these results, Ux is assigned a uniform distribution. In the driver’s

seat: 0.9 # Ux # 1.1, while in the sleeper: 0.93 # Ux # 1.07.

Table C.55 Hauling copper tubes: dose rates in driver’s seat

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 1.57e-25 1.85e-25 1.71e-25 0.116 9.33e-26 1.09e-25 1.01e-25 0.110

0.020 2.24e-20 2.59e-20 2.42e-20 0.102 7.88e-21 9.11e-21 8.50e-21 1.02e-01

0.030 2.28e-17 2.65e-17 2.47e-17 0.106 1.29e-17 1.50e-17 1.40e-17 1.06e-01

0.050 9.92e-16 1.14e-15 1.07e-15 0.098 7.71e-16 8.89e-16 8.30e-16 1.01e-01

0.070 4.76e-15 5.44e-15 5.10e-15 0.094 4.10e-15 4.70e-15 4.40e-15 9.64e-02

0.1 1.93e-14 2.20e-14 2.07e-14 0.093 1.74e-14 1.99e-14 1.87e-14 9.48e-02

0.2 1.48e-13 1.69e-13 1.59e-13 0.094 1.36e-13 1.55e-13 1.46e-13 9.23e-02

0.500 7.04e-13 8.04e-13 7.54e-13 0.094 6.57e-13 7.50e-13 7.04e-13 9.35e-02

1.0 1.61e-12 1.85e-12 1.73e-12 0.098 1.51e-12 1.73e-12 1.62e-12 9.60e-02

2.0 3.33e-12 3.82e-12 3.58e-12 0.097 3.13e-12 3.59e-12 3.36e-12 9.68e-02

5.0 7.25e-12 8.33e-12 7.79e-12 0.098 6.73e-12 7.73e-12 7.23e-12 0.098

Average 0.099 0.099

a

 Coefficient of variation
Appendix C External Exposure Dose Coefficients

C-61 NUREG-1640

Table C.56 Hauling copper tubes: dose rates in sleeper berth

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 3 TP 4 Mean Cv

a TP 3 TP 4 Mean Cva

0.015 7.75e-25 7.01e-25 7.38e-25 0.071 5.21e-25 4.71e-25 4.96e-25 0.071

0.020 5.71e-20 5.15e-20 5.43e-20 0.073 4.03e-20 3.63e-20 3.83e-20 0.074

0.030 4.59e-17 4.11e-17 4.35e-17 0.078 3.79e-17 3.40e-17 3.60e-17 0.077

0.050 1.55e-15 1.40e-15 1.48e-15 0.072 1.48e-15 1.33e-15 1.41e-15 0.076

0.070 7.01e-15 6.36e-15 6.69e-15 0.069 7.10e-15 6.44e-15 6.77e-15 0.069

0.100 2.79e-14 2.54e-14 2.67e-14 0.066 2.80e-14 2.55e-14 2.68e-14 0.066

0.200 2.15e-13 1.96e-13 2.06e-13 0.065 2.15e-13 1.96e-13 2.06e-13 0.065

0.5 1.06e-12 9.60e-13 1.01e-12 0.070 1.05e-12 9.53e-13 1.00e-12 0.069

1.0 2.48e-12 2.24e-12 2.36e-12 0.072 2.46e-12 2.22e-12 2.34e-12 0.073

2.0 5.25e-12 4.74e-12 5.00e-12 0.072 5.24e-12 4.74e-12 4.99e-12 0.071

5 1.17e-11 1.05e-11 1.11e-11 0.076 1.17e-11 1.05e-11 1.11e-11 0.076

Average 0.071 0.072

a

 Coefficient of variation

C.4 Aluminum

Because of the large differences in density and atomic number between the materials in the

aluminum analysis and those in the steel and copper analysis, new MCNP calculations of dose

rates are performed for all but one of the exposure geometries. The exception is the baghouse at

an aluminum smelter. The difference in the composition of the dust is judged not to significantly

affect the dose rates, given the attenuation by the filters, the steel walls, and the air. However, to

derive the dose coefficients for individual nuclides, the elemental composition of the interior of

the baghouse module is used to calculate the bremsstrahlung contribution, using the scaled

bremsstrahlung spectra discussed in Section C.1.2.2. 

The composition of the materials unique to the aluminum analysis is listed in Table C.57.

C.4.1 Aluminum Scrap Pile

The analysis of the aluminum scrap pile is modeled after that of the steel scrap pile described in

Section C.2.1.1. Only the features that are unique to aluminum are described here.

The bulk density of the scrap is estimated on the basis of the bulk density of ferrous scrap: 

'b,Al = bulk density of aluminum alloy scrap

= 0.11 g/cm3

'b,s = bulk density of steel scrap

= 0.32 g/cm3
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-62

'Al = density of aluminum

= 2.71 g/cm3

's = density of steel

 = 7.86 g/cm3

Table C.57 Composition of materials unique to aluminum analysis (wt. fraction)

Element Al scrap Al dust Dross Baghousea Alloy 319 Alloy 383 Alloy 390

H 1.96e-04 

B 0.0103 

N 0.2331 

O 0.4311 0.1716 0.3984 

Na 0.0922 7.60e-03 

Mg 5.50e-04 0.0394 0.0171 0.0010 0.0010 0.0010

Al 0.9300 0.3940 0.3596 0.1736 0.8730 0.8165 0.7585

Si 0.0331 0.0969 0.0600 0.1050 0.1750

Cl 0.2102 

Ar 0.0040 

K 0.1663 

Ti 1.38e-03 0.0085 0.0037 0.0025 0.0020

Mn 0.0028 0.0012 5.22e-04 0.0050 0.0050 0.0010

Fe 0.0055 0.0939 0.0407 0.0100 0.0130 0.0130

Ni 0.0019 0.0035 0.0030 0.0035

Cu 0.0193 0.0118 0.0051 0.0350 0.0250 0.0450

Zn 0.0055 0.0201 0.0087 0.0100 0.0300 0.0010

Sn 0.0015 

Db c 1.224 1.3 3.61e-03 2.79 2.74 d

a Baghouse interior: Al dust + fiberglass + moist air

b Density ( g/cm3

), unless otherwise specified for individual exposure scenarios; bulk densities for aggregate materials

such as dross and Al dust

c See descriptions of exposure geometries

d See description of engine block in Section C.4.9 for effective density used in analysis

The average size of a scrap pile at an aluminum scrap dealer is estimated to be approximately

100 tons (90.7 t). The radius, as calculated by Equation C.1, is 7.43 m. 

Aluminum scrap is composed of various alloys but is known to contain 93% aluminum. In the

present analysis, the aluminum scrap is assumed to be Alloy 319. The fractions of elements

other than aluminum, listed in Table C.57, are calculated on the assumption that these elements

make up 7% of the total weight of the scrap and are present in the same relative proportions as in

Alloy 319.
Appendix C External Exposure Dose Coefficients

C-63 NUREG-1640

The results of the aluminum scrap pile analysis are presented in Table C.58. The dose rates from

the 12 monoenergetic photon sources are computed by MCNP at distances of 100 cm and

500 cm from the edge of the pile. The average effective coefficient of variation, which is listed

at the bottom of the table, was calculated in the same way as in the analysis of the copper scrap

pile described in Section C.3.1, again omitting the 10 keV dose rates. Based on these results, Ux

for the aluminum scrap yard is assigned a uniform distribution: 0.5 # Ux # 1.5.

Table C.58 Dose rates from pile of aluminum scrap

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm FD 100 cm 500 cm xo (cm) Ao 200 cm FD

0.01 8.44e-17 1.85e-18 30.49 4.08e-13 1.42e-17 4.13e-17 7.04e-17 1.54e-18 30.57 3.39e-13 1.18e-17 3.44e-17

0.015 1.24e-15 1.64e-16 -128.61 6.48e-11 6.00e-16 5.38e-16 8.35e-16 1.11e-16 -129.53 4.40e-11 4.05e-16 3.62e-16

0.020 5.34e-15 1.10e-15 -232.42 5.90e-10 3.16e-15 2.12e-15 3.76e-15 7.73e-16 -231.82 4.14e-10 2.22e-15 1.49e-15

0.030 2.96e-14 7.79e-15 -321.37 5.26e-09 1.93e-14 1.09e-14 2.44e-14 6.41e-15 -320.59 4.32e-09 1.59e-14 9.00e-15

0.050 1.69e-13 5.06e-14 -383.36 3.95e-08 1.16e-13 5.92e-14 1.61e-13 4.81e-14 -382.20 3.74e-08 1.10e-13 5.65e-14

0.070 4.22e-13 1.33e-13 -411.99 1.11e-07 2.95e-13 1.45e-13 4.28e-13 1.34e-13 -408.14 1.11e-07 2.99e-13 1.47e-13

0.100 9.35e-13 3.04e-13 -430.68 2.63e-07 6.62e-13 3.16e-13 9.37e-13 3.05e-13 -431.39 2.65e-07 6.64e-13 3.16e-13

0.2 2.86e-12 9.44e-13 -440.11 8.34e-07 2.04e-12 9.58e-13 2.86e-12 9.44e-13 -440.11 8.34e-07 2.04e-12 9.58e-13

0.5 8.73e-12 2.87e-12 -437.58 2.52e-06 6.21e-12 2.93e-12 8.66e-12 2.85e-12 -438.24 2.51e-06 6.16e-12 2.91e-12

1.0 1.87e-11 6.16e-12 -438.84 5.43e-06 1.33e-11 6.27e-12 1.85e-11 6.10e-12 -439.45 5.38e-06 1.32e-11 6.20e-12

2 3.81e-11 1.27e-11 -446.41 1.14e-05 2.72e-11 1.27e-11 3.81e-11 1.27e-11 -446.41 1.14e-05 2.72e-11 1.27e-11

5.0 8.98e-11 3.05e-11 -458.75 2.80e-05 6.46e-11 2.97e-11 8.97e-11 3.04e-11 -457.30 2.79e-05 6.45e-11 2.97e-11

Averagea 1.04e-11 0.46b 1.04e-11 0.46b

a

 Omits 0.010 MeV values—see text

b

 Average effective coefficient of variation—see text

C.4.2 Dross Pile

The analysis of the aluminum dross pile is modeled after that of the steel slag pile described in

Section C.2.2. Only the features that are unique to aluminum are described here.

The mass of the pile is based on the average amount of dross on hand at a secondary aluminum

smelter, which is calculated as follows. The average production capacity of the 18 smelters

listed in Table D.10 is about 82.2 kt/y. The average mass fraction of dross, based on the

probability distribution presented in Table B.7, is 0.16. Dross is typically removed from a

smelter once a month. Consequently, the average amount of dross that would be on hand at any

one time is one half of a month’s production, or of the annual production. Consequently, the

mass of the pile is 548 t (82,200 t × 0.16 ÷ 24 = 548 t). The radius, as calculated by

Equation C.1, is 5.86 m.

The results of the aluminum dross pile analysis are presented in Table C.59. The dose rates from

the 12 monoenergetic photon sources are computed by MCNP at distances of 100 cm and 500

cm from the edge of the pile. The average effective coefficient of variation is calculated in the

same way as in the analysis of the copper scrap pile described in Section C.3.1, again omitting
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-64

the 10 keV dose rates. Based on these results, Ux for dross handling is assigned a uniform

distribution: 0.4 # Ux # 1.6.

Table C.59 Dose rates from pile of aluminum dross

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm FD 100 cm 500 cm xo (cm) Ao 200 cm FD

0.010 6.66e-17 1.39e-18 32.45 3.04e-13 1.08e-17 3.26e-17 5.56e-17 1.16e-18 32.47 2.54e-13 9.03e-18 2.72e-17

0.015 1.00e-15 1.19e-16 -110.65 4.44e-11 4.60e-16 4.41e-16 6.74e-16 8.01e-17 -110.44 2.98e-11 3.10e-16 2.97e-16

0.020 4.33e-15 7.90e-16 -198.25 3.85e-10 2.43e-15 1.77e-15 3.05e-15 5.57e-16 -198.50 2.72e-10 1.71e-15 1.25e-15

0.030 2.44e-14 5.67e-15 -272.28 3.38e-09 1.52e-14 9.37e-15 2.02e-14 4.67e-15 -270.45 2.77e-09 1.25e-14 7.77e-15

0.050 1.47e-13 3.81e-14 -314.83 2.53e-08 9.54e-14 5.45e-14 1.41e-13 3.62e-14 -310.85 2.38e-08 9.12e-14 5.24e-14

0.070 3.90e-13 1.04e-13 -327.13 7.12e-08 2.56e-13 1.43e-13 3.95e-13 1.05e-13 -325.73 7.16e-08 2.59e-13 1.45e-13

0.100 9.17e-13 2.48e-13 -333.41 1.72e-07 6.05e-13 3.35e-13 9.18e-13 2.48e-13 -332.92 1.72e-07 6.06e-13 3.35e-13

0.200 3.05e-12 8.18e-13 -329.66 5.63e-07 2.01e-12 1.12e-12 3.05e-12 8.18e-13 -329.66 5.63e-07 2.01e-12 1.12e-12

0.5 9.95e-12 2.60e-12 -318.30 1.74e-06 6.48e-12 3.68e-12 9.87e-12 2.58e-12 -318.45 1.73e-06 6.43e-12 3.65e-12

1 2.22e-11 5.73e-12 -313.08 3.79e-06 1.44e-11 8.24e-12 2.20e-11 5.68e-12 -313.20 3.76e-06 1.43e-11 8.16e-12

2.0 4.79e-11 1.23e-11 -310.93 8.09e-06 3.10e-11 1.78e-11 4.78e-11 1.23e-11 -311.80 8.11e-06 3.09e-11 1.78e-11

5.0 1.22e-10 3.13e-11 -310.56 2.06e-05 7.89e-11 4.54e-11 1.22e-10 3.12e-11 -309.23 2.04e-05 7.88e-11 4.54e-11

Averagea 1.22e-11 0.57b 1.21e-11 0.57b

a

 Omits 0.010 MeV values—see text

b

 Average effective coefficient of variation (see text)

C.4.3 Large Aluminum Object

The generic large aluminum object is made of Alloy 319, a common aluminum alloy. The

exposure geometry is the same as that for the large steel object. 

The results of the analysis are presented in Table C.60. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the three locations described in

Section C.2.5. The coefficient of variation is calculated in the conventional manner, based on

the mean and standard deviation at each energy. The values of Cv for the 10 keV source are

considerably higher than for the other sources. Since, as was discussed in Section C.2.2, photons

in this low-energy range make only minor contributions to the dose coefficients of most of the

radionuclides in the present analysis, is calculated on the basis of the 11 sources, E > 10

keV. Based on these results, Ux for the large aluminum object is assigned the uniform

distribution: 0.2 # Ux # 1.8.

C.4.4 Small Aluminum Object

The generic small aluminum object is also made of Alloy 319. The exposure geometry is the

same as that for the small steel object. 

The results of the analysis are presented in Table C.61. The dose rates from the 12

monoenergetic photon sources are computed by MCNP at the three locations described in

Section C.2.6. Because of the large variation of dose rate with distance, Ux is assigned a
Appendix C External Exposure Dose Coefficients

18 Brandt Miller, Clement Industries, private communication with Robert Anigstein, SC&A, Inc., September 23,

2002.

19 Robert H. Graham, plant manager, Wabash Alloys, Dickson TN, private communication with William C.

Thurber, SC&A, Inc., May 2, 1997.

C-65 NUREG-1640

specially constructed distribution. By fitting parameters to the data, we derive the following

Crystal Ball distribution: Ux = 0.2 + 8.8 × Beta(, , s), with  = 0.7034602,  = 7.034602,

s = 1. 

Table C.60 Dose rates from large aluminum object

Energy

 (MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 200 cm 300 cm CV

a 100 cm 200 cm 300 cm CVa

0.010 1.97e-17 3.88e-18 1.09e-18 1.00 1.64e-17 3.23e-18 9.08e-19 1.22

0.015 2.40e-16 7.09e-17 2.97e-17 0.98 1.61e-16 4.77e-17 1.99e-17 0.98

0.02 9.71e-16 3.15e-16 1.45e-16 0.91 6.85e-16 2.22e-16 1.02e-16 0.92

0.03 5.19e-15 1.78e-15 8.60e-16 0.87 4.29e-15 1.47e-15 7.11e-16 0.87

0.050 2.68e-14 9.60e-15 4.89e-15 0.84 2.56e-14 9.17e-15 4.66e-15 0.84

0.070 5.55e-14 2.06e-14 1.09e-14 0.81 5.64e-14 2.09e-14 1.10e-14 0.81

0.100 9.93e-14 3.79e-14 2.05e-14 0.79 9.95e-14 3.80e-14 2.06e-14 0.79

0.200 2.30e-13 8.88e-14 4.87e-14 0.78 2.31e-13 8.88e-14 4.88e-14 0.78

0.500 5.79e-13 2.14e-13 1.14e-13 0.81 5.73e-13 2.12e-13 1.13e-13 0.81

1 1.07e-12 3.85e-13 2.00e-13 0.83 1.06e-12 3.81e-13 1.99e-13 0.83

2.0 1.86e-12 6.54e-13 3.34e-13 0.85 1.87e-12 6.55e-13 3.34e-13 0.85

5.0 3.72e-12 1.28e-12 6.47e-13 0.86 3.71e-12 1.28e-12 6.46e-13 0.86

Averageb 0.85 0.85

a

 Coefficient of variation

b

 Omits 0.010 MeV values—see text

C.4.5 Aluminum Scrap Truck

The aluminum scrap would most likely be hauled in a dump trailer, such as the Mark 2 Scrapstar,

manufactured by Clement Industries. The Mark 2, Clement’s most popular large-capacity trailer,

has the following inside dimensions: 77 inches high, 37 feet long, 851⁄4 inches wide (1.96 × 11.3

× 2.16 m).18 A typical load of aluminum scrap arriving at a secondary smelter weighs 45,000 lb

(20.41 t).19 Assuming that this load completely fills the volume of the trailer, the scrap would

have an effective density of 0.4274 g/cm3. 

The tractor hauling this trailer is assumed to be the same as the one used to haul the trailer

carrying steel scrap, described in Section C.2.8.1. The detailed geometry is presented in

Table C.62. 
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-66

Table C.61 Dose rates from small aluminum object

Energy

 (MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 200 cm 300 cm 100 cm 200 cm 300 cm

0.010 2.07e-18 2.93e-19 7.37e-20 1.73e-18 2.44e-19 6.15e-20

0.015 2.30e-17 4.92e-18 1.87e-18 1.55e-17 3.31e-18 1.26e-18

0.020 9.10e-17 2.15e-17 8.97e-18 6.42e-17 1.52e-17 6.32e-18

0.030 4.82e-16 1.21e-16 5.34e-17 3.99e-16 9.98e-17 4.41e-17

0.050 2.59e-15 6.93e-16 3.25e-16 2.48e-15 6.61e-16 3.09e-16

0.070 5.55e-15 1.56e-15 7.65e-16 5.64e-15 1.58e-15 7.72e-16

0.100 1.00e-14 2.94e-15 1.50e-15 1.01e-14 2.95e-15 1.50e-15

0.2 2.35e-14 6.97e-15 3.62e-15 2.35e-14 6.98e-15 3.63e-15

0.500 6.07e-14 1.69e-14 8.41e-15 6.00e-14 1.67e-14 8.34e-15

1.0 1.15e-13 3.05e-14 1.46e-14 1.14e-13 3.03e-14 1.45e-14

2.0 2.03e-13 5.24e-14 2.43e-14 2.03e-13 5.25e-14 2.44e-14

5.0 4.09e-13 1.04e-13 4.73e-14 4.09e-13 1.04e-13 4.73e-14

Table C.62 Aluminum scrap truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load 0 -1128 -108.3 108.3 0 195.6

Trailer—SAE 1020 steel 4 sides 0.476 0.476 -1128.5 -108.8 108.8 0.0 195.6

Floor 0.635 0.476 -1128.5 -108.8 108.8 -0.6 0.0

Truck cab—SAE 1020 steel 6 walls 0.15 213 396 -107 107 0 152.4

Pavement—concrete — — -125

Tally points (TP)

1 244

53 76.2

2 335

The results of the analysis are presented in Table C.63. The dose rates from 10 of the 12

monoenergetic photon sources are computed by MCNP at the two locations specified in

Table C.62. Because of the strong absorption of low-energy photons by the walls of the truck

cab, the dose rates from 10 and 15 keV sources are too low to be statistically meaningful and are

therefore not listed. The average of the dose rates at the two tally points is adopted as the dose

rate from each of the 10 photon sources in this exposure geometry. is calculated on the basis

of these 10 sources. Based on these results, Ux for the driver of the aluminum scrap truck is

assigned the uniform distribution: 0.7 # Ux # 1.3.

C.4.6 Dross Truck

The exposure geometry for the truck driver hauling dross from a secondary aluminum smelter is

almost the same as for the truck hauling steel slag, the only difference being the composition and

density of the dross. Dross, having a lower density than steel slag, would fill the trailer to a

greater depth. The details of the exposure geometry are presented in Table C.64.
Appendix C External Exposure Dose Coefficients

C-67 NUREG-1640

Table C.63 Dose rates to aluminum scrap truck driver

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.020 3.38e-34 1.01e-33 6.74e-34 0.71 1.28e-34 3.69e-34 2.49e-34 0.69

0.030 1.31e-22 1.99e-22 1.65e-22 0.29 6.93e-23 1.07e-22 8.82e-23 0.30

0.050 1.86e-17 1.98e-17 1.92e-17 0.04 1.40e-17 1.48e-17 1.44e-17 0.04

0.07 2.33e-15 1.59e-15 1.96e-15 0.27 2.03e-15 1.38e-15 1.71e-15 0.27

0.100 3.97e-14 2.47e-14 3.22e-14 0.33 3.61e-14 2.24e-14 2.93e-14 0.33

0.200 4.04e-13 2.53e-13 3.29e-13 0.33 3.73e-13 2.33e-13 3.03e-13 0.33

0.500 1.71e-12 1.07e-12 1.39e-12 0.33 1.60e-12 9.98e-13 1.30e-12 0.33

1.0 3.90e-12 2.41e-12 3.16e-12 0.33 3.66e-12 2.26e-12 2.96e-12 0.33

2.0 8.12e-12 5.02e-12 6.57e-12 0.33 7.64e-12 4.72e-12 6.18e-12 0.33

5.0 1.91e-11 1.20e-11 1.56e-11 0.32 1.77e-11 1.11e-11 1.44e-11 0.32

0.32 0.32

a

 Coefficient of variation

Table C.64 Dross truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -731.5 0.0 -121.9 121.9 137.2 223.4

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer

aluminum

floor 0.635 -731.5 0.0 -121.9 121.9 136.5 137.2

nose & taila 0.4826 -731.5 0.0 -121.9 121.9 137.2 259.1

sidesb 0.4064 -731.5 0.0 -121.9 121.9 137.2 259.1

Pavement—concrete 40.6 -40.6 0.0

Tally points (TP)

1 243.8

61.0 168.4

2 335.3

a

 x-min and x-max refer to tail and nose, respectively 

b

 y-min and y-max refer to right and left sides, respectively

The results of the analysis are presented in Table C.65. The dose rates from 11 of the 12

monoenergetic photon sources are computed by MCNP at the two locations specified in Table

C.64. Because of the strong absorption of low-energy photons by the walls of the truck cab, the

dose rates from the 10 keV source are too low to be statistically meaningful and are therefore not

listed. The average of the dose rates at the two tally points is adopted as the dose rate from each

of the 11 photon sources in this exposure geometry. is calculated on the basis of these 11

sources. Based on these results, Ux for the driver of the aluminum dross truck is assigned the

uniform distribution: 0.7 # Ux # 1.3.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-68

Table C.65 Dose rates to dross truck driver

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 6.54e-24 5.59e-24 6.07e-24 0.11 4.76e-23 3.39e-23 4.08e-23 0.24

0.020 4.41e-19 2.71e-19 3.56e-19 0.34 1.60e-19 9.85e-20 1.29e-19 0.34

0.030 3.36e-16 1.98e-16 2.67e-16 0.37 1.89e-16 1.11e-16 1.50e-16 0.37

0.050 1.25e-14 7.73e-15 1.01e-14 0.33 9.66e-15 5.97e-15 7.82e-15 0.33

0.070 4.72e-14 2.97e-14 3.85e-14 0.32 4.04e-14 2.53e-14 3.29e-14 0.33

0.100 1.27e-13 8.12e-14 1.04e-13 0.31 1.14e-13 7.25e-14 9.33e-14 0.31

0.200 4.49e-13 2.86e-13 3.68e-13 0.31 4.12e-13 2.61e-13 3.37e-13 0.32

0.500 1.37e-12 8.55e-13 1.11e-12 0.33 1.27e-12 7.95e-13 1.03e-12 0.33

1.0 2.86e-12 1.75e-12 2.31e-12 0.34 2.68e-12 1.64e-12 2.16e-12 0.34

2.0 5.78e-12 3.51e-12 4.65e-12 0.35 5.43e-12 3.30e-12 4.37e-12 0.35

5.0 1.38e-11 8.34e-12 1.11e-11 0.35 1.28e-11 7.74e-12 1.03e-11 0.35

Average 0.31 0.33

a

 Coefficient of variation

C.4.7 Aluminum Dust Truck

The exposure geometry for the truck driver hauling dust from a secondary aluminum smelter is

almost the same as for the truck hauling dross, the only difference being the different

composition and density of the aluminum smelter dust. Aluminum dust, having a lower density

than dross, would fill the trailer to a greater depth. The details of the exposure geometry are

presented in Table C.66.

Table C.66 Aluminum dust truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -731.5 0.0 -121.9 121.9 137.2 228.6

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer—

aluminum

floor 0.635 -731.5 0.0 -121.9 121.9 136.5 137.2

nose & taila 0.4826 -731.5 0.0 -121.9 121.9 137.2 259.1

sidesb 0.4064 -731.5 0.0 -121.9 121.9 137.2 259.1

Pavement—concrete 40.6 -40.6 0.0

Tally points (TP)

1 243.8

61.0 168.4

2 335.3

a

 x-min and x-max refer to tail and nose, respectively 

b

 y-min and y-max refer to right and left sides, respectively

The results of the analysis are presented in Table C.67. The dose rates from 11 of the 12

monoenergetic photon sources are computed by MCNP at the two locations specified in Table

C.66. Because of the strong absorption of low-energy photons by the walls of the truck cab, the

dose rates from the 10 keV source are too low to be statistically meaningful and are therefore not
Appendix C External Exposure Dose Coefficients

C-69 NUREG-1640

listed. The average of the dose rates at the two tally points is adopted as the dose rate from each

of the 11 photon sources in this exposure geometry. is calculated on the basis of these 11

sources. Based on these results, Ux for the driver of the aluminum dust truck is assigned a

uniform distribution: 0.7 # Ux # 1.3.

Table C.67 Dose rates to aluminum dust truck driver

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 6.73e-24 5.84e-24 6.29e-24 0.10 4.67e-23 3.37e-23 4.02e-23 0.23

0.020 4.11e-19 2.55e-19 3.33e-19 0.33 1.50e-19 9.29e-20 1.21e-19 0.33

0.030 3.00e-16 1.78e-16 2.39e-16 0.36 1.69e-16 9.97e-17 1.34e-16 0.36

0.050 1.10e-14 6.78e-15 8.89e-15 0.34 8.50e-15 5.24e-15 6.87e-15 0.34

0.070 4.20e-14 2.64e-14 3.42e-14 0.32 3.61e-14 2.25e-14 2.93e-14 0.33

0.100 1.18e-13 7.46e-14 9.63e-14 0.32 1.06e-13 6.68e-14 8.64e-14 0.32

0.200 4.44e-13 2.82e-13 3.63e-13 0.32 4.07e-13 2.58e-13 3.33e-13 0.32

0.500 1.40e-12 8.72e-13 1.14e-12 0.33 1.30e-12 8.12e-13 1.06e-12 0.33

1.0 2.94e-12 1.81e-12 2.38e-12 0.34 2.76e-12 1.69e-12 2.23e-12 0.34

2.0 6.00e-12 3.64e-12 4.82e-12 0.35 5.63e-12 3.42e-12 4.53e-12 0.35

5.0 1.45e-11 8.77e-12 1.16e-11 0.35 1.34e-11 8.13e-12 1.08e-11 0.35

0.31 0.33

a

 Coefficient of variation

C.4.8 Truck Loaded with Aluminum Product

Aluminum ingots are the main product of secondary aluminum smelters. Such ingots would

most likely be shipped on a flat-bed trailer. The exposure geometry is similar to that of the truck

hauling steel products described in Section C.2.8.5. The main differences are that the load is

modeled as a single rectangular solid and that the trailer in the present case is only 28 ft (8.5 m)

long, such a trailer being adequate to transport a 22-ton (20-t) load of ingots. The ingots are

made of Alloy 319, which has a density of 2.79 g/cm3

. The ingots are assumed to completely

cover the 8-ft (2.44-m) wide floor of the trailer. The height of the load above the trailer floor is

calculated by dividing the volume by the area of the floor. The details of the exposure geometry

are shown in Table C.68.

The results of the analysis are presented in Table C.69. The dose rates from 11 of the 12

monoenergetic photon sources are computed by MCNP at the two locations specified in Table

C.68. Because of the strong absorption of low-energy photons by the walls of the truck cab, the

dose rates from the 10 keV source are too low to be statistically meaningful and are therefore not

listed. The average of the dose rates at the two tally points is adopted as the dose rate from each

of the 11 photon sources in this exposure geometry. is calculated on the basis of these 11

sources. Based on these results, Ux for the driver of the aluminum product truck is assigned the

uniform distribution: 0.7 # Ux # 1.3.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-70

Table C.68 Aluminum products truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load 34.34 -853.4 0.0 -121.9 121.9 137.2 171.5

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer floor—aluminuma 3.175 -1219.2 0.0 -121.9 121.9 134.0 137.2

Pavement—concrete 40.64 -40.6 0.0

Tally points (TP)

1 243.8

61.0 168.4

2 335.3

a

 Floor is extruded aluminum honeycomb, estimated effective density = 1 g/cm3

Table C.69 Dose rates to aluminum product truck driver

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 1.85e-20 1.00e-20 1.43e-20 0.42 1.13e-20 6.13e-21 8.72e-21 0.42

0.02 8.63e-18 4.82e-18 6.73e-18 0.40 3.05e-18 1.70e-18 2.38e-18 0.40

0.03 4.86e-16 2.84e-16 3.85e-16 0.37 2.73e-16 1.59e-16 2.16e-16 0.37

0.050 7.64e-15 4.80e-15 6.22e-15 0.32 5.89e-15 3.68e-15 4.79e-15 0.33

0.070 2.57e-14 1.67e-14 2.12e-14 0.30 2.20e-14 1.42e-14 1.81e-14 0.30

0.100 6.90e-14 4.52e-14 5.71e-14 0.29 6.16e-14 4.03e-14 5.10e-14 0.30

0.200 2.46e-13 1.61e-13 2.04e-13 0.30 2.25e-13 1.47e-13 1.86e-13 0.30

0.500 7.28e-13 4.67e-13 5.98e-13 0.31 6.76e-13 4.33e-13 5.55e-13 0.31

1.0 1.46e-12 9.18e-13 1.19e-12 0.32 1.37e-12 8.58e-13 1.11e-12 0.33

2.0 2.85e-12 1.75e-12 2.30e-12 0.34 2.67e-12 1.64e-12 2.16e-12 0.34

5.0 6.64e-12 4.01e-12 5.33e-12 0.35 6.16e-12 3.72e-12 4.94e-12 0.35

Average 0.34 0.34

a

 Coefficient of variation

C.4.9 Auto—Aluminum Engine Block

The exposure geometry of the automobile with an aluminum engine block is the same as that of

the car with a cast iron engine block, the only difference being the weight and material of the

block. The block is made of Alloy 390 and weighs 59 lb (26.8 kg) (GMPartsDirect.com [n/d]). 

The dimensions of the block, as stated in Section C.2.11, are 56 × 40 × 48 cm. The effective

density: = 0.249 g/cm3

.

The results of the analysis are presented in Table C.70, which lists the dose rates from the 12

monoenergetic photon sources. The average of the dose rates at the two tally points is adopted

as the dose rate from each of the sources. is calculated on the basis of all the sources. Based

on these results, Ux for the driver of the automobile with an aluminum engine block is assigned

the uniform distribution: 0.9 # Ux # 1.1.
Appendix C External Exposure Dose Coefficients

20 National Presto Industries, Inc. no longer produces cast aluminum pressure cookers. However, this earlier vessel

is used as a surrogate for a generic cooking utensil.

C-71 NUREG-1640

Figure C.14 Aluminum cooking pot

Table C.70 Dose rates to driver of automobile with aluminum engine block

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.010 2.74e-34 2.31e-34 2.53e-34 0.12 2.14e-34 1.81e-34 1.98e-34 0.12

0.015 1.01e-31 9.77e-32 9.94e-32 0.02 8.06e-32 7.77e-32 7.92e-32 0.03

0.020 1.14e-22 1.07e-22 1.11e-22 0.04 9.85e-23 9.22e-23 9.54e-23 0.05

0.03 3.18e-17 2.81e-17 3.00e-17 0.09 2.89e-17 2.56e-17 2.73e-17 0.09

0.050 6.76e-15 5.77e-15 6.27e-15 0.11 6.28e-15 5.36e-15 5.82e-15 0.11

0.070 2.78e-14 2.36e-14 2.57e-14 0.12 2.70e-14 2.30e-14 2.50e-14 0.11

0.100 6.52e-14 5.55e-14 6.04e-14 0.11 6.33e-14 5.39e-14 5.86e-14 0.11

0.200 1.76e-13 1.51e-13 1.64e-13 0.11 1.71e-13 1.46e-13 1.59e-13 0.11

0.500 4.31e-13 3.68e-13 4.00e-13 0.11 4.18e-13 3.57e-13 3.88e-13 0.11

1.0 7.62e-13 6.49e-13 7.06e-13 0.11 7.42e-13 6.32e-13 6.87e-13 0.11

2.0 1.27e-12 1.08e-12 1.18e-12 0.11 1.24e-12 1.05e-12 1.15e-12 0.12

5.0 2.44e-12 2.07e-12 2.26e-12 0.12 2.34e-12 1.98e-12 2.16e-12 0.12

Average 0.10 0.10

a

 Coefficient of variation

C.4.10 Aluminum Cooking Pot

The aluminum cooking pot is based on a 4-qt

(3.8-L) Presto cast aluminum pressure

cooker.20 The pot is assumed to be made of

Alloy 383, which has a density of 2.74 g/cm3

. 

A schematic diagram of this utensil is shown in

Figure C.14. Like the large and small metal

object exposure geometries, this generic

scenario utilizes rotational symmetry. The pot

is in a cylindrical concrete room, 2 m high and

4 m in diameter. The center of the pot is 1 m

above the floor. The dose rates are calculated

at a distance of 1 m from the center of the pot,

at a height of 1 m above the floor. The

rotational symmetry enables MCNP to utilize

the ring detector for greater computational

efficiency. Since the exposed individual would be facing the pot, the dose calculations are based

on the anteroposterior (AP) irradiation geometry. The details of the exposure geometry for this

scenario are presented in Table C.71.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-72

Table C.71 Cooking pot exposure geometry (cylindrical coordinates) (cm)

Location Thickness

r Z

Min Max Min Max

Pot

Apex of cone

(1⁄2-angle = 4/)

Outside — — 0.0 

Inside — — 7.168

Bottom 0.5 — — 142.677 143.177

Sides 0.5 — — 142.677 155.877

Room

Concrete

Wall—cylinder

3 MFPs

200 rmin + 3 MFPs 51.237 301.237

Floor—slab zmax ! 3 MFPs 51.237

Ceiling—slab 301.237 zmax + 3 MFPs

moist air cylinder 0 200 51.237 301.237

Tally: ring detector 100 151.237

The results of the analysis are presented in Table C.72, which lists the dose rates from the 12

monoenergetic photon sources. Since the doses are calculated at a single distance, there is no

basis for determining uncertainty based on variation of location. Ux for aluminum cookware is

therefore assigned the fixed value, Ux = 1.

Table C.72 Dose rates from aluminum cookware

Energy (MeV) EDE (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

0.010 2.35e-18 1.84e-18

0.015 2.65e-17 2.11e-17

0.020 1.02e-16 8.81e-17

0.030 4.87e-16 4.43e-16

0.050 2.04e-15 1.89e-15

0.070 3.73e-15 3.62e-15

0.100 6.06e-15 5.88e-15

0.200 1.30e-14 1.27e-14

0.500 3.03e-14 2.94e-14

1.0 5.34e-14 5.20e-14

2.0 8.90e-14 8.69e-14

5.0 1.72e-13 1.66e-13

C.5 Concrete

The two external exposure geometries in the concrete analysis are based on those in the analyses

of other materials. Because of differences in size and materials, however, new MCNP

calculations of dose rates are performed for these scenarios. Only the features which are unique

to the concrete analysis are discussed in the next two sections.
Appendix C External Exposure Dose Coefficients

C-73 NUREG-1640

C.5.1 Concrete Pile

The concrete pile exposure geometry is similar to the exposure geometries for piles of scrap

metal. The size of the pile is assumed to be 2,000 t—one week’s production at a facility that

processes a nominal 100 kt/y—which is comparable to the rate of clearance from a BWR or

PWR nuclear power plant during dismantlement. The bulk density of the concrete rubble can

vary greatly. For the purpose of the present analysis, we assume that the rubble would be

sufficiently compacted to enable a 20-t load to be shipped in one large truck-trailer. As shown in

Section C.5.2, this corresponds to a bulk density of 0.4 g/cm3

. The radius of this pile, as

calculated by Equation C.1, is 3.37 m.

The results of the concrete rubble pile analysis are presented in Table C.73. The dose rates from

the 12 monoenergetic photon sources are computed by MCNP at distances of 100 cm and

500 cm from the edge of the pile. The average effective coefficient of variation, which is listed

at the bottom of the table, was calculated in the same way as in the analysis of the copper scrap

pile described in Section C.3.1, again omitting the 10 keV dose rates. Based on these results, Ux

for concrete processing is assigned a uniform distribution: 0.6 # Ux # 1.4.

Table C.73 Dose rates from pile of concrete rubble

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

100 cm 500 cm xo (cm) Ao 200 cm FD 100 cm 500 cm xo (cm) Ao 200 cm FD

0.01 1.20e-16 3.10e-18 23.40 7.04e-13 2.26e-17 5.85e-17 9.98e-17 2.58e-18 23.36 5.86e-13 1.88e-17 4.86e-17

0.015 1.84e-15 3.05e-16 -174.69 1.39e-10 9.89e-16 7.68e-16 1.24e-15 2.05e-16 -174.08 9.31e-11 6.66e-16 5.18e-16

0.02 8.02e-15 2.12e-15 -323.28 1.44e-09 5.25e-15 2.95e-15 5.65e-15 1.49e-15 -322.26 1.01e-09 3.69e-15 2.08e-15

0.030 4.51e-14 1.56e-14 -471.18 1.47e-08 3.27e-14 1.48e-14 3.73e-14 1.28e-14 -465.72 1.19e-08 2.69e-14 1.23e-14

0.050 2.57e-13 1.01e-13 -572.08 1.16e-07 1.95e-13 7.80e-14 2.45e-13 9.55e-14 -564.78 1.08e-07 1.85e-13 7.48e-14

0.070 6.32e-13 2.58e-13 -607.81 3.17e-07 4.85e-13 1.87e-13 6.38e-13 2.59e-13 -602.37 3.15e-07 4.89e-13 1.90e-13

0.100 1.37e-12 5.69e-13 -625.05 7.20e-07 1.06e-12 4.01e-13 1.37e-12 5.69e-13 -625.05 7.20e-07 1.06e-12 4.01e-13

0.200 4.09e-12 1.70e-12 -625.83 2.15e-06 3.16e-12 1.20e-12 4.09e-12 1.70e-12 -625.83 2.15e-06 3.16e-12 1.20e-12

0.500 1.25e-11 5.11e-12 -609.18 6.29e-06 9.60e-12 3.70e-12 1.24e-11 5.07e-12 -609.36 6.24e-06 9.53e-12 3.67e-12

1.0 2.72e-11 1.10e-11 -598.70 1.33e-05 2.08e-11 8.10e-12 2.69e-11 1.09e-11 -600.58 1.32e-05 2.06e-11 8.00e-12

2.0 5.76e-11 2.33e-11 -598.94 2.81e-05 4.41e-11 1.72e-11 5.76e-11 2.33e-11 -598.94 2.81e-05 4.41e-11 1.72e-11

5.0 1.48e-10 6.01e-11 -602.67 7.31e-05 1.13e-10 4.40e-11 1.48e-10 6.00e-11 -601.06 7.27e-05 1.13e-10 4.40e-11

Averagea 1.75e-11 0.39b 1.75e-11 0.39b

a

 Omits 0.010 MeV values—see text

b

 Average effective coefficient of variation—see text

C.5.2 Concrete Truck

The 22-ton (20-t) load of concrete rubble is assumed to be carried in an aluminum trailer. The

inside of the trailer is 40 ft long × 8 ft wide × 66 inches high (12.19× 2.44 × 1.68 m), with a

calculated volume of 1760 ft3

 (49.84 m3). Assuming that the rubble just fills the trailer, it would

have a bulk density of 0.40 g/cm3

. The cab of the truck is the same as that of the truck hauling

steel products, described in Section C.2.8.5. The detailed exposure geometry is described in

Table C.74.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-74

Table C.74 Concrete truck driver exposure geometry (cm)

Location Thickness

XYZ

Min Max Min Max Min Max

Load -1219.2 0.0 -121.9 121.9 137.2 304.8

Truck cab—aluminum 0.3175 153.0 363.9 -121.9 121.9 66.5 245.4

Trailer—

aluminum

floor 0.635 -1219.2 0.0 -121.9 121.9 136.5 137.2

nose&taila 0.4826 -1219.2 0.0 -121.9 121.9 137.2 304.8

sidesb 0.4064 -1219.2 0.0 -121.9 121.9 137.2 304.8

Pavement—concrete 0.0

Tally points

1 243.8

61.0 168.4

2 335.3

a x-min and x-max refer to tail and nose, respectively 

b y-min and y-max refer to right and left sides, respectively

The results of the analysis are presented in Table C.75. The dose rates from 11 of the 12

monoenergetic photon sources are computed by MCNP at the two locations specified in Table

C.74. Because of the strong absorption of low-energy photons by the walls of the truck cab, the

dose rates from the 10 keV source are too low to be statistically meaningful and are therefore not

listed. The average of the dose rates at the two tally points is adopted as the dose rate from each

of the 11 photon sources in this exposure geometry. is calculated on the basis of these 11

sources. Based on these results, Ux for the truck driver transporting concrete rubble is assigned a

uniform distribution: 0.7 # Ux # 1.3.

Table C.75 Dose rates to concrete rubble truck driver

Energy

(MeV)

Effective dose equivalent (Sv/s per Bq/g) Effective dose (Sv/s per Bq/g)

TP 1 TP 2 Mean Cv

a TP 1 TP 2 Mean Cva

0.015 7.72e-24 4.47e-24 6.10e-24 0.38 6.33e-23 3.00e-23 4.67e-23 0.50

0.020 8.05e-19 5.11e-19 6.58e-19 0.32 2.91e-19 1.84e-19 2.38e-19 0.32

0.03 7.34e-16 4.64e-16 5.99e-16 0.32 4.13e-16 2.60e-16 3.37e-16 0.32

0.050 2.61e-14 1.66e-14 2.14e-14 0.31 2.02e-14 1.28e-14 1.65e-14 0.32

0.070 8.91e-14 5.76e-14 7.34e-14 0.30 7.62e-14 4.91e-14 6.27e-14 0.31

0.100 2.17e-13 1.40e-13 1.79e-13 0.31 1.94e-13 1.25e-13 1.60e-13 0.31

0.200 6.76e-13 4.43e-13 5.60e-13 0.29 6.19e-13 4.06e-13 5.13e-13 0.29

0.500 1.95e-12 1.25e-12 1.60e-12 0.31 1.81e-12 1.17e-12 1.49e-12 0.30

1.0 3.98e-12 2.54e-12 3.26e-12 0.31 3.73e-12 2.38e-12 3.06e-12 0.31

2.0 7.85e-12 4.98e-12 6.42e-12 0.32 7.38e-12 4.68e-12 6.03e-12 0.32

5.0 1.84e-11 1.17e-11 1.51e-11 0.31 1.70e-11 1.08e-11 1.39e-11 0.32

Average 0.32 0.33

a

 Coefficient of variation
Appendix C External Exposure Dose Coefficients

C-75 NUREG-1640

C.6 External Exposure Dose Coefficients for Individual Radionuclides

The external exposure dose coefficients for the individual radionuclides are listed in the

following tables, in units of :Sv/h per Bq/g of the radiation source in each exposure geometry. 

These external exposure dose coefficients serve as input parameters to the analyses of doses

from external exposure in the various exposure scenarios. The actual radionuclide

concentrations in the different materials are calculated in the course of these analyses, taking into

account radioactive decay, mixing with other materials, and partitioning during the melting and

refining of scrap metals. The resulting mass-based doses reported in the Chapters 2 – 6 of the

main report and in Appendices F – I are normalized to a specific activity of 1 Bq/g in the cleared

material. 

In the interest of a uniform presentation, all 115 radionuclides addressed by the radiological

assessments are listed in the tables. Some coefficients are listed as zero. As discussed in the

introductory paragraph of this appendix, the dose coefficients for 3 radionuclides—H-3, Ca-41

and Mn-53—are not assessed. Certain other nuclides emit only low-energy radiation which

would be effectively absorbed by the shielding material in some exposure geometries, such as

the cab of a truck which encloses the driver.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-76

Table C.76 Effective dose equivalent coefficients for steel scenarios–part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Dust pile Baghouse Large metal

object

Small metal

object

Small object 

on body Scrap truck Slag truck

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.28e-07 8.85e-08 6.41e-08 5.08e-08 1.10e-08 7.60e-10 6.01e-08 1.24e-09 4.41e-09

Na-22 1.72e-01 1.81e-01 1.62e-01 1.68e-02 7.14e-03 5.44e-04 5.94e-04 2.02e-02 1.26e-02

P-32 3.44e-04 2.43e-04 1.82e-04 1.91e-05 2.07e-05 1.52e-06 2.79e-05 3.67e-05 1.81e-05

S-35 1.31e-07 1.35e-07 7.21e-08 5.33e-08 1.14e-08 8.32e-10 6.08e-08 1.47e-09 8.86e-09

Cl-36 4.77e-05 3.70e-05 3.67e-05 5.39e-06 2.61e-06 1.92e-07 3.94e-08 4.00e-06 3.05e-06

K-40 1.37e-02 1.42e-02 1.28e-02 1.20e-03 4.91e-04 3.78e-05 4.06e-05 1.60e-03 9.25e-04

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 8.32e-07 8.89e-07 4.04e-07 1.74e-07 5.12e-08 3.61e-09 7.03e-16 2.71e-08 5.87e-08

Sc-46 1.65e-01 1.71e-01 1.54e-01 1.57e-02 6.54e-03 5.00e-04 5.49e-04 1.95e-02 1.17e-02

Cr-51 1.80e-03 2.10e-03 1.74e-03 2.19e-04 1.04e-04 7.79e-06 8.51e-06 2.08e-04 1.65e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 6.62e-02 6.89e-02 6.18e-02 6.53e-03 2.79e-03 2.12e-04 2.32e-04 7.86e-03 4.85e-03

Fe-55 3.07e-12 5.36e-12 3.43e-12 7.63e-13 2.39e-13 1.72e-14 2.76e-14 1.65e-13 4.26e-13

Fe-59 9.96e-02 1.04e-01 9.31e-02 9.19e-03 3.77e-03 2.89e-04 3.19e-04 1.18e-02 6.95e-03

Co-56 3.00e-01 3.17e-01 2.84e-01 2.68e-02 1.09e-02 8.39e-04 9.18e-04 3.51e-02 2.08e-02

Co-57 2.29e-03 3.96e-03 2.55e-03 5.69e-04 1.76e-04 1.26e-05 2.04e-05 1.24e-04 3.14e-04

Co-58 7.54e-02 7.89e-02 7.05e-02 7.57e-03 3.27e-03 2.48e-04 2.70e-04 8.92e-03 5.61e-03

Co-60 2.13e-01 2.21e-01 1.99e-01 1.93e-02 7.89e-03 6.06e-04 6.68e-04 2.51e-02 1.47e-02

Ni-59 1.11e-06 1.20e-06 1.05e-06 1.22e-07 5.47e-08 4.13e-09 4.45e-09 1.30e-07 8.96e-08

Ni-63 1.48e-09 1.46e-09 9.95e-10 2.08e-09 1.16e-10 7.90e-12 0.00e+00 2.88e-14 1.90e-11

Zn-65 4.80e-02 4.99e-02 4.49e-02 4.50e-03 1.86e-03 1.43e-04 1.57e-04 5.68e-03 3.38e-03

As-73 1.49e-05 3.77e-05 1.88e-05 2.29e-05 1.12e-06 7.69e-08 2.56e-07 5.05e-09 1.89e-06

Se-75 1.68e-02 2.12e-02 1.66e-02 2.36e-03 1.04e-03 7.72e-05 9.12e-05 1.76e-03 1.68e-03

Sr-85 3.43e-02 3.68e-02 3.23e-02 3.74e-03 1.68e-03 1.27e-04 1.37e-04 3.98e-03 2.75e-03

Sr-89 2.71e-04 1.85e-04 1.35e-04 1.46e-05 1.43e-05 1.06e-06 2.40e-08 1.27e-04 1.51e-05

Sr-90 7.56e-04 5.09e-04 4.07e-04 3.97e-05 4.11e-05 3.07e-06 1.14e-11 8.08e-05 3.79e-05

Y-91 5.85e-04 5.25e-04 4.25e-04 4.30e-05 2.67e-05 2.01e-06 9.69e-07 6.73e-05 3.67e-05

Zr-93 1.72e-09 1.70e-09 1.16e-09 2.43e-09 1.35e-10 9.25e-12 0.00e+00 9.57e-14 2.27e-11

Zr-95 5.67e-02 5.92e-02 5.30e-02 5.72e-03 2.47e-03 1.88e-04 2.04e-04 6.73e-03 4.23e-03

Nb-93m 1.33e-07 3.51e-07 1.73e-07 1.00e-06 1.19e-08 8.18e-10 7.31e-09 3.54e-18 4.39e-12

Nb-94 1.22e-01 1.27e-01 1.14e-01 1.22e-02 5.22e-03 3.98e-04 4.33e-04 1.45e-02 9.02e-03

Nb-95 5.96e-02 6.22e-02 5.56e-02 5.97e-03 2.58e-03 1.96e-04 2.13e-04 7.07e-03 4.42e-03

Mo-93 7.15e-07 1.90e-06 9.38e-07 5.42e-06 6.43e-08 4.41e-09 3.97e-08 0.00e+00 6.60e-12

Tc-97 9.54e-07 2.54e-06 1.25e-06 6.82e-06 8.36e-08 5.73e-09 4.72e-08 0.00e+00 3.41e-11

Tc-97m 4.52e-06 9.56e-06 5.36e-06 7.99e-06 3.67e-07 2.57e-08 8.18e-08 7.13e-08 5.22e-07

Tc-99 1.68e-06 1.11e-06 9.07e-07 3.14e-07 1.47e-07 1.05e-08 4.07e-07 7.06e-08 7.57e-08

Ru-103 3.43e-02 3.69e-02 3.23e-02 3.75e-03 1.69e-03 1.27e-04 1.38e-04 3.98e-03 2.76e-03

Ru-106 1.70e-02 1.70e-02 1.52e-02 1.67e-03 7.91e-04 5.99e-05 5.70e-05 1.99e-03 1.24e-03

Ag-108m 1.17e-01 1.24e-01 1.10e-01 1.23e-02 5.45e-03 4.13e-04 4.47e-04 1.38e-02 9.11e-03

Ag-110m 2.17e-01 2.27e-01 2.03e-01 2.11e-02 8.96e-03 6.84e-04 7.46e-04 2.57e-02 1.58e-02

Cd-109 3.39e-05 7.43e-05 4.10e-05 4.26e-05 2.70e-06 1.89e-07 5.22e-07 3.67e-07 4.49e-06

Sn-113 1.61e-02 1.80e-02 1.53e-02 1.89e-03 8.67e-04 6.52e-05 7.05e-05 1.89e-03 1.39e-03

Sb-124 1.52e-01 1.59e-01 1.43e-01 1.41e-02 5.87e-03 4.50e-04 4.90e-04 1.78e-02 1.08e-02

Sb-125 2.90e-02 3.13e-02 2.74e-02 3.21e-03 1.42e-03 1.07e-04 1.16e-04 3.39e-03 2.34e-03

Te-123m 3.75e-03 5.74e-03 3.99e-03 7.35e-04 2.74e-04 2.00e-05 2.76e-05 2.97e-04 4.64e-04

Te-127m 3.32e-04 3.68e-04 3.10e-04 6.10e-05 1.81e-05 1.36e-06 1.47e-06 3.73e-05 2.73e-05

I-125 1.99e-05 5.26e-05 2.61e-05 8.99e-05 1.51e-06 1.03e-07 5.09e-07 3.72e-12 3.79e-07

I-129 1.61e-05 4.21e-05 2.09e-05 6.26e-05 1.21e-06 8.21e-08 3.73e-07 7.44e-10 5.75e-07

I-131 2.38e-02 2.66e-02 2.27e-02 2.74e-03 1.27e-03 9.58e-05 1.04e-04 2.79e-03 2.05e-03

Cs-134 1.19e-01 1.24e-01 1.11e-01 1.21e-02 5.25e-03 3.99e-04 4.33e-04 1.40e-02 8.94e-03

Cs-135 1.30e-06 1.45e-06 1.10e-06 3.78e-07 7.83e-08 5.54e-09 0.00e+00 4.46e-08 8.46e-08

Cs-137 4.22e-02 4.44e-02 3.95e-02 4.36e-03 1.91e-03 1.45e-04 1.57e-04 5.00e-03 3.22e-03

Ba-133 1.98e-02 2.30e-02 1.91e-02 2.56e-03 1.12e-03 8.39e-05 9.34e-05 2.28e-03 1.79e-03

Ce-139 3.93e-03 5.90e-03 4.15e-03 7.88e-04 2.84e-04 2.08e-05 2.82e-05 3.23e-04 4.75e-04

Ce-141 1.72e-03 2.77e-03 1.86e-03 3.75e-04 1.29e-04 9.37e-06 1.37e-05 1.22e-04 2.22e-04

Ce-144 4.05e-03 3.74e-03 3.34e-03 3.65e-04 1.80e-04 1.36e-05 1.01e-05 4.45e-04 2.58e-04

Pm-147 5.09e-07 5.88e-07 2.77e-07 1.26e-07 3.08e-08 2.17e-09 5.95e-10 1.22e-08 3.65e-08

Sm-151 5.53e-09 8.02e-09 3.45e-09 1.08e-08 3.13e-10 2.14e-11 4.33e-11 1.75e-13 8.55e-11
Appendix C External Exposure Dose Coefficients

Table C.76 Effective dose equivalent coefficients for steel scenarios–part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Dust pile Baghouse Large metal

object

Small metal

object

Small object 

on body Scrap truck Slag truck

C-77 NUREG-1640

Eu-152 8.90e-02 9.40e-02 8.36e-02 8.74e-03 3.61e-03 2.76e-04 3.05e-04 1.04e-02 6.47e-03

Eu-154 8.75e-02 9.20e-02 8.21e-02 8.50e-03 3.50e-03 2.67e-04 2.96e-04 1.03e-02 6.30e-03

Eu-155 5.54e-04 1.13e-03 6.53e-04 2.56e-04 4.41e-05 3.11e-06 6.47e-06 1.21e-05 8.30e-05

Gd-153 7.13e-04 1.46e-03 8.43e-04 4.23e-04 5.67e-05 4.00e-06 8.54e-06 1.58e-05 1.03e-04

Tb-160 8.75e-02 9.20e-02 8.20e-02 8.57e-03 3.58e-03 2.74e-04 3.02e-04 1.03e-02 6.37e-03

Tm-170 7.39e-05 9.34e-05 5.54e-05 2.04e-05 5.11e-06 3.69e-07 3.05e-07 5.61e-06 6.72e-06

Tm-171 1.79e-06 4.43e-06 2.24e-06 2.40e-06 1.35e-07 9.31e-09 2.94e-08 1.51e-09 2.38e-07

Ta-182 1.00e-01 1.05e-01 9.40e-02 9.64e-03 3.88e-03 2.97e-04 3.31e-04 1.17e-02 7.11e-03

W-181 1.31e-04 3.23e-04 1.64e-04 1.57e-04 9.99e-06 6.89e-07 2.12e-06 2.12e-07 1.85e-05

W-185 5.78e-06 3.66e-06 2.91e-06 7.91e-07 4.11e-07 2.95e-08 8.09e-07 2.86e-07 2.68e-07

Os-185 4.88e-02 5.15e-02 4.57e-02 5.18e-03 2.20e-03 1.67e-04 1.82e-04 5.75e-03 3.72e-03

Ir-192 4.98e-02 5.61e-02 4.76e-02 5.82e-03 2.68e-03 2.02e-04 2.20e-04 5.77e-03 4.33e-03

Tl-204 4.01e-05 3.11e-05 2.32e-05 7.26e-06 2.70e-06 1.95e-07 3.66e-06 2.62e-06 2.24e-06

Pb-210 9.39e-05 5.91e-05 5.44e-05 1.43e-05 5.95e-06 4.37e-07 7.58e-08 8.46e-06 4.20e-06

Bi-207 1.17e-01 1.23e-01 1.10e-01 1.16e-02 4.87e-03 3.71e-04 4.08e-04 1.38e-02 8.58e-03

Po-210 7.65e-07 7.97e-07 7.14e-07 7.61e-08 3.26e-08 2.48e-09 2.70e-09 9.08e-08 5.64e-08

Ra-226 1.38e-01 1.46e-01 1.30e-01 1.30e-02 5.42e-03 4.15e-04 4.53e-04 1.61e-02 9.89e-03

Ra-228 6.72e-02 7.08e-02 6.30e-02 6.57e-03 2.77e-03 2.12e-04 2.32e-04 7.91e-03 4.91e-03

Ac-227 2.08e-02 2.44e-02 2.00e-02 2.71e-03 1.17e-03 8.75e-05 9.92e-05 2.30e-03 1.89e-03

Th-228 1.17e-01 1.26e-01 1.12e-01 1.04e-02 4.20e-03 3.23e-04 3.53e-04 1.34e-02 8.17e-03

Th-229 1.50e-02 1.74e-02 1.45e-02 1.97e-03 7.76e-04 5.82e-05 6.81e-05 1.63e-03 1.30e-03

Th-230 5.11e-06 8.60e-06 5.57e-06 2.16e-06 3.66e-07 2.65e-08 4.81e-08 3.29e-07 6.35e-07

Th-232 1.47e-06 3.01e-06 1.72e-06 1.23e-06 1.13e-07 8.01e-09 2.01e-08 4.81e-08 2.01e-07

Pa-231 1.66e-03 1.98e-03 1.61e-03 2.25e-04 9.79e-05 7.33e-06 8.28e-06 1.87e-04 1.56e-04

U-232 3.40e-06 5.74e-06 3.72e-06 1.84e-06 2.46e-07 1.78e-08 3.43e-08 2.17e-07 4.14e-07

U-233 6.86e-06 9.37e-06 6.97e-06 1.69e-06 4.42e-07 3.26e-08 4.54e-08 6.49e-07 7.22e-07

U-234 1.23e-06 2.40e-06 1.42e-06 1.21e-06 9.67e-08 6.86e-09 1.74e-08 4.55e-08 1.59e-07

U-235 5.31e-03 7.69e-03 5.52e-03 1.08e-03 3.72e-04 2.73e-05 3.68e-05 4.48e-04 6.16e-04

U-236 5.35e-07 1.12e-06 6.35e-07 8.78e-07 4.31e-08 3.04e-09 1.01e-08 1.40e-08 6.43e-08

U-238 2.07e-03 1.95e-03 1.74e-03 2.09e-04 9.49e-05 7.16e-06 5.82e-06 2.30e-04 1.37e-04

Np-237 1.05e-02 1.28e-02 1.03e-02 1.47e-03 6.21e-04 4.64e-05 5.42e-05 1.15e-03 1.01e-03

Pu-236 6.31e-07 1.14e-06 7.04e-07 1.16e-06 4.39e-08 3.13e-09 1.12e-08 3.50e-08 5.60e-08

Pu-238 2.93e-07 6.37e-07 3.53e-07 9.82e-07 2.34e-08 1.64e-09 8.33e-09 7.76e-09 2.26e-08

Pu-239 2.08e-06 2.76e-06 2.09e-06 7.54e-07 1.25e-07 9.26e-09 1.45e-08 2.02e-07 2.01e-07

Pu-240 2.72e-07 6.09e-07 3.32e-07 9.40e-07 2.22e-08 1.55e-09 7.95e-09 5.65e-09 2.14e-08

Pu-241 2.22e-08 4.09e-08 2.53e-08 6.91e-09 1.74e-09 1.24e-10 2.20e-10 9.39e-10 3.17e-09

Pu-242 2.44e-07 5.48e-07 2.98e-07 7.85e-07 2.02e-08 1.41e-09 6.83e-09 4.68e-09 2.11e-08

Pu-244 2.43e-02 2.56e-02 2.27e-02 2.48e-03 1.08e-03 8.20e-05 8.78e-05 2.85e-03 1.83e-03

Am-241 7.68e-05 1.88e-04 9.58e-05 9.55e-05 5.84e-06 4.02e-07 1.26e-06 1.56e-07 1.07e-05

Am-242m 4.33e-04 6.03e-04 4.40e-04 9.00e-05 2.48e-05 1.82e-06 2.73e-06 3.53e-05 4.41e-05

Am-243 5.82e-03 8.27e-03 5.98e-03 1.18e-03 3.84e-04 2.83e-05 3.92e-05 5.09e-04 6.46e-04

Cm-242 3.84e-07 7.24e-07 4.35e-07 1.13e-06 2.66e-08 1.89e-09 8.86e-09 2.07e-08 2.33e-08

Cm-243 4.18e-03 5.67e-03 4.24e-03 7.00e-04 2.73e-04 2.02e-05 2.58e-05 3.95e-04 4.50e-04

Cm-244 3.26e-07 6.09e-07 3.69e-07 9.57e-07 2.25e-08 1.60e-09 7.52e-09 1.82e-08 1.94e-08

Cm-245 1.67e-03 2.91e-03 1.86e-03 4.54e-04 1.28e-04 9.18e-06 1.52e-05 8.65e-05 2.28e-04

Cm-246 1.17e-07 3.09e-07 1.52e-07 7.49e-07 9.97e-09 6.83e-10 5.27e-09 9.96e-13 1.69e-09

Cm-247 1.99e-02 2.24e-02 1.90e-02 2.37e-03 1.07e-03 8.07e-05 8.84e-05 2.31e-03 1.73e-03

Cm-248 1.07e-07 2.84e-07 1.40e-07 6.93e-07 9.18e-09 6.29e-10 4.87e-09 8.06e-13 1.46e-09

Bk-249 6.62e-08 7.32e-08 4.80e-08 2.21e-08 3.81e-09 2.74e-10 1.63e-10 3.68e-09 4.78e-09

Cf-248 3.93e-07 8.89e-07 4.83e-07 1.12e-06 3.22e-08 2.24e-09 9.40e-09 5.56e-09 3.56e-08

Cf-249 1.95e-02 2.21e-02 1.87e-02 2.30e-03 1.07e-03 8.03e-05 8.73e-05 2.28e-03 1.71e-03

Cf-250 1.32e-07 3.51e-07 1.73e-07 8.43e-07 1.11e-08 7.62e-10 5.55e-09 3.36e-13 9.00e-10

Cf-251 2.99e-03 4.49e-03 3.15e-03 5.99e-04 2.11e-04 1.54e-05 2.17e-05 2.35e-04 3.58e-04

Cf-252 3.82e-07 8.06e-07 4.56e-07 9.30e-07 3.06e-08 2.15e-09 8.03e-09 1.11e-08 3.57e-08

Cf-254 1.41e+00 1.47e+00 1.32e+00 1.37e-01 5.76e-02 4.40e-03 4.82e-03 1.67e-01 1.02e-01

Es-254 7.32e-02 7.61e-02 6.83e-02 7.01e-03 2.91e-03 2.23e-04 2.45e-04 8.67e-03 5.22e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-78

Table C.77 Effective dose equivalent coefficients for steel scenarios–part 2 (:Sv/h per Bq/g)

Nuclide Atop dust

truck

Dry bulk

trailer

Dust in dump trailer Truck with

I-beams

Cement

basement

House with

steel studs

Auto engine

Driver’s seat Sleeper block

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 2.89e-08 1.88e-09 4.34e-09 7.85e-09 1.07e-08 4.00e-07 3.82e-08 1.09e-08

Na-22 1.04e-01 6.75e-03 1.48e-02 2.67e-02 1.33e-02 5.75e-01 9.95e-03 1.25e-02

P-32 1.14e-04 8.42e-06 1.84e-05 3.23e-05 3.10e-05 6.59e-04 3.65e-05 3.50e-05

S-35 3.33e-08 2.22e-09 5.08e-09 9.16e-09 1.03e-08 6.26e-07 4.18e-08 1.15e-08

Cl-36 2.28e-05 1.71e-06 3.75e-06 6.63e-06 3.63e-06 1.21e-04 5.78e-06 3.80e-06

K-40 8.24e-03 5.07e-04 1.11e-03 2.03e-03 9.89e-04 4.24e-02 6.70e-04 8.53e-04

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 2.16e-07 1.60e-08 3.53e-08 6.25e-08 5.36e-08 3.34e-06 1.92e-07 5.67e-08

Sc-46 1.00e-01 6.35e-03 1.39e-02 2.52e-02 1.25e-02 5.38e-01 9.01e-03 1.15e-02

Cr-51 1.10e-03 8.23e-05 1.79e-04 3.14e-04 1.60e-04 7.50e-03 1.61e-04 1.80e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 4.02e-02 2.61e-03 5.71e-03 1.03e-02 5.14e-03 2.21e-01 3.87e-03 4.90e-03

Fe-55 2.06e-12 1.68e-13 3.62e-13 6.27e-13 2.81e-13 2.52e-11 6.71e-13 3.67e-13

Fe-59 6.04e-02 3.78e-03 8.26e-03 1.51e-02 7.37e-03 3.19e-01 5.17e-03 6.61e-03

Co-56 1.82e-01 1.13e-02 2.46e-02 4.52e-02 2.18e-02 9.51e-01 1.49e-02 1.90e-02

Co-57 1.53e-03 1.24e-04 2.67e-04 4.63e-04 2.08e-04 1.86e-02 4.95e-04 2.69e-04

Co-58 4.57e-02 3.00e-03 6.58e-03 1.18e-02 5.93e-03 2.56e-01 4.56e-03 5.74e-03

Co-60 1.29e-01 8.02e-03 1.75e-02 3.20e-02 1.56e-02 6.75e-01 1.08e-02 1.38e-02

Ni-59 6.74e-07 4.67e-08 1.03e-07 1.82e-07 9.28e-08 4.06e-06 7.86e-08 9.57e-08

Ni-63 1.58e-10 5.85e-12 1.70e-11 3.24e-11 4.24e-11 7.04e-09 2.30e-10 1.35e-11

Zn-65 2.92e-02 1.84e-03 4.02e-03 7.31e-03 3.59e-03 1.55e-01 2.56e-03 3.26e-03

As-73 8.97e-06 5.17e-07 1.25e-06 2.31e-06 1.00e-06 2.48e-04 6.08e-06 9.38e-07

Se-75 1.05e-02 7.98e-04 1.73e-03 3.02e-03 1.51e-03 8.07e-02 1.85e-03 1.76e-03

Sr-85 2.07e-02 1.43e-03 3.15e-03 5.60e-03 2.85e-03 1.24e-01 2.41e-03 2.94e-03

Sr-89 8.46e-05 6.24e-06 1.36e-05 2.39e-05 2.12e-05 5.31e-04 2.73e-05 2.11e-05

Sr-90 2.57e-04 1.84e-05 4.03e-05 7.11e-05 6.41e-05 1.33e-03 7.23e-05 6.15e-05

Y-91 2.73e-04 1.80e-05 3.94e-05 7.09e-05 4.50e-05 1.53e-03 4.46e-05 4.25e-05

Zr-93 1.86e-10 7.18e-12 2.05e-11 3.88e-11 4.98e-11 8.22e-09 2.69e-10 1.73e-11

Zr-95 3.44e-02 2.26e-03 4.96e-03 8.92e-03 4.48e-03 1.93e-01 3.45e-03 4.35e-03

Nb-93m 7.95e-11 5.18e-13 3.27e-12 5.86e-12 7.36e-11 2.48e-06 1.45e-10 2.56e-13

Nb-94 7.41e-02 4.84e-03 1.06e-02 1.91e-02 9.56e-03 4.11e-01 7.28e-03 9.18e-03

Nb-95 3.61e-02 2.37e-03 5.20e-03 9.35e-03 4.69e-03 2.02e-01 3.59e-03 4.53e-03

Mo-93 2.73e-10 1.04e-13 5.88e-12 8.93e-12 3.52e-10 1.34e-05 6.05e-10 7.38e-17

Tc-97 1.03e-09 8.60e-13 2.68e-11 4.38e-11 9.47e-10 1.75e-05 1.74e-09 3.32e-15

Tc-97m 2.36e-06 1.86e-07 4.04e-07 7.09e-07 3.09e-07 5.46e-05 1.07e-06 3.95e-07

Tc-99 5.03e-07 3.82e-08 8.38e-08 1.47e-07 1.64e-07 4.44e-06 4.84e-07 1.98e-07

Ru-103 2.07e-02 1.44e-03 3.16e-03 5.62e-03 2.86e-03 1.25e-01 2.43e-03 2.95e-03

Ru-106 9.81e-03 6.62e-04 1.45e-03 2.60e-03 1.38e-03 5.56e-02 1.14e-03 1.36e-03

Ag-108m 7.10e-02 4.80e-03 1.05e-02 1.88e-02 9.52e-03 4.13e-01 7.75e-03 9.57e-03

Ag-110m 1.32e-01 8.49e-03 1.86e-02 3.36e-02 1.67e-02 7.21e-01 1.24e-02 1.57e-02

Cd-109 2.00e-05 1.53e-06 3.34e-06 5.91e-06 2.52e-06 4.28e-04 9.73e-06 3.20e-06

Sn-113 9.77e-03 7.07e-04 1.55e-03 2.72e-03 1.39e-03 6.28e-02 1.29e-03 1.51e-03

Sb-124 9.19e-02 5.82e-03 1.27e-02 2.32e-02 1.13e-02 4.91e-01 8.06e-03 1.02e-02

Sb-125 1.76e-02 1.21e-03 2.67e-03 4.74e-03 2.41e-03 1.06e-01 2.06e-03 2.48e-03

Te-123m 2.44e-03 1.98e-04 4.26e-04 7.37e-04 3.48e-04 2.45e-02 6.19e-04 4.41e-04

Te-127m 1.94e-04 1.39e-05 3.05e-05 5.39e-05 2.83e-05 1.33e-03 2.87e-05 3.03e-05

I-125 2.90e-06 6.11e-08 2.38e-07 4.61e-07 4.97e-07 3.34e-04 2.30e-06 3.95e-08

I-129 3.75e-06 1.14e-07 3.68e-07 7.07e-07 5.40e-07 2.69e-04 2.87e-06 1.24e-07

I-131 1.45e-02 1.04e-03 2.28e-03 4.02e-03 2.05e-03 9.29e-02 1.91e-03 2.21e-03

Cs-134 7.19e-02 4.76e-03 1.04e-02 1.87e-02 9.42e-03 4.06e-01 7.35e-03 9.22e-03

Cs-135 5.83e-07 4.75e-08 9.04e-08 1.59e-07 8.40e-08 4.46e-06 2.84e-07 8.96e-08

Cs-137 2.56e-02 1.71e-03 3.75e-03 6.72e-03 3.39e-03 1.46e-01 2.69e-03 3.36e-03

Ba-133 1.21e-02 8.92e-04 1.95e-03 3.42e-03 1.74e-03 8.28e-02 1.77e-03 1.93e-03

Ce-139 2.54e-03 2.05e-04 4.42e-04 7.65e-04 3.65e-04 2.49e-02 6.19e-04 4.58e-04

Ce-141 1.13e-03 9.21e-05 1.98e-04 3.43e-04 1.59e-04 1.23e-02 3.17e-04 2.04e-04

Ce-144 2.12e-03 1.39e-04 3.03e-04 5.49e-04 3.14e-04 1.20e-02 3.00e-04 2.92e-04

Pm-147 1.48e-07 1.10e-08 2.44e-08 4.31e-08 3.16e-08 2.18e-06 1.17e-07 3.41e-08
Appendix C External Exposure Dose Coefficients

Table C.77 Effective dose equivalent coefficients for steel scenarios–part 2 (:Sv/h per Bq/g)

Nuclide Atop dust

truck

Dry bulk

trailer

Dust in dump trailer Truck with

I-beams

Cement

basement

House with

steel studs

Auto engine

Driver’s seat Sleeper block

C-79 NUREG-1640

Sm-151 4.00e-10 1.62e-11 4.50e-11 8.50e-11 1.04e-10 4.05e-08 5.64e-10 4.15e-11

Eu-152 5.41e-02 3.47e-03 7.58e-03 1.37e-02 6.77e-03 2.98e-01 5.12e-03 6.31e-03

Eu-154 5.32e-02 3.39e-03 7.41e-03 1.34e-02 6.62e-03 2.91e-01 4.95e-03 6.11e-03

Eu-155 3.75e-04 2.93e-05 6.38e-05 1.12e-04 4.79e-05 6.09e-03 1.67e-04 6.17e-05

Gd-153 4.71e-04 3.61e-05 7.92e-05 1.39e-04 6.02e-05 7.93e-03 2.09e-04 7.56e-05

Tb-160 5.32e-02 3.42e-03 7.48e-03 1.35e-02 6.70e-03 2.93e-01 5.05e-03 6.28e-03

Tm-170 3.23e-05 2.41e-06 5.30e-06 9.36e-06 6.40e-06 3.88e-04 1.55e-05 6.97e-06

Tm-171 1.11e-06 6.76e-08 1.59e-07 2.93e-07 1.25e-07 2.87e-05 7.29e-07 1.27e-07

Ta-182 6.09e-02 3.84e-03 8.38e-03 1.53e-02 7.47e-03 3.30e-01 5.49e-03 6.77e-03

W-181 8.42e-05 5.36e-06 1.24e-05 2.28e-05 9.57e-06 2.08e-03 5.45e-05 1.03e-05

W-185 1.69e-06 1.31e-07 2.86e-07 5.01e-07 4.92e-07 1.51e-05 1.21e-06 5.96e-07

Os-185 2.96e-02 1.97e-03 4.32e-03 7.75e-03 3.90e-03 1.70e-01 3.14e-03 3.85e-03

Ir-192 3.04e-02 2.19e-03 4.79e-03 8.45e-03 4.31e-03 1.97e-01 4.06e-03 4.66e-03

Tl-204 1.37e-05 1.03e-06 2.25e-06 3.97e-06 3.24e-06 1.47e-04 7.29e-06 4.07e-06

Pb-210 3.27e-05 2.42e-06 5.31e-06 9.33e-06 8.20e-06 2.20e-04 1.33e-05 8.33e-06

Bi-207 7.10e-02 4.59e-03 1.01e-02 1.82e-02 9.02e-03 3.94e-01 6.87e-03 8.52e-03

Po-210 4.64e-07 3.02e-08 6.63e-08 1.19e-07 5.98e-08 2.57e-06 4.53e-08 5.73e-08

Ra-226 8.34e-02 5.32e-03 1.16e-02 2.11e-02 1.03e-02 4.53e-01 7.60e-03 9.45e-03

Ra-228 4.08e-02 2.63e-03 5.76e-03 1.04e-02 5.16e-03 2.25e-01 3.91e-03 4.85e-03

Ac-227 1.27e-02 9.30e-04 2.03e-03 3.57e-03 1.81e-03 8.94e-02 1.96e-03 2.00e-03

Th-228 7.08e-02 4.41e-03 9.56e-03 1.76e-02 8.40e-03 3.75e-01 5.88e-03 7.25e-03

Th-229 9.17e-03 6.45e-04 1.41e-03 2.50e-03 1.25e-03 6.30e-02 1.33e-03 1.32e-03

Th-230 3.29e-06 2.53e-07 5.51e-07 9.66e-07 4.49e-07 4.26e-05 1.09e-06 5.48e-07

Th-232 9.48e-07 7.04e-08 1.55e-07 2.75e-07 1.20e-07 1.71e-05 4.38e-07 1.48e-07

Pa-231 1.02e-03 7.67e-05 1.67e-04 2.92e-04 1.49e-04 7.28e-03 1.59e-04 1.68e-04

U-232 2.15e-06 1.66e-07 3.63e-07 6.34e-07 2.93e-07 2.81e-05 6.78e-07 3.60e-07

U-233 4.28e-06 3.28e-07 7.12e-07 1.24e-06 6.12e-07 3.88e-05 9.02e-07 7.18e-07

U-234 7.58e-07 5.89e-08 1.29e-07 2.25e-07 9.97e-08 1.29e-05 2.98e-07 1.26e-07

U-235 3.40e-03 2.71e-04 5.85e-04 1.01e-03 4.90e-04 3.21e-02 7.83e-04 6.05e-04

U-236 3.02e-07 2.31e-08 5.07e-08 8.90e-08 3.91e-08 6.36e-06 1.29e-07 4.85e-08

U-238 1.12e-03 7.35e-05 1.61e-04 2.90e-04 1.64e-04 6.47e-03 1.60e-04 1.56e-04

Np-237 6.48e-03 4.85e-04 1.06e-03 1.85e-03 9.34e-04 4.82e-02 1.08e-03 1.06e-03

Pu-236 3.18e-07 2.29e-08 5.05e-08 8.94e-08 4.21e-08 6.21e-06 9.38e-08 4.73e-08

Pu-238 1.14e-07 8.45e-09 1.86e-08 3.28e-08 1.49e-08 3.89e-06 4.36e-08 1.76e-08

Pu-239 1.26e-06 9.32e-08 2.04e-07 3.58e-07 1.77e-07 1.15e-05 2.44e-07 1.99e-07

Pu-240 1.04e-07 7.69e-09 1.70e-08 3.01e-08 1.36e-08 3.78e-06 4.38e-08 1.60e-08

Pu-241 1.50e-08 1.20e-09 2.60e-09 4.52e-09 1.99e-09 2.03e-07 5.51e-09 2.59e-09

Pu-242 1.00e-07 7.56e-09 1.67e-08 2.93e-08 1.31e-08 3.35e-06 4.29e-08 1.59e-08

Pu-244 1.47e-02 9.73e-04 2.13e-03 3.83e-03 1.93e-03 8.35e-02 1.54e-03 1.89e-03

Am-241 4.88e-05 3.11e-06 7.21e-06 1.32e-05 5.54e-06 1.21e-03 3.15e-05 5.98e-06

Am-242m 2.72e-04 1.94e-05 4.22e-05 7.49e-05 3.53e-05 2.57e-03 6.29e-05 3.89e-05

Am-243 3.69e-03 2.84e-04 6.18e-04 1.08e-03 5.24e-04 3.54e-02 8.73e-04 6.23e-04

Cm-242 1.47e-07 1.03e-08 2.27e-08 4.03e-08 1.99e-08 4.17e-06 3.43e-08 2.10e-08

Cm-243 2.64e-03 2.05e-04 4.43e-04 7.72e-04 3.81e-04 2.29e-02 5.51e-04 4.51e-04

Cm-244 1.24e-07 8.75e-09 1.92e-08 3.41e-08 1.68e-08 3.49e-06 2.74e-08 1.79e-08

Cm-245 1.11e-03 8.92e-05 1.93e-04 3.35e-04 1.51e-04 1.39e-02 3.72e-04 1.94e-04

Cm-246 9.11e-09 4.18e-10 1.10e-09 2.07e-09 1.22e-09 2.12e-06 6.68e-09 6.68e-10

Cm-247 1.21e-02 8.75e-04 1.91e-03 3.38e-03 1.72e-03 7.91e-02 1.64e-03 1.86e-03

Cm-248 7.92e-09 3.59e-10 9.47e-10 1.79e-09 1.07e-09 1.95e-06 5.82e-09 5.70e-10

Bk-249 2.62e-08 1.86e-09 4.13e-09 7.30e-09 4.34e-09 3.03e-07 1.10e-08 4.40e-09

Cf-248 1.63e-07 1.27e-08 2.76e-08 4.85e-08 2.14e-08 5.32e-06 7.14e-08 2.67e-08

Cf-249 1.19e-02 8.66e-04 1.89e-03 3.33e-03 1.70e-03 7.77e-02 1.62e-03 1.85e-03

Cf-250 5.58e-09 2.04e-10 5.79e-10 1.10e-09 1.00e-09 2.37e-06 4.40e-09 3.05e-10

Cf-251 1.93e-03 1.53e-04 3.31e-04 5.75e-04 2.74e-04 1.94e-02 4.90e-04 3.38e-04

Cf-252 1.72e-07 1.35e-08 2.93e-08 5.12e-08 2.33e-08 4.63e-06 6.44e-08 2.90e-08

Cf-254 8.57e-01 5.50e-02 1.20e-01 2.18e-01 1.08e-01 4.66e+00 7.97e-02 1.01e-01

Es-254 4.45e-02 2.82e-03 6.18e-03 1.12e-02 5.54e-03 2.39e-01 4.03e-03 5.12e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-80

Table C.78 Effective dose equivalent coefficients for steel scenarios–part 3 (:Sv/h per Bq/g)

Nuclide Diesel truck Hull plate Steel ship

Driver’s seat Sleeper Bunk Lounge area Berthing Mess Operations Deck

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.65e-08 5.62e-09 2.16e-07 4.64e-08 4.29e-09 7.12e-09 3.66e-09 2.01e-07

Na-22 1.64e-02 6.89e-03 1.23e-01 2.48e-02 9.80e-02 1.20e-01 9.62e-02 2.04e-01

P-32 3.64e-05 1.54e-05 3.38e-04 7.42e-05 1.55e-04 1.98e-04 1.53e-04 4.86e-04

S-35 1.76e-08 5.87e-09 2.09e-07 5.00e-08 5.87e-09 9.59e-09 5.19e-09 2.26e-07

Cl-36 4.55e-06 1.74e-06 4.30e-05 9.71e-06 1.65e-05 2.16e-05 1.64e-05 6.36e-05

K-40 1.18e-03 5.12e-04 8.71e-03 1.68e-03 8.29e-03 1.00e-02 8.20e-03 1.52e-02

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 7.89e-08 2.69e-08 8.87e-07 2.09e-07 9.51e-08 1.42e-07 9.47e-08 1.26e-06

Sc-46 1.53e-02 6.51e-03 1.14e-01 2.27e-02 9.53e-02 1.16e-01 9.32e-02 1.91e-01

Cr-51 2.09e-04 8.24e-05 1.69e-03 3.72e-04 8.95e-04 1.14e-03 8.82e-04 2.55e-03

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 6.40e-03 2.69e-03 4.81e-02 9.71e-03 3.73e-02 4.55e-02 3.64e-02 7.89e-02

Fe-55 4.22e-13 1.54e-13 3.93e-12 9.26e-13 8.08e-13 1.18e-12 8.50e-13 5.58e-12

Fe-59 8.96e-03 3.84e-03 6.64e-02 1.30e-02 5.88e-02 7.11e-02 5.77e-02 1.13e-01

Co-56 2.60e-02 1.13e-02 1.93e-01 3.75e-02 1.83e-01 2.21e-01 1.82e-01 3.36e-01

Co-57 3.12e-04 1.14e-04 2.89e-03 6.80e-04 6.10e-04 8.80e-04 6.37e-04 4.12e-03

Co-58 7.42e-03 3.10e-03 5.60e-02 1.14e-02 4.20e-02 5.13e-02 4.09e-02 9.12e-02

Co-60 1.89e-02 8.13e-03 1.39e-01 2.72e-02 1.27e-01 1.53e-01 1.25e-01 2.40e-01

Ni-59 1.18e-07 4.82e-08 9.15e-07 1.93e-07 5.82e-07 7.24e-07 5.68e-07 1.44e-06

Ni-63 8.82e-11 2.26e-11 2.43e-09 5.22e-10 1.34e-13 2.76e-13 0.00e+00 2.97e-09

Zn-65 4.39e-03 1.88e-03 3.26e-02 6.44e-03 2.81e-02 3.40e-02 2.75e-02 5.52e-02

As-73 2.10e-06 6.34e-07 2.10e-05 4.95e-06 4.97e-08 1.03e-07 0.00e+00 3.17e-05

Se-75 2.02e-03 7.84e-04 1.68e-02 3.78e-03 7.65e-03 9.92e-03 7.59e-03 2.51e-02

Sr-85 3.63e-03 1.48e-03 2.81e-02 5.92e-03 1.79e-02 2.23e-02 1.75e-02 4.42e-02

Sr-89 2.52e-05 9.83e-06 2.35e-04 5.22e-05 1.10e-04 1.42e-04 1.09e-04 3.55e-04

Sr-90 7.46e-05 2.96e-05 6.81e-04 1.48e-04 3.66e-04 4.62e-04 3.60e-04 1.05e-03

Y-91 5.40e-05 2.21e-05 4.52e-04 9.50e-05 2.97e-04 3.68e-04 2.93e-04 7.22e-04

Zr-93 1.03e-10 2.65e-11 2.85e-09 6.10e-10 8.39e-13 1.63e-12 2.33e-13 3.47e-09

Zr-95 5.61e-03 2.34e-03 4.24e-02 8.65e-03 3.14e-02 3.85e-02 3.06e-02 6.88e-02

Nb-93m 1.94e-10 4.62e-11 2.76e-07 5.01e-08 0.00e+00 0.00e+00 0.00e+00 2.78e-07

Nb-94 1.19e-02 5.00e-03 8.99e-02 1.82e-02 6.83e-02 8.35e-02 6.66e-02 1.47e-01

Nb-95 5.86e-03 2.45e-03 4.42e-02 8.99e-03 3.32e-02 4.06e-02 3.23e-02 7.20e-02

Mo-93 9.48e-10 2.27e-10 1.49e-06 2.70e-07 0.00e+00 0.00e+00 0.00e+00 1.50e-06

Tc-97 2.35e-09 5.39e-10 1.90e-06 3.59e-07 0.00e+00 0.00e+00 0.00e+00 1.97e-06

Tc-97m 5.05e-07 1.76e-07 6.69e-06 1.51e-06 4.61e-07 7.39e-07 4.43e-07 8.80e-06

Tc-99 2.30e-07 8.63e-08 2.46e-06 5.81e-07 2.80e-07 4.07e-07 2.82e-07 2.81e-06

Ru-103 3.65e-03 1.48e-03 2.82e-02 5.96e-03 1.79e-02 2.22e-02 1.74e-02 4.43e-02

Ru-106 1.72e-03 7.08e-04 1.34e-02 2.78e-03 9.18e-03 1.13e-02 8.98e-03 2.14e-02

Ag-108m 1.20e-02 4.96e-03 9.22e-02 1.92e-02 6.33e-02 7.80e-02 6.17e-02 1.47e-01

Ag-110m 2.07e-02 8.72e-03 1.55e-01 3.12e-02 1.24e-01 1.51e-01 1.21e-01 2.57e-01

Cd-109 4.26e-06 1.45e-06 4.80e-05 1.13e-05 2.84e-06 4.79e-06 2.51e-06 6.55e-05

Sn-113 1.80e-03 7.19e-04 1.42e-02 3.08e-03 8.23e-03 1.04e-02 8.07e-03 2.19e-02

Sb-124 1.37e-02 5.88e-03 1.02e-01 2.03e-02 8.96e-02 1.09e-01 8.86e-02 1.75e-01

Sb-125 3.07e-03 1.25e-03 2.38e-02 5.01e-03 1.53e-02 1.90e-02 1.49e-02 3.74e-02

Te-123m 4.95e-04 1.85e-04 4.44e-03 1.03e-03 1.33e-03 1.84e-03 1.39e-03 6.38e-03

Te-127m 3.67e-05 1.46e-05 3.00e-04 6.52e-05 1.64e-04 2.06e-04 1.61e-04 4.58e-04

I-125 1.23e-06 2.86e-07 3.14e-05 7.07e-06 0.00e+00 0.00e+00 0.00e+00 3.84e-05

I-129 1.33e-06 3.31e-07 2.47e-05 5.62e-06 4.79e-09 7.95e-09 4.09e-09 3.15e-05

I-131 2.65e-03 1.06e-03 2.10e-02 4.53e-03 1.22e-02 1.54e-02 1.20e-02 3.23e-02

Cs-134 1.18e-02 4.92e-03 8.96e-02 1.84e-02 6.54e-02 8.02e-02 6.38e-02 1.45e-01

Cs-135 1.21e-07 4.17e-08 1.35e-06 3.17e-07 1.66e-07 2.44e-07 1.67e-07 1.92e-06

Cs-137 4.27e-03 1.77e-03 3.25e-02 6.70e-03 2.30e-02 2.83e-02 2.24e-02 5.22e-02

Ba-133 2.27e-03 8.99e-04 1.83e-02 4.01e-03 9.85e-03 1.25e-02 9.69e-03 2.78e-02

Ce-139 5.15e-04 1.93e-04 4.59e-03 1.07e-03 1.44e-03 1.98e-03 1.49e-03 6.61e-03

Ce-141 2.31e-04 8.54e-05 2.10e-03 4.92e-04 5.58e-04 7.85e-04 5.86e-04 3.01e-03

Ce-144 3.78e-04 1.57e-04 3.08e-03 6.38e-04 2.22e-03 2.74e-03 2.21e-03 5.03e-03

Pm-147 4.82e-08 1.63e-08 5.37e-07 1.27e-07 5.17e-08 7.82e-08 5.15e-08 7.61e-07
Appendix C External Exposure Dose Coefficients

Table C.78 Effective dose equivalent coefficients for steel scenarios–part 3 (:Sv/h per Bq/g)

Nuclide Diesel truck Hull plate Steel ship

Driver’s seat Sleeper Bunk Lounge area Berthing Mess Operations Deck

C-81 NUREG-1640

Sm-151 2.13e-10 5.57e-11 6.56e-09 1.42e-09 1.39e-12 2.80e-12 3.80e-14 8.01e-09

Eu-152 8.34e-03 3.53e-03 6.27e-02 1.26e-02 5.12e-02 6.23e-02 5.03e-02 1.05e-01

Eu-154 8.14e-03 3.45e-03 6.10e-02 1.22e-02 5.05e-02 6.14e-02 4.95e-02 1.02e-01

Eu-155 7.87e-05 2.74e-05 7.49e-04 1.78e-04 7.45e-05 1.18e-04 7.26e-05 1.06e-03

Gd-153 1.00e-04 3.45e-05 9.70e-04 2.30e-04 9.53e-05 1.50e-04 9.42e-05 1.38e-03

Tb-160 8.28e-03 3.49e-03 6.22e-02 1.25e-02 5.01e-02 6.10e-02 4.90e-02 1.03e-01

Tm-170 8.85e-06 3.20e-06 8.58e-05 1.99e-05 2.17e-05 2.92e-05 2.14e-05 1.25e-04

Tm-171 2.54e-07 7.82e-08 2.50e-06 5.93e-07 1.61e-08 3.17e-08 1.01e-11 3.72e-06

Ta-182 9.13e-03 3.90e-03 6.81e-02 1.34e-02 5.85e-02 7.09e-02 5.75e-02 1.15e-01

W-181 1.90e-05 5.93e-06 1.83e-04 4.35e-05 1.74e-06 3.23e-06 4.11e-07 2.71e-04

W-185 6.56e-07 2.51e-07 6.81e-06 1.59e-06 1.14e-06 1.60e-06 1.15e-06 7.98e-06

Os-185 4.92e-03 2.04e-03 3.74e-02 7.70e-03 2.66e-02 3.27e-02 2.59e-02 6.02e-02

Ir-192 5.56e-03 2.22e-03 4.41e-02 9.55e-03 2.54e-02 3.19e-02 2.49e-02 6.78e-02

Tl-204 4.52e-06 1.76e-06 4.49e-05 1.04e-05 1.01e-05 1.36e-05 1.00e-05 5.66e-05

Pb-210 1.02e-05 3.84e-06 9.83e-05 2.22e-05 3.75e-05 4.89e-05 3.73e-05 1.46e-04

Bi-207 1.12e-02 4.70e-03 8.41e-02 1.70e-02 6.64e-02 8.09e-02 6.50e-02 1.39e-01

Po-210 7.46e-08 3.12e-08 5.61e-07 1.14e-07 4.29e-07 5.24e-07 4.18e-07 9.17e-07

Ra-226 1.26e-02 5.35e-03 9.43e-02 1.88e-02 8.09e-02 9.84e-02 8.01e-02 1.60e-01

Ra-228 6.37e-03 2.69e-03 4.80e-02 9.66e-03 3.84e-02 4.68e-02 3.77e-02 7.96e-02

Ac-227 2.37e-03 9.36e-04 1.92e-02 4.21e-03 1.01e-02 1.29e-02 9.98e-03 2.92e-02

Th-228 9.91e-03 4.31e-03 7.39e-02 1.45e-02 7.27e-02 8.79e-02 7.30e-02 1.31e-01

Th-229 1.62e-03 6.51e-04 1.30e-02 2.79e-03 7.54e-03 9.45e-03 7.42e-03 2.02e-02

Th-230 6.74e-07 2.44e-07 6.14e-06 1.42e-06 1.48e-06 2.02e-06 1.48e-06 8.84e-06

Th-232 2.01e-07 6.90e-08 1.98e-06 4.61e-07 2.31e-07 3.35e-07 2.31e-07 2.81e-06

Pa-231 1.95e-04 7.65e-05 1.59e-03 3.53e-04 8.05e-04 1.03e-03 7.93e-04 2.39e-03

U-232 4.38e-07 1.60e-07 4.16e-06 9.54e-07 9.95e-07 1.36e-06 1.01e-06 5.93e-06

U-233 8.41e-07 3.21e-07 7.25e-06 1.64e-06 2.85e-06 3.73e-06 2.83e-06 1.07e-05

U-234 1.59e-07 5.60e-08 1.68e-06 3.86e-07 2.31e-07 3.40e-07 2.40e-07 2.33e-06

U-235 6.85e-04 2.57e-04 6.02e-03 1.39e-03 1.99e-03 2.71e-03 2.02e-03 8.71e-03

U-236 6.43e-08 2.23e-08 7.82e-07 1.74e-07 7.52e-08 1.14e-07 7.74e-08 1.05e-06

U-238 2.01e-04 8.29e-05 1.62e-03 3.38e-04 1.11e-03 1.36e-03 1.08e-03 2.61e-03

Np-237 1.24e-03 4.84e-04 1.01e-02 2.25e-03 4.97e-03 6.37e-03 4.90e-03 1.52e-02

Pu-236 6.27e-08 2.31e-08 8.18e-07 1.74e-07 1.65e-07 2.17e-07 1.64e-07 1.09e-06

Pu-238 2.40e-08 8.38e-09 4.64e-07 9.58e-08 3.90e-08 5.46e-08 3.92e-08 5.66e-07

Pu-239 2.40e-07 9.29e-08 2.10e-06 4.64e-07 8.94e-07 1.15e-06 8.82e-07 3.11e-06

Pu-240 2.25e-08 7.72e-09 4.41e-07 9.13e-08 2.91e-08 4.21e-08 2.94e-08 5.37e-07

Pu-241 3.09e-09 1.11e-09 2.89e-08 6.84e-09 4.81e-09 7.12e-09 4.92e-09 4.10e-08

Pu-242 2.17e-08 7.43e-09 3.95e-07 8.29e-08 2.49e-08 3.75e-08 2.54e-08 4.86e-07

Pu-244 2.41e-03 1.00e-03 1.84e-02 3.78e-03 1.34e-02 1.65e-02 1.31e-02 2.99e-02

Am-241 1.10e-05 3.43e-06 1.07e-04 2.54e-05 1.11e-06 1.94e-06 4.24e-07 1.58e-04

Am-242m 4.90e-05 1.90e-05 4.22e-04 9.35e-05 1.75e-04 2.24e-04 1.73e-04 6.40e-04

Am-243 7.31e-04 2.76e-04 6.29e-03 1.44e-03 2.25e-03 2.98e-03 2.23e-03 9.23e-03

Cm-242 2.84e-08 1.07e-08 5.27e-07 1.07e-07 9.61e-08 1.22e-07 9.48e-08 6.60e-07

Cm-243 5.21e-04 1.99e-04 4.44e-03 1.01e-03 1.73e-03 2.28e-03 1.72e-03 6.53e-03

Cm-244 2.38e-08 9.01e-09 4.46e-07 9.05e-08 8.43e-08 1.07e-07 8.32e-08 5.57e-07

Cm-245 2.28e-04 8.27e-05 2.11e-03 4.96e-04 4.22e-04 6.08e-04 4.33e-04 3.00e-03

Cm-246 2.79e-09 7.48e-10 2.23e-07 4.31e-08 0.00e+00 0.00e+00 0.00e+00 2.42e-07

Cm-247 2.23e-03 8.90e-04 1.77e-02 3.82e-03 1.01e-02 1.27e-02 9.92e-03 2.71e-02

Cm-248 2.46e-09 6.56e-10 2.05e-07 3.97e-08 0.00e+00 0.00e+00 0.00e+00 2.23e-07

Bk-249 6.40e-09 2.27e-09 6.76e-08 1.53e-08 1.61e-08 2.08e-08 1.58e-08 9.74e-08

Cf-248 3.54e-08 1.22e-08 6.15e-07 1.34e-07 3.37e-08 5.32e-08 3.34e-08 7.72e-07

Cf-249 2.20e-03 8.77e-04 1.75e-02 3.81e-03 9.91e-03 1.25e-02 9.73e-03 2.68e-02

Cf-250 2.31e-09 5.65e-10 2.47e-07 4.90e-08 0.00e+00 0.00e+00 0.00e+00 2.69e-07

Cf-251 3.88e-04 1.45e-04 3.44e-03 7.95e-04 1.06e-03 1.44e-03 1.07e-03 4.97e-03

Cf-252 3.66e-08 1.29e-08 5.71e-07 1.25e-07 5.57e-08 8.15e-08 5.70e-08 7.29e-07

Cf-254 1.34e-01 5.66e-02 1.00e+00 2.00e-01 8.06e-01 9.81e-01 7.87e-01 1.66e+00

Es-254 6.82e-03 2.90e-03 5.09e-02 1.01e-02 4.22e-02 5.13e-02 4.13e-02 8.51e-02
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-82

Table C.79 Effective dose coefficients for external exposure in steel scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Dust pile Baghouse Large metal

object

Small metal

object

Small object 

on body Scrap truck Slag truck

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.28e-07 8.85e-08 6.41e-08 5.08e-08 1.10e-08 7.60e-10 2.40e-08 1.24e-09 4.41e-09

Na-22 1.72e-01 1.81e-01 1.62e-01 1.68e-02 7.14e-03 5.44e-04 2.74e-04 2.02e-02 1.26e-02

P-32 3.44e-04 2.43e-04 1.82e-04 1.91e-05 2.07e-05 1.52e-06 1.12e-05 3.67e-05 1.81e-05

S-35 1.31e-07 1.35e-07 7.21e-08 5.33e-08 1.14e-08 8.32e-10 2.42e-08 1.47e-09 8.86e-09

Cl-36 4.77e-05 3.70e-05 3.67e-05 5.39e-06 2.61e-06 1.92e-07 1.79e-08 4.00e-06 3.05e-06

K-40 1.37e-02 1.42e-02 1.28e-02 1.20e-03 4.91e-04 3.78e-05 1.91e-05 1.60e-03 9.25e-04

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 8.32e-07 8.89e-07 4.04e-07 1.74e-07 5.12e-08 3.61e-09 2.75e-16 2.71e-08 5.87e-08

Sc-46 1.65e-01 1.71e-01 1.54e-01 1.57e-02 6.54e-03 5.00e-04 2.53e-04 1.95e-02 1.17e-02

Cr-51 1.80e-03 2.10e-03 1.74e-03 2.19e-04 1.04e-04 7.79e-06 3.82e-06 2.08e-04 1.65e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 6.62e-02 6.89e-02 6.18e-02 6.53e-03 2.79e-03 2.12e-04 1.06e-04 7.86e-03 4.85e-03

Fe-55 3.07e-12 5.36e-12 3.43e-12 7.63e-13 2.39e-13 1.72e-14 1.41e-14 1.65e-13 4.26e-13

Fe-59 9.96e-02 1.04e-01 9.31e-02 9.19e-03 3.77e-03 2.89e-04 1.48e-04 1.18e-02 6.95e-03

Co-56 3.00e-01 3.17e-01 2.84e-01 2.68e-02 1.09e-02 8.39e-04 4.30e-04 3.51e-02 2.08e-02

Co-57 2.29e-03 3.96e-03 2.55e-03 5.69e-04 1.76e-04 1.26e-05 1.04e-05 1.24e-04 3.14e-04

Co-58 7.54e-02 7.89e-02 7.05e-02 7.57e-03 3.27e-03 2.48e-04 1.24e-04 8.92e-03 5.61e-03

Co-60 2.13e-01 2.21e-01 1.99e-01 1.93e-02 7.89e-03 6.06e-04 3.10e-04 2.51e-02 1.47e-02

Ni-59 1.11e-06 1.20e-06 1.05e-06 1.22e-07 5.47e-08 4.13e-09 2.02e-09 1.30e-07 8.96e-08

Ni-63 1.48e-09 1.46e-09 9.95e-10 2.08e-09 1.16e-10 7.90e-12 0.00e+00 2.88e-14 1.90e-11

Zn-65 4.80e-02 4.99e-02 4.49e-02 4.50e-03 1.86e-03 1.43e-04 7.25e-05 5.68e-03 3.38e-03

As-73 1.49e-05 3.77e-05 1.88e-05 2.29e-05 1.12e-06 7.69e-08 1.32e-07 5.05e-09 1.89e-06

Se-75 1.68e-02 2.12e-02 1.66e-02 2.36e-03 1.04e-03 7.72e-05 4.21e-05 1.76e-03 1.68e-03

Sr-85 3.43e-02 3.68e-02 3.23e-02 3.74e-03 1.68e-03 1.27e-04 6.21e-05 3.98e-03 2.75e-03

Sr-89 2.71e-04 1.85e-04 1.35e-04 1.46e-05 1.43e-05 1.06e-06 1.10e-08 1.27e-04 1.51e-05

Sr-90 7.56e-04 5.09e-04 4.07e-04 3.97e-05 4.11e-05 3.07e-06 5.08e-12 8.08e-05 3.79e-05

Y-91 5.85e-04 5.25e-04 4.25e-04 4.30e-05 2.67e-05 2.01e-06 4.50e-07 6.73e-05 3.67e-05

Zr-93 1.72e-09 1.70e-09 1.16e-09 2.43e-09 1.35e-10 9.25e-12 0.00e+00 9.57e-14 2.27e-11

Zr-95 5.67e-02 5.92e-02 5.30e-02 5.72e-03 2.47e-03 1.88e-04 9.33e-05 6.73e-03 4.23e-03

Nb-93m 1.33e-07 3.51e-07 1.73e-07 1.00e-06 1.19e-08 8.18e-10 2.84e-09 3.54e-18 4.39e-12

Nb-94 1.22e-01 1.27e-01 1.14e-01 1.22e-02 5.22e-03 3.98e-04 1.98e-04 1.45e-02 9.02e-03

Nb-95 5.96e-02 6.22e-02 5.56e-02 5.97e-03 2.58e-03 1.96e-04 9.74e-05 7.07e-03 4.42e-03

Mo-93 7.15e-07 1.90e-06 9.38e-07 5.42e-06 6.43e-08 4.41e-09 1.54e-08 0.00e+00 6.60e-12

Tc-97 9.54e-07 2.54e-06 1.25e-06 6.82e-06 8.36e-08 5.73e-09 1.83e-08 0.00e+00 3.41e-11

Tc-97m 4.52e-06 9.56e-06 5.36e-06 7.99e-06 3.67e-07 2.57e-08 3.73e-08 7.13e-08 5.22e-07

Tc-99 1.68e-06 1.11e-06 9.07e-07 3.14e-07 1.47e-07 1.05e-08 1.64e-07 7.06e-08 7.57e-08

Ru-103 3.43e-02 3.69e-02 3.23e-02 3.75e-03 1.69e-03 1.27e-04 6.25e-05 3.98e-03 2.76e-03

Ru-106 1.70e-02 1.70e-02 1.52e-02 1.67e-03 7.91e-04 5.99e-05 2.60e-05 1.99e-03 1.24e-03

Ag-108m 1.17e-01 1.24e-01 1.10e-01 1.23e-02 5.45e-03 4.13e-04 2.03e-04 1.38e-02 9.11e-03

Ag-110m 2.17e-01 2.27e-01 2.03e-01 2.11e-02 8.96e-03 6.84e-04 3.43e-04 2.57e-02 1.58e-02

Cd-109 3.39e-05 7.43e-05 4.10e-05 4.26e-05 2.70e-06 1.89e-07 2.54e-07 3.67e-07 4.49e-06

Sn-113 1.61e-02 1.80e-02 1.53e-02 1.89e-03 8.67e-04 6.52e-05 3.18e-05 1.89e-03 1.39e-03

Sb-124 1.52e-01 1.59e-01 1.43e-01 1.41e-02 5.87e-03 4.50e-04 2.28e-04 1.78e-02 1.08e-02

Sb-125 2.90e-02 3.13e-02 2.74e-02 3.21e-03 1.42e-03 1.07e-04 5.29e-05 3.39e-03 2.34e-03

Te-123m 3.75e-03 5.74e-03 3.99e-03 7.35e-04 2.74e-04 2.00e-05 1.34e-05 2.97e-04 4.64e-04

Te-127m 3.32e-04 3.68e-04 3.10e-04 6.10e-05 1.81e-05 1.36e-06 6.57e-07 3.73e-05 2.73e-05

I-125 1.99e-05 5.26e-05 2.61e-05 8.99e-05 1.51e-06 1.03e-07 1.99e-07 3.72e-12 3.79e-07

I-129 1.61e-05 4.21e-05 2.09e-05 6.26e-05 1.21e-06 8.21e-08 1.51e-07 7.44e-10 5.75e-07

I-131 2.38e-02 2.66e-02 2.27e-02 2.74e-03 1.27e-03 9.58e-05 4.68e-05 2.79e-03 2.05e-03

Cs-134 1.19e-01 1.24e-01 1.11e-01 1.21e-02 5.25e-03 3.99e-04 1.98e-04 1.40e-02 8.94e-03

Cs-135 1.30e-06 1.45e-06 1.10e-06 3.78e-07 7.83e-08 5.54e-09 0.00e+00 4.46e-08 8.46e-08

Cs-137 4.22e-02 4.44e-02 3.95e-02 4.36e-03 1.91e-03 1.45e-04 7.15e-05 5.00e-03 3.22e-03

Ba-133 1.98e-02 2.30e-02 1.91e-02 2.56e-03 1.12e-03 8.39e-05 4.22e-05 2.28e-03 1.79e-03

Ce-139 3.93e-03 5.90e-03 4.15e-03 7.88e-04 2.84e-04 2.08e-05 1.35e-05 3.23e-04 4.75e-04

Ce-141 1.72e-03 2.77e-03 1.86e-03 3.75e-04 1.29e-04 9.37e-06 6.75e-06 1.22e-04 2.22e-04

Ce-144 4.05e-03 3.74e-03 3.34e-03 3.65e-04 1.80e-04 1.36e-05 4.86e-06 4.45e-04 2.58e-04

Pm-147 5.09e-07 5.88e-07 2.77e-07 1.26e-07 3.08e-08 2.17e-09 3.05e-10 1.22e-08 3.65e-08

Sm-151 5.53e-09 8.02e-09 3.45e-09 1.08e-08 3.13e-10 2.14e-11 1.67e-11 1.75e-13 8.55e-11
Appendix C External Exposure Dose Coefficients

Table C.79 Effective dose coefficients for external exposure in steel scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Dust pile Baghouse Large metal

object

Small metal

object

Small object 

on body Scrap truck Slag truck

C-83 NUREG-1640

Eu-152 8.90e-02 9.40e-02 8.36e-02 8.74e-03 3.61e-03 2.76e-04 1.41e-04 1.04e-02 6.47e-03

Eu-154 8.75e-02 9.20e-02 8.21e-02 8.50e-03 3.50e-03 2.67e-04 1.37e-04 1.03e-02 6.30e-03

Eu-155 5.54e-04 1.13e-03 6.53e-04 2.56e-04 4.41e-05 3.11e-06 3.41e-06 1.21e-05 8.30e-05

Gd-153 7.13e-04 1.46e-03 8.43e-04 4.23e-04 5.67e-05 4.00e-06 4.44e-06 1.58e-05 1.03e-04

Tb-160 8.75e-02 9.20e-02 8.20e-02 8.57e-03 3.58e-03 2.74e-04 1.39e-04 1.03e-02 6.37e-03

Tm-170 7.39e-05 9.34e-05 5.54e-05 2.04e-05 5.11e-06 3.69e-07 1.61e-07 5.61e-06 6.72e-06

Tm-171 1.79e-06 4.43e-06 2.24e-06 2.40e-06 1.35e-07 9.31e-09 1.53e-08 1.51e-09 2.38e-07

Ta-182 1.00e-01 1.05e-01 9.40e-02 9.64e-03 3.88e-03 2.97e-04 1.54e-04 1.17e-02 7.11e-03

W-181 1.31e-04 3.23e-04 1.64e-04 1.57e-04 9.99e-06 6.89e-07 1.11e-06 2.12e-07 1.85e-05

W-185 5.78e-06 3.66e-06 2.91e-06 7.91e-07 4.11e-07 2.95e-08 3.27e-07 2.86e-07 2.68e-07

Os-185 4.88e-02 5.15e-02 4.57e-02 5.18e-03 2.20e-03 1.67e-04 8.34e-05 5.75e-03 3.72e-03

Ir-192 4.98e-02 5.61e-02 4.76e-02 5.82e-03 2.68e-03 2.02e-04 9.93e-05 5.77e-03 4.33e-03

Tl-204 4.01e-05 3.11e-05 2.32e-05 7.26e-06 2.70e-06 1.95e-07 1.50e-06 2.62e-06 2.24e-06

Pb-210 9.39e-05 5.91e-05 5.44e-05 1.43e-05 5.95e-06 4.37e-07 3.67e-08 8.46e-06 4.20e-06

Bi-207 1.17e-01 1.23e-01 1.10e-01 1.16e-02 4.87e-03 3.71e-04 1.88e-04 1.38e-02 8.58e-03

Po-210 7.65e-07 7.97e-07 7.14e-07 7.61e-08 3.26e-08 2.48e-09 1.24e-09 9.08e-08 5.64e-08

Ra-226 1.38e-01 1.46e-01 1.30e-01 1.30e-02 5.42e-03 4.15e-04 2.10e-04 1.61e-02 9.89e-03

Ra-228 6.72e-02 7.08e-02 6.30e-02 6.57e-03 2.77e-03 2.12e-04 1.07e-04 7.91e-03 4.91e-03

Ac-227 2.08e-02 2.44e-02 2.00e-02 2.71e-03 1.17e-03 8.75e-05 4.54e-05 2.30e-03 1.89e-03

Th-228 1.17e-01 1.26e-01 1.12e-01 1.04e-02 4.20e-03 3.23e-04 1.67e-04 1.34e-02 8.17e-03

Th-229 1.50e-02 1.74e-02 1.45e-02 1.97e-03 7.76e-04 5.82e-05 3.17e-05 1.63e-03 1.30e-03

Th-230 5.11e-06 8.60e-06 5.57e-06 2.16e-06 3.66e-07 2.65e-08 2.38e-08 3.29e-07 6.35e-07

Th-232 1.47e-06 3.01e-06 1.72e-06 1.23e-06 1.13e-07 8.01e-09 1.00e-08 4.81e-08 2.01e-07

Pa-231 1.66e-03 1.98e-03 1.61e-03 2.25e-04 9.79e-05 7.33e-06 3.74e-06 1.87e-04 1.56e-04

U-232 3.40e-06 5.74e-06 3.72e-06 1.84e-06 2.46e-07 1.78e-08 1.66e-08 2.17e-07 4.14e-07

U-233 6.86e-06 9.37e-06 6.97e-06 1.69e-06 4.42e-07 3.26e-08 2.12e-08 6.49e-07 7.22e-07

U-234 1.23e-06 2.40e-06 1.42e-06 1.21e-06 9.67e-08 6.86e-09 8.32e-09 4.55e-08 1.59e-07

U-235 5.31e-03 7.69e-03 5.52e-03 1.08e-03 3.72e-04 2.73e-05 1.73e-05 4.48e-04 6.16e-04

U-236 5.35e-07 1.12e-06 6.35e-07 8.78e-07 4.31e-08 3.04e-09 4.60e-09 1.40e-08 6.43e-08

U-238 2.07e-03 1.95e-03 1.74e-03 2.09e-04 9.49e-05 7.16e-06 2.75e-06 2.30e-04 1.37e-04

Np-237 1.05e-02 1.28e-02 1.03e-02 1.47e-03 6.21e-04 4.64e-05 2.50e-05 1.15e-03 1.01e-03

Pu-236 6.31e-07 1.14e-06 7.04e-07 1.16e-06 4.39e-08 3.13e-09 4.80e-09 3.50e-08 5.60e-08

Pu-238 2.93e-07 6.37e-07 3.53e-07 9.82e-07 2.34e-08 1.64e-09 3.45e-09 7.76e-09 2.26e-08

Pu-239 2.08e-06 2.76e-06 2.09e-06 7.54e-07 1.25e-07 9.26e-09 6.64e-09 2.02e-07 2.01e-07

Pu-240 2.72e-07 6.09e-07 3.32e-07 9.40e-07 2.22e-08 1.55e-09 3.31e-09 5.65e-09 2.14e-08

Pu-241 2.22e-08 4.09e-08 2.53e-08 6.91e-09 1.74e-09 1.24e-10 1.14e-10 9.39e-10 3.17e-09

Pu-242 2.44e-07 5.48e-07 2.98e-07 7.85e-07 2.02e-08 1.41e-09 2.88e-09 4.68e-09 2.11e-08

Pu-244 2.43e-02 2.56e-02 2.27e-02 2.48e-03 1.08e-03 8.20e-05 4.02e-05 2.85e-03 1.83e-03

Am-241 7.68e-05 1.88e-04 9.58e-05 9.55e-05 5.84e-06 4.02e-07 6.58e-07 1.56e-07 1.07e-05

Am-242m 4.33e-04 6.03e-04 4.40e-04 9.00e-05 2.48e-05 1.82e-06 1.37e-06 3.53e-05 4.41e-05

Am-243 5.82e-03 8.27e-03 5.98e-03 1.18e-03 3.84e-04 2.83e-05 1.89e-05 5.09e-04 6.46e-04

Cm-242 3.84e-07 7.24e-07 4.35e-07 1.13e-06 2.66e-08 1.89e-09 3.59e-09 2.07e-08 2.33e-08

Cm-243 4.18e-03 5.67e-03 4.24e-03 7.00e-04 2.73e-04 2.02e-05 1.22e-05 3.95e-04 4.50e-04

Cm-244 3.26e-07 6.09e-07 3.69e-07 9.57e-07 2.25e-08 1.60e-09 3.03e-09 1.82e-08 1.94e-08

Cm-245 1.67e-03 2.91e-03 1.86e-03 4.54e-04 1.28e-04 9.18e-06 7.79e-06 8.65e-05 2.28e-04

Cm-246 1.17e-07 3.09e-07 1.52e-07 7.49e-07 9.97e-09 6.83e-10 2.07e-09 9.96e-13 1.69e-09

Cm-247 1.99e-02 2.24e-02 1.90e-02 2.37e-03 1.07e-03 8.07e-05 4.01e-05 2.31e-03 1.73e-03

Cm-248 1.07e-07 2.84e-07 1.40e-07 6.93e-07 9.18e-09 6.29e-10 1.91e-09 8.06e-13 1.46e-09

Bk-249 6.62e-08 7.32e-08 4.80e-08 2.21e-08 3.81e-09 2.74e-10 7.44e-11 3.68e-09 4.78e-09

Cf-248 3.93e-07 8.89e-07 4.83e-07 1.12e-06 3.22e-08 2.24e-09 4.02e-09 5.56e-09 3.56e-08

Cf-249 1.95e-02 2.21e-02 1.87e-02 2.30e-03 1.07e-03 8.03e-05 3.94e-05 2.28e-03 1.71e-03

Cf-250 1.32e-07 3.51e-07 1.73e-07 8.43e-07 1.11e-08 7.62e-10 2.16e-09 3.36e-13 9.00e-10

Cf-251 2.99e-03 4.49e-03 3.15e-03 5.99e-04 2.11e-04 1.54e-05 1.05e-05 2.35e-04 3.58e-04

Cf-252 3.82e-07 8.06e-07 4.56e-07 9.30e-07 3.06e-08 2.15e-09 3.43e-09 1.11e-08 3.57e-08

Cf-254 1.41e+00 1.47e+00 1.32e+00 1.37e-01 5.76e-02 4.40e-03 2.21e-03 1.67e-01 1.02e-01

Es-254 7.32e-02 7.61e-02 6.83e-02 7.01e-03 2.91e-03 2.23e-04 1.13e-04 8.67e-03 5.22e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-84

Table C.80 Effective dose coefficients for external exposure in steel scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Atop dust

truck

Dry bulk

trailer

Dust in dump trailer Truck with

I-beams

Cement

basement

House with

steel studs

Auto engine

Driver’s seat Sleeper block

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 2.89e-08 1.88e-09 4.34e-09 7.85e-09 1.07e-08 4.00e-07 3.82e-08 1.09e-08

Na-22 1.04e-01 6.75e-03 1.48e-02 2.67e-02 1.33e-02 5.75e-01 9.95e-03 1.25e-02

P-32 1.14e-04 8.42e-06 1.84e-05 3.23e-05 3.10e-05 6.59e-04 3.65e-05 3.50e-05

S-35 3.33e-08 2.22e-09 5.08e-09 9.16e-09 1.03e-08 6.26e-07 4.18e-08 1.15e-08

Cl-36 2.28e-05 1.71e-06 3.75e-06 6.63e-06 3.63e-06 1.21e-04 5.78e-06 3.80e-06

K-40 8.24e-03 5.07e-04 1.11e-03 2.03e-03 9.89e-04 4.24e-02 6.70e-04 8.53e-04

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 2.16e-07 1.60e-08 3.53e-08 6.25e-08 5.36e-08 3.34e-06 1.92e-07 5.67e-08

Sc-46 1.00e-01 6.35e-03 1.39e-02 2.52e-02 1.25e-02 5.38e-01 9.01e-03 1.15e-02

Cr-51 1.10e-03 8.23e-05 1.79e-04 3.14e-04 1.60e-04 7.50e-03 1.61e-04 1.80e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 4.02e-02 2.61e-03 5.71e-03 1.03e-02 5.14e-03 2.21e-01 3.87e-03 4.90e-03

Fe-55 2.06e-12 1.68e-13 3.62e-13 6.27e-13 2.81e-13 2.52e-11 6.71e-13 3.67e-13

Fe-59 6.04e-02 3.78e-03 8.26e-03 1.51e-02 7.37e-03 3.19e-01 5.17e-03 6.61e-03

Co-56 1.82e-01 1.13e-02 2.46e-02 4.52e-02 2.18e-02 9.51e-01 1.49e-02 1.90e-02

Co-57 1.53e-03 1.24e-04 2.67e-04 4.63e-04 2.08e-04 1.86e-02 4.95e-04 2.69e-04

Co-58 4.57e-02 3.00e-03 6.58e-03 1.18e-02 5.93e-03 2.56e-01 4.56e-03 5.74e-03

Co-60 1.29e-01 8.02e-03 1.75e-02 3.20e-02 1.56e-02 6.75e-01 1.08e-02 1.38e-02

Ni-59 6.74e-07 4.67e-08 1.03e-07 1.82e-07 9.28e-08 4.06e-06 7.86e-08 9.57e-08

Ni-63 1.58e-10 5.85e-12 1.70e-11 3.24e-11 4.24e-11 7.04e-09 2.30e-10 1.35e-11

Zn-65 2.92e-02 1.84e-03 4.02e-03 7.31e-03 3.59e-03 1.55e-01 2.56e-03 3.26e-03

As-73 8.97e-06 5.17e-07 1.25e-06 2.31e-06 1.00e-06 2.48e-04 6.08e-06 9.38e-07

Se-75 1.05e-02 7.98e-04 1.73e-03 3.02e-03 1.51e-03 8.07e-02 1.85e-03 1.76e-03

Sr-85 2.07e-02 1.43e-03 3.15e-03 5.60e-03 2.85e-03 1.24e-01 2.41e-03 2.94e-03

Sr-89 8.46e-05 6.24e-06 1.36e-05 2.39e-05 2.12e-05 5.31e-04 2.73e-05 2.11e-05

Sr-90 2.57e-04 1.84e-05 4.03e-05 7.11e-05 6.41e-05 1.33e-03 7.23e-05 6.15e-05

Y-91 2.73e-04 1.80e-05 3.94e-05 7.09e-05 4.50e-05 1.53e-03 4.46e-05 4.25e-05

Zr-93 1.86e-10 7.18e-12 2.05e-11 3.88e-11 4.98e-11 8.22e-09 2.69e-10 1.73e-11

Zr-95 3.44e-02 2.26e-03 4.96e-03 8.92e-03 4.48e-03 1.93e-01 3.45e-03 4.35e-03

Nb-93m 7.95e-11 5.18e-13 3.27e-12 5.86e-12 7.36e-11 2.48e-06 1.45e-10 2.56e-13

Nb-94 7.41e-02 4.84e-03 1.06e-02 1.91e-02 9.56e-03 4.11e-01 7.28e-03 9.18e-03

Nb-95 3.61e-02 2.37e-03 5.20e-03 9.35e-03 4.69e-03 2.02e-01 3.59e-03 4.53e-03

Mo-93 2.73e-10 1.04e-13 5.88e-12 8.93e-12 3.52e-10 1.34e-05 6.05e-10 7.38e-17

Tc-97 1.03e-09 8.60e-13 2.68e-11 4.38e-11 9.47e-10 1.75e-05 1.74e-09 3.32e-15

Tc-97m 2.36e-06 1.86e-07 4.04e-07 7.09e-07 3.09e-07 5.46e-05 1.07e-06 3.95e-07

Tc-99 5.03e-07 3.82e-08 8.38e-08 1.47e-07 1.64e-07 4.44e-06 4.84e-07 1.98e-07

Ru-103 2.07e-02 1.44e-03 3.16e-03 5.62e-03 2.86e-03 1.25e-01 2.43e-03 2.95e-03

Ru-106 9.81e-03 6.62e-04 1.45e-03 2.60e-03 1.38e-03 5.56e-02 1.14e-03 1.36e-03

Ag-108m 7.10e-02 4.80e-03 1.05e-02 1.88e-02 9.52e-03 4.13e-01 7.75e-03 9.57e-03

Ag-110m 1.32e-01 8.49e-03 1.86e-02 3.36e-02 1.67e-02 7.21e-01 1.24e-02 1.57e-02

Cd-109 2.00e-05 1.53e-06 3.34e-06 5.91e-06 2.52e-06 4.28e-04 9.73e-06 3.20e-06

Sn-113 9.77e-03 7.07e-04 1.55e-03 2.72e-03 1.39e-03 6.28e-02 1.29e-03 1.51e-03

Sb-124 9.19e-02 5.82e-03 1.27e-02 2.32e-02 1.13e-02 4.91e-01 8.06e-03 1.02e-02

Sb-125 1.76e-02 1.21e-03 2.67e-03 4.74e-03 2.41e-03 1.06e-01 2.06e-03 2.48e-03

Te-123m 2.44e-03 1.98e-04 4.26e-04 7.37e-04 3.48e-04 2.45e-02 6.19e-04 4.41e-04

Te-127m 1.94e-04 1.39e-05 3.05e-05 5.39e-05 2.83e-05 1.33e-03 2.87e-05 3.03e-05

I-125 2.90e-06 6.11e-08 2.38e-07 4.61e-07 4.97e-07 3.34e-04 2.30e-06 3.95e-08

I-129 3.75e-06 1.14e-07 3.68e-07 7.07e-07 5.40e-07 2.69e-04 2.87e-06 1.24e-07

I-131 1.45e-02 1.04e-03 2.28e-03 4.02e-03 2.05e-03 9.29e-02 1.91e-03 2.21e-03

Cs-134 7.19e-02 4.76e-03 1.04e-02 1.87e-02 9.42e-03 4.06e-01 7.35e-03 9.22e-03

Cs-135 5.83e-07 4.75e-08 9.04e-08 1.59e-07 8.40e-08 4.46e-06 2.84e-07 8.96e-08

Cs-137 2.56e-02 1.71e-03 3.75e-03 6.72e-03 3.39e-03 1.46e-01 2.69e-03 3.36e-03

Ba-133 1.21e-02 8.92e-04 1.95e-03 3.42e-03 1.74e-03 8.28e-02 1.77e-03 1.93e-03

Ce-139 2.54e-03 2.05e-04 4.42e-04 7.65e-04 3.65e-04 2.49e-02 6.19e-04 4.58e-04

Ce-141 1.13e-03 9.21e-05 1.98e-04 3.43e-04 1.59e-04 1.23e-02 3.17e-04 2.04e-04

Ce-144 2.12e-03 1.39e-04 3.03e-04 5.49e-04 3.14e-04 1.20e-02 3.00e-04 2.92e-04

Pm-147 1.48e-07 1.10e-08 2.44e-08 4.31e-08 3.16e-08 2.18e-06 1.17e-07 3.41e-08
Appendix C External Exposure Dose Coefficients

Table C.80 Effective dose coefficients for external exposure in steel scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Atop dust

truck

Dry bulk

trailer

Dust in dump trailer Truck with

I-beams

Cement

basement

House with

steel studs

Auto engine

Driver’s seat Sleeper block

C-85 NUREG-1640

Sm-151 4.00e-10 1.62e-11 4.50e-11 8.50e-11 1.04e-10 4.05e-08 5.64e-10 4.15e-11

Eu-152 5.41e-02 3.47e-03 7.58e-03 1.37e-02 6.77e-03 2.98e-01 5.12e-03 6.31e-03

Eu-154 5.32e-02 3.39e-03 7.41e-03 1.34e-02 6.62e-03 2.91e-01 4.95e-03 6.11e-03

Eu-155 3.75e-04 2.93e-05 6.38e-05 1.12e-04 4.79e-05 6.09e-03 1.67e-04 6.17e-05

Gd-153 4.71e-04 3.61e-05 7.92e-05 1.39e-04 6.02e-05 7.93e-03 2.09e-04 7.56e-05

Tb-160 5.32e-02 3.42e-03 7.48e-03 1.35e-02 6.70e-03 2.93e-01 5.05e-03 6.28e-03

Tm-170 3.23e-05 2.41e-06 5.30e-06 9.36e-06 6.40e-06 3.88e-04 1.55e-05 6.97e-06

Tm-171 1.11e-06 6.76e-08 1.59e-07 2.93e-07 1.25e-07 2.87e-05 7.29e-07 1.27e-07

Ta-182 6.09e-02 3.84e-03 8.38e-03 1.53e-02 7.47e-03 3.30e-01 5.49e-03 6.77e-03

W-181 8.42e-05 5.36e-06 1.24e-05 2.28e-05 9.57e-06 2.08e-03 5.45e-05 1.03e-05

W-185 1.69e-06 1.31e-07 2.86e-07 5.01e-07 4.92e-07 1.51e-05 1.21e-06 5.96e-07

Os-185 2.96e-02 1.97e-03 4.32e-03 7.75e-03 3.90e-03 1.70e-01 3.14e-03 3.85e-03

Ir-192 3.04e-02 2.19e-03 4.79e-03 8.45e-03 4.31e-03 1.97e-01 4.06e-03 4.66e-03

Tl-204 1.37e-05 1.03e-06 2.25e-06 3.97e-06 3.24e-06 1.47e-04 7.29e-06 4.07e-06

Pb-210 3.27e-05 2.42e-06 5.31e-06 9.33e-06 8.20e-06 2.20e-04 1.33e-05 8.33e-06

Bi-207 7.10e-02 4.59e-03 1.01e-02 1.82e-02 9.02e-03 3.94e-01 6.87e-03 8.52e-03

Po-210 4.64e-07 3.02e-08 6.63e-08 1.19e-07 5.98e-08 2.57e-06 4.53e-08 5.73e-08

Ra-226 8.34e-02 5.32e-03 1.16e-02 2.11e-02 1.03e-02 4.53e-01 7.60e-03 9.45e-03

Ra-228 4.08e-02 2.63e-03 5.76e-03 1.04e-02 5.16e-03 2.25e-01 3.91e-03 4.85e-03

Ac-227 1.27e-02 9.30e-04 2.03e-03 3.57e-03 1.81e-03 8.94e-02 1.96e-03 2.00e-03

Th-228 7.08e-02 4.41e-03 9.56e-03 1.76e-02 8.40e-03 3.75e-01 5.88e-03 7.25e-03

Th-229 9.17e-03 6.45e-04 1.41e-03 2.50e-03 1.25e-03 6.30e-02 1.33e-03 1.32e-03

Th-230 3.29e-06 2.53e-07 5.51e-07 9.66e-07 4.49e-07 4.26e-05 1.09e-06 5.48e-07

Th-232 9.48e-07 7.04e-08 1.55e-07 2.75e-07 1.20e-07 1.71e-05 4.38e-07 1.48e-07

Pa-231 1.02e-03 7.67e-05 1.67e-04 2.92e-04 1.49e-04 7.28e-03 1.59e-04 1.68e-04

U-232 2.15e-06 1.66e-07 3.63e-07 6.34e-07 2.93e-07 2.81e-05 6.78e-07 3.60e-07

U-233 4.28e-06 3.28e-07 7.12e-07 1.24e-06 6.12e-07 3.88e-05 9.02e-07 7.18e-07

U-234 7.58e-07 5.89e-08 1.29e-07 2.25e-07 9.97e-08 1.29e-05 2.98e-07 1.26e-07

U-235 3.40e-03 2.71e-04 5.85e-04 1.01e-03 4.90e-04 3.21e-02 7.83e-04 6.05e-04

U-236 3.02e-07 2.31e-08 5.07e-08 8.90e-08 3.91e-08 6.36e-06 1.29e-07 4.85e-08

U-238 1.12e-03 7.35e-05 1.61e-04 2.90e-04 1.64e-04 6.47e-03 1.60e-04 1.56e-04

Np-237 6.48e-03 4.85e-04 1.06e-03 1.85e-03 9.34e-04 4.82e-02 1.08e-03 1.06e-03

Pu-236 3.18e-07 2.29e-08 5.05e-08 8.94e-08 4.21e-08 6.21e-06 9.38e-08 4.73e-08

Pu-238 1.14e-07 8.45e-09 1.86e-08 3.28e-08 1.49e-08 3.89e-06 4.36e-08 1.76e-08

Pu-239 1.26e-06 9.32e-08 2.04e-07 3.58e-07 1.77e-07 1.15e-05 2.44e-07 1.99e-07

Pu-240 1.04e-07 7.69e-09 1.70e-08 3.01e-08 1.36e-08 3.78e-06 4.38e-08 1.60e-08

Pu-241 1.50e-08 1.20e-09 2.60e-09 4.52e-09 1.99e-09 2.03e-07 5.51e-09 2.59e-09

Pu-242 1.00e-07 7.56e-09 1.67e-08 2.93e-08 1.31e-08 3.35e-06 4.29e-08 1.59e-08

Pu-244 1.47e-02 9.73e-04 2.13e-03 3.83e-03 1.93e-03 8.35e-02 1.54e-03 1.89e-03

Am-241 4.88e-05 3.11e-06 7.21e-06 1.32e-05 5.54e-06 1.21e-03 3.15e-05 5.98e-06

Am-242m 2.72e-04 1.94e-05 4.22e-05 7.49e-05 3.53e-05 2.57e-03 6.29e-05 3.89e-05

Am-243 3.69e-03 2.84e-04 6.18e-04 1.08e-03 5.24e-04 3.54e-02 8.73e-04 6.23e-04

Cm-242 1.47e-07 1.03e-08 2.27e-08 4.03e-08 1.99e-08 4.17e-06 3.43e-08 2.10e-08

Cm-243 2.64e-03 2.05e-04 4.43e-04 7.72e-04 3.81e-04 2.29e-02 5.51e-04 4.51e-04

Cm-244 1.24e-07 8.75e-09 1.92e-08 3.41e-08 1.68e-08 3.49e-06 2.74e-08 1.79e-08

Cm-245 1.11e-03 8.92e-05 1.93e-04 3.35e-04 1.51e-04 1.39e-02 3.72e-04 1.94e-04

Cm-246 9.11e-09 4.18e-10 1.10e-09 2.07e-09 1.22e-09 2.12e-06 6.68e-09 6.68e-10

Cm-247 1.21e-02 8.75e-04 1.91e-03 3.38e-03 1.72e-03 7.91e-02 1.64e-03 1.86e-03

Cm-248 7.92e-09 3.59e-10 9.47e-10 1.79e-09 1.07e-09 1.95e-06 5.82e-09 5.70e-10

Bk-249 2.62e-08 1.86e-09 4.13e-09 7.30e-09 4.34e-09 3.03e-07 1.10e-08 4.40e-09

Cf-248 1.63e-07 1.27e-08 2.76e-08 4.85e-08 2.14e-08 5.32e-06 7.14e-08 2.67e-08

Cf-249 1.19e-02 8.66e-04 1.89e-03 3.33e-03 1.70e-03 7.77e-02 1.62e-03 1.85e-03

Cf-250 5.58e-09 2.04e-10 5.79e-10 1.10e-09 1.00e-09 2.37e-06 4.40e-09 3.05e-10

Cf-251 1.93e-03 1.53e-04 3.31e-04 5.75e-04 2.74e-04 1.94e-02 4.90e-04 3.38e-04

Cf-252 1.72e-07 1.35e-08 2.93e-08 5.12e-08 2.33e-08 4.63e-06 6.44e-08 2.90e-08

Cf-254 8.57e-01 5.50e-02 1.20e-01 2.18e-01 1.08e-01 4.66e+00 7.97e-02 1.01e-01

Es-254 4.45e-02 2.82e-03 6.18e-03 1.12e-02 5.54e-03 2.39e-01 4.03e-03 5.12e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-86

Table C.81 Effective dose coefficients for external exposure in steel scenarios—part 3 (:Sv/h per Bq/g)

Nuclide Diesel truck Hull plate Steel ship

Driver’s seat Sleeper Bunk Lounge area Berthing Mess Operations Deck

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.65e-08 5.62e-09 2.16e-07 4.64e-08 4.14e-09 6.87e-09 3.54e-09 1.82e-07

Na-22 1.64e-02 6.89e-03 1.23e-01 2.48e-02 9.57e-02 1.16e-01 9.42e-02 2.00e-01

P-32 3.64e-05 1.54e-05 3.38e-04 7.42e-05 1.50e-04 1.92e-04 1.48e-04 4.72e-04

S-35 1.76e-08 5.87e-09 2.09e-07 5.00e-08 5.68e-09 9.28e-09 5.02e-09 2.06e-07

Cl-36 4.55e-06 1.74e-06 4.30e-05 9.71e-06 1.60e-05 2.10e-05 1.59e-05 6.16e-05

K-40 1.18e-03 5.12e-04 8.71e-03 1.68e-03 8.11e-03 9.77e-03 8.06e-03 1.50e-02

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 7.89e-08 2.69e-08 8.87e-07 2.09e-07 9.24e-08 1.38e-07 9.19e-08 1.19e-06

Sc-46 1.53e-02 6.51e-03 1.14e-01 2.27e-02 9.31e-02 1.13e-01 9.17e-02 1.88e-01

Cr-51 2.09e-04 8.24e-05 1.69e-03 3.72e-04 8.67e-04 1.11e-03 8.53e-04 2.48e-03

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 6.40e-03 2.69e-03 4.81e-02 9.71e-03 3.64e-02 4.43e-02 3.57e-02 7.73e-02

Fe-55 4.22e-13 1.54e-13 3.93e-12 9.26e-13 7.88e-13 1.15e-12 8.27e-13 5.45e-12

Fe-59 8.96e-03 3.84e-03 6.64e-02 1.30e-02 5.75e-02 6.94e-02 5.68e-02 1.11e-01

Co-56 2.60e-02 1.13e-02 1.93e-01 3.75e-02 1.79e-01 2.16e-01 1.79e-01 3.30e-01

Co-57 3.12e-04 1.14e-04 2.89e-03 6.80e-04 5.94e-04 8.58e-04 6.19e-04 4.02e-03

Co-58 7.42e-03 3.10e-03 5.60e-02 1.14e-02 4.09e-02 5.00e-02 4.01e-02 8.93e-02

Co-60 1.89e-02 8.13e-03 1.39e-01 2.72e-02 1.24e-01 1.49e-01 1.23e-01 2.36e-01

Ni-59 1.18e-07 4.82e-08 9.15e-07 1.93e-07 5.66e-07 7.03e-07 5.52e-07 1.40e-06

Ni-63 8.82e-11 2.26e-11 2.43e-09 5.22e-10 1.24e-13 2.56e-13 0.00e+00 2.26e-09

Zn-65 4.39e-03 1.88e-03 3.26e-02 6.44e-03 2.74e-02 3.32e-02 2.71e-02 5.42e-02

As-73 2.10e-06 6.34e-07 2.10e-05 4.95e-06 4.58e-08 9.53e-08 0.00e+00 2.91e-05

Se-75 2.02e-03 7.84e-04 1.68e-02 3.78e-03 7.41e-03 9.65e-03 7.35e-03 2.43e-02

Sr-85 3.63e-03 1.48e-03 2.81e-02 5.92e-03 1.74e-02 2.16e-02 1.70e-02 4.31e-02

Sr-89 2.52e-05 9.83e-06 2.35e-04 5.22e-05 1.07e-04 1.38e-04 1.06e-04 3.44e-04

Sr-90 7.46e-05 2.96e-05 6.81e-04 1.48e-04 3.56e-04 4.50e-04 3.51e-04 1.02e-03

Y-91 5.40e-05 2.21e-05 4.52e-04 9.50e-05 2.90e-04 3.59e-04 2.87e-04 7.05e-04

Zr-93 1.03e-10 2.65e-11 2.85e-09 6.10e-10 7.92e-13 1.54e-12 2.23e-13 2.64e-09

Zr-95 5.61e-03 2.34e-03 4.24e-02 8.65e-03 3.06e-02 3.74e-02 3.00e-02 6.74e-02

Nb-93m 1.94e-10 4.62e-11 2.76e-07 5.01e-08 0.00e+00 0.00e+00 0.00e+00 1.84e-07

Nb-94 1.19e-02 5.00e-03 8.99e-02 1.82e-02 6.67e-02 8.13e-02 6.53e-02 1.44e-01

Nb-95 5.86e-03 2.45e-03 4.42e-02 8.99e-03 3.24e-02 3.95e-02 3.17e-02 7.05e-02

Mo-93 9.48e-10 2.27e-10 1.49e-06 2.70e-07 0.00e+00 0.00e+00 0.00e+00 9.93e-07

Tc-97 2.35e-09 5.39e-10 1.90e-06 3.59e-07 0.00e+00 0.00e+00 0.00e+00 1.30e-06

Tc-97m 5.05e-07 1.76e-07 6.69e-06 1.51e-06 4.47e-07 7.17e-07 4.29e-07 7.92e-06

Tc-99 2.30e-07 8.63e-08 2.46e-06 5.81e-07 2.72e-07 3.96e-07 2.74e-07 2.68e-06

Ru-103 3.65e-03 1.48e-03 2.82e-02 5.96e-03 1.74e-02 2.16e-02 1.69e-02 4.33e-02

Ru-106 1.72e-03 7.08e-04 1.34e-02 2.78e-03 8.94e-03 1.10e-02 8.76e-03 2.09e-02

Ag-108m 1.20e-02 4.96e-03 9.22e-02 1.92e-02 6.16e-02 7.59e-02 6.02e-02 1.44e-01

Ag-110m 2.07e-02 8.72e-03 1.55e-01 3.12e-02 1.21e-01 1.47e-01 1.19e-01 2.52e-01

Cd-109 4.26e-06 1.45e-06 4.80e-05 1.13e-05 2.75e-06 4.63e-06 2.42e-06 6.06e-05

Sn-113 1.80e-03 7.19e-04 1.42e-02 3.08e-03 7.98e-03 1.01e-02 7.82e-03 2.13e-02

Sb-124 1.37e-02 5.88e-03 1.02e-01 2.03e-02 8.76e-02 1.06e-01 8.68e-02 1.71e-01

Sb-125 3.07e-03 1.25e-03 2.38e-02 5.01e-03 1.49e-02 1.84e-02 1.45e-02 3.65e-02

Te-123m 4.95e-04 1.85e-04 4.44e-03 1.03e-03 1.29e-03 1.80e-03 1.35e-03 6.21e-03

Te-127m 3.67e-05 1.46e-05 3.00e-04 6.52e-05 1.59e-04 2.00e-04 1.56e-04 4.43e-04

I-125 1.23e-06 2.86e-07 3.14e-05 7.07e-06 0.00e+00 0.00e+00 0.00e+00 2.83e-05

I-129 1.33e-06 3.31e-07 2.47e-05 5.62e-06 4.63e-09 7.68e-09 3.96e-09 2.44e-05

I-131 2.65e-03 1.06e-03 2.10e-02 4.53e-03 1.19e-02 1.49e-02 1.16e-02 3.14e-02

Cs-134 1.18e-02 4.92e-03 8.96e-02 1.84e-02 6.37e-02 7.80e-02 6.24e-02 1.42e-01

Cs-135 1.21e-07 4.17e-08 1.35e-06 3.17e-07 1.61e-07 2.38e-07 1.62e-07 1.82e-06

Cs-137 4.27e-03 1.77e-03 3.25e-02 6.70e-03 2.24e-02 2.75e-02 2.19e-02 5.11e-02

Ba-133 2.27e-03 8.99e-04 1.83e-02 4.01e-03 9.54e-03 1.21e-02 9.38e-03 2.70e-02

Ce-139 5.15e-04 1.93e-04 4.59e-03 1.07e-03 1.40e-03 1.93e-03 1.44e-03 6.42e-03

Ce-141 2.31e-04 8.54e-05 2.10e-03 4.92e-04 5.43e-04 7.66e-04 5.70e-04 2.93e-03

Ce-144 3.78e-04 1.57e-04 3.08e-03 6.38e-04 2.17e-03 2.67e-03 2.16e-03 4.93e-03

Pm-147 4.82e-08 1.63e-08 5.37e-07 1.27e-07 5.03e-08 7.60e-08 5.00e-08 7.18e-07
Appendix C External Exposure Dose Coefficients

Table C.81 Effective dose coefficients for external exposure in steel scenarios—part 3 (:Sv/h per Bq/g)

Nuclide Diesel truck Hull plate Steel ship

Driver’s seat Sleeper Bunk Lounge area Berthing Mess Operations Deck

C-87 NUREG-1640

Sm-151 2.13e-10 5.57e-11 6.56e-09 1.42e-09 1.29e-12 2.61e-12 3.63e-14 6.02e-09

Eu-152 8.34e-03 3.53e-03 6.27e-02 1.26e-02 5.00e-02 6.08e-02 4.94e-02 1.03e-01

Eu-154 8.14e-03 3.45e-03 6.10e-02 1.22e-02 4.93e-02 5.98e-02 4.87e-02 1.00e-01

Eu-155 7.87e-05 2.74e-05 7.49e-04 1.78e-04 7.24e-05 1.15e-04 7.04e-05 1.03e-03

Gd-153 1.00e-04 3.45e-05 9.70e-04 2.30e-04 9.27e-05 1.46e-04 9.14e-05 1.32e-03

Tb-160 8.28e-03 3.49e-03 6.22e-02 1.25e-02 4.89e-02 5.94e-02 4.82e-02 1.01e-01

Tm-170 8.85e-06 3.20e-06 8.58e-05 1.99e-05 2.11e-05 2.84e-05 2.07e-05 1.21e-04

Tm-171 2.54e-07 7.82e-08 2.50e-06 5.93e-07 1.51e-08 2.99e-08 9.70e-12 3.45e-06

Ta-182 9.13e-03 3.90e-03 6.81e-02 1.34e-02 5.72e-02 6.92e-02 5.66e-02 1.13e-01

W-181 1.90e-05 5.93e-06 1.83e-04 4.35e-05 1.65e-06 3.06e-06 3.99e-07 2.53e-04

W-185 6.56e-07 2.51e-07 6.81e-06 1.59e-06 1.11e-06 1.56e-06 1.12e-06 7.68e-06

Os-185 4.92e-03 2.04e-03 3.74e-02 7.70e-03 2.59e-02 3.18e-02 2.53e-02 5.89e-02

Ir-192 5.56e-03 2.22e-03 4.41e-02 9.55e-03 2.46e-02 3.10e-02 2.41e-02 6.60e-02

Tl-204 4.52e-06 1.76e-06 4.49e-05 1.04e-05 9.81e-06 1.33e-05 9.71e-06 5.46e-05

Pb-210 1.02e-05 3.84e-06 9.83e-05 2.22e-05 3.64e-05 4.76e-05 3.61e-05 1.41e-04

Bi-207 1.12e-02 4.70e-03 8.41e-02 1.70e-02 6.48e-02 7.89e-02 6.38e-02 1.36e-01

Po-210 7.46e-08 3.12e-08 5.61e-07 1.14e-07 4.18e-07 5.10e-07 4.10e-07 8.99e-07

Ra-226 1.26e-02 5.35e-03 9.43e-02 1.88e-02 7.91e-02 9.60e-02 7.85e-02 1.57e-01

Ra-228 6.37e-03 2.69e-03 4.80e-02 9.66e-03 3.75e-02 4.56e-02 3.70e-02 7.80e-02

Ac-227 2.37e-03 9.36e-04 1.92e-02 4.21e-03 9.84e-03 1.25e-02 9.68e-03 2.84e-02

Th-228 9.91e-03 4.31e-03 7.39e-02 1.45e-02 7.11e-02 8.59e-02 7.14e-02 1.28e-01

Th-229 1.62e-03 6.51e-04 1.30e-02 2.79e-03 7.34e-03 9.20e-03 7.22e-03 1.97e-02

Th-230 6.74e-07 2.44e-07 6.14e-06 1.42e-06 1.44e-06 1.97e-06 1.43e-06 8.50e-06

Th-232 2.01e-07 6.90e-08 1.98e-06 4.61e-07 2.25e-07 3.26e-07 2.24e-07 2.66e-06

Pa-231 1.95e-04 7.65e-05 1.59e-03 3.53e-04 7.79e-04 1.00e-03 7.67e-04 2.32e-03

U-232 4.38e-07 1.60e-07 4.16e-06 9.54e-07 9.66e-07 1.33e-06 9.80e-07 5.68e-06

U-233 8.41e-07 3.21e-07 7.25e-06 1.64e-06 2.76e-06 3.63e-06 2.74e-06 1.03e-05

U-234 1.59e-07 5.60e-08 1.68e-06 3.86e-07 2.25e-07 3.32e-07 2.33e-07 2.20e-06

U-235 6.85e-04 2.57e-04 6.02e-03 1.39e-03 1.93e-03 2.64e-03 1.96e-03 8.44e-03

U-236 6.43e-08 2.23e-08 7.82e-07 1.74e-07 7.33e-08 1.11e-07 7.52e-08 9.58e-07

U-238 2.01e-04 8.29e-05 1.62e-03 3.38e-04 1.08e-03 1.33e-03 1.06e-03 2.55e-03

Np-237 1.24e-03 4.84e-04 1.01e-02 2.25e-03 4.81e-03 6.19e-03 4.74e-03 1.48e-02

Pu-236 6.27e-08 2.31e-08 8.18e-07 1.74e-07 1.61e-07 2.11e-07 1.59e-07 9.72e-07

Pu-238 2.40e-08 8.38e-09 4.64e-07 9.58e-08 3.79e-08 5.32e-08 3.82e-08 4.71e-07

Pu-239 2.40e-07 9.29e-08 2.10e-06 4.64e-07 8.67e-07 1.12e-06 8.55e-07 2.98e-06

Pu-240 2.25e-08 7.72e-09 4.41e-07 9.13e-08 2.83e-08 4.10e-08 2.86e-08 4.46e-07

Pu-241 3.09e-09 1.11e-09 2.89e-08 6.84e-09 4.68e-09 6.93e-09 4.78e-09 4.00e-08

Pu-242 2.17e-08 7.43e-09 3.95e-07 8.29e-08 2.42e-08 3.64e-08 2.46e-08 4.09e-07

Pu-244 2.41e-03 1.00e-03 1.84e-02 3.78e-03 1.31e-02 1.60e-02 1.28e-02 2.92e-02

Am-241 1.10e-05 3.43e-06 1.07e-04 2.54e-05 1.05e-06 1.84e-06 4.12e-07 1.47e-04

Am-242m 4.90e-05 1.90e-05 4.22e-04 9.35e-05 1.71e-04 2.18e-04 1.70e-04 6.24e-04

Am-243 7.31e-04 2.76e-04 6.29e-03 1.44e-03 2.18e-03 2.89e-03 2.16e-03 8.95e-03

Cm-242 2.84e-08 1.07e-08 5.27e-07 1.07e-07 9.35e-08 1.19e-07 9.25e-08 5.46e-07

Cm-243 5.21e-04 1.99e-04 4.44e-03 1.01e-03 1.68e-03 2.22e-03 1.66e-03 6.33e-03

Cm-244 2.38e-08 9.01e-09 4.46e-07 9.05e-08 8.20e-08 1.04e-07 8.12e-08 4.60e-07

Cm-245 2.28e-04 8.27e-05 2.11e-03 4.96e-04 4.10e-04 5.93e-04 4.20e-04 2.92e-03

Cm-246 2.79e-09 7.48e-10 2.23e-07 4.31e-08 0.00e+00 0.00e+00 0.00e+00 1.69e-07

Cm-247 2.23e-03 8.90e-04 1.77e-02 3.82e-03 9.81e-03 1.24e-02 9.61e-03 2.64e-02

Cm-248 2.46e-09 6.56e-10 2.05e-07 3.97e-08 0.00e+00 0.00e+00 0.00e+00 1.55e-07

Bk-249 6.40e-09 2.27e-09 6.76e-08 1.53e-08 1.56e-08 2.02e-08 1.53e-08 8.95e-08

Cf-248 3.54e-08 1.22e-08 6.15e-07 1.34e-07 3.28e-08 5.17e-08 3.24e-08 6.55e-07

Cf-249 2.20e-03 8.77e-04 1.75e-02 3.81e-03 9.61e-03 1.22e-02 9.42e-03 2.61e-02

Cf-250 2.31e-09 5.65e-10 2.47e-07 4.90e-08 0.00e+00 0.00e+00 0.00e+00 1.85e-07

Cf-251 3.88e-04 1.45e-04 3.44e-03 7.95e-04 1.03e-03 1.40e-03 1.04e-03 4.83e-03

Cf-252 3.66e-08 1.29e-08 5.71e-07 1.25e-07 5.41e-08 7.94e-08 5.53e-08 6.30e-07

Cf-254 1.34e-01 5.66e-02 1.00e+00 2.00e-01 7.87e-01 9.55e-01 7.74e-01 1.63e+00

Es-254 6.82e-03 2.90e-03 5.09e-02 1.01e-02 4.13e-02 5.00e-02 4.06e-02 8.35e-02
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-88

Table C.82 Effective dose equivalent coefficients for copper scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Baghouse Large metal

object

Small metal

object

Small object 

on body

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 3.73e-08 5.43e-08 5.50e-08 9.04e-09 6.26e-10 6.01e-08

Na-22 7.22e-02 9.54e-02 1.68e-02 7.14e-03 5.44e-04 5.94e-04

P-32 1.52e-04 1.22e-04 2.04e-05 2.25e-05 1.68e-06 2.79e-05

S-35 4.22e-08 6.03e-08 5.77e-08 1.02e-08 7.11e-10 6.08e-08

Cl-36 1.75e-05 1.80e-05 3.99e-06 2.96e-06 2.18e-07 3.94e-08

K-40 5.77e-03 7.01e-03 1.20e-03 4.93e-04 3.79e-05 4.06e-05

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 2.54e-07 3.05e-07 1.88e-07 6.00e-08 4.23e-09 7.03e-16

Sc-46 6.96e-02 9.04e-02 1.57e-02 6.54e-03 5.00e-04 5.49e-04

Cr-51 7.15e-04 1.13e-03 2.19e-04 1.04e-04 7.79e-06 8.51e-06

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 2.79e-02 3.74e-02 6.53e-03 2.79e-03 2.12e-04 2.32e-04

Fe-55 1.04e-12 2.09e-12 7.63e-13 2.39e-13 1.72e-14 2.76e-14

Fe-59 4.20e-02 5.32e-02 9.19e-03 3.77e-03 2.89e-04 3.19e-04

Co-56 1.26e-01 1.55e-01 2.68e-02 1.09e-02 8.39e-04 9.18e-04

Co-57 7.77e-04 1.55e-03 5.69e-04 1.76e-04 1.26e-05 2.04e-05

Co-58 3.17e-02 4.31e-02 7.57e-03 3.27e-03 2.48e-04 2.70e-04

Co-60 8.97e-02 1.12e-01 1.93e-02 7.89e-03 6.06e-04 6.68e-04

Ni-59 4.63e-07 6.69e-07 1.22e-07 5.47e-08 4.13e-09 4.45e-09

Ni-63 5.59e-10 1.02e-09 2.25e-09 1.33e-10 9.11e-12 0.00e+00

Zn-65 2.03e-02 2.60e-02 4.50e-03 1.86e-03 1.43e-04 1.57e-04

As-73 4.66e-06 1.55e-05 2.29e-05 1.12e-06 7.69e-08 2.56e-07

Se-75 6.47e-03 1.07e-02 2.36e-03 1.04e-03 7.72e-05 9.12e-05

Sr-85 1.42e-02 2.06e-02 3.74e-03 1.68e-03 1.27e-04 1.37e-04

Sr-89 1.09e-04 9.03e-05 1.55e-05 1.65e-05 1.22e-06 2.40e-08

Sr-90 3.46e-04 2.68e-04 4.23e-05 4.72e-05 3.53e-06 1.14e-11

Y-91 2.45e-04 2.56e-04 4.40e-05 2.90e-05 2.18e-06 9.69e-07

Zr-93 6.54e-10 1.19e-09 2.63e-09 1.56e-10 1.07e-11 0.00e+00

Zr-95 2.39e-02 3.25e-02 5.72e-03 2.48e-03 1.88e-04 2.04e-04

Nb-93m 4.68e-08 2.14e-07 1.00e-06 1.19e-08 8.19e-10 7.31e-09

Nb-94 5.15e-02 6.95e-02 1.22e-02 5.22e-03 3.98e-04 4.33e-04

Nb-95 2.51e-02 3.41e-02 5.97e-03 2.58e-03 1.96e-04 2.13e-04

Mo-93 2.52e-07 1.16e-06 5.42e-06 6.43e-08 4.41e-09 3.97e-08

Tc-97 3.34e-07 1.48e-06 6.82e-06 8.36e-08 5.73e-09 4.72e-08

Tc-97m 1.49e-06 4.13e-06 8.00e-06 3.70e-07 2.59e-08 8.18e-08

Tc-99 5.88e-07 6.64e-07 3.39e-07 1.35e-07 9.61e-09 4.07e-07

Ru-103 1.42e-02 2.06e-02 3.75e-03 1.69e-03 1.27e-04 1.38e-04

Ru-106 7.21e-03 9.48e-03 1.67e-03 8.04e-04 6.09e-05 5.70e-05

Ag-108m 4.90e-02 6.89e-02 1.23e-02 5.46e-03 4.13e-04 4.47e-04

Ag-110m 9.15e-02 1.21e-01 2.11e-02 8.96e-03 6.84e-04 7.46e-04

Cd-109 1.09e-05 3.07e-05 4.26e-05 2.71e-06 1.89e-07 5.22e-07

Sn-113 6.52e-03 9.91e-03 1.89e-03 8.67e-04 6.52e-05 7.05e-05

Sb-124 6.38e-02 8.10e-02 1.41e-02 5.87e-03 4.50e-04 4.90e-04

Sb-125 1.20e-02 1.73e-02 3.21e-03 1.42e-03 1.07e-04 1.16e-04

Te-123m 1.33e-03 2.48e-03 7.35e-04 2.74e-04 2.00e-05 2.76e-05

Te-127m 1.35e-04 2.03e-04 6.11e-05 1.83e-05 1.37e-06 1.47e-06

I-125 6.50e-06 2.46e-05 8.99e-05 1.51e-06 1.03e-07 5.09e-07

I-129 5.19e-06 1.91e-05 6.26e-05 1.21e-06 8.22e-08 3.73e-07

I-131 9.65e-03 1.46e-02 2.74e-03 1.27e-03 9.58e-05 1.04e-04

Cs-134 4.98e-02 6.83e-02 1.21e-02 5.25e-03 3.99e-04 4.33e-04

Cs-135 3.93e-07 4.57e-07 2.56e-07 9.18e-08 6.50e-09 3.08e-07

Cs-137 1.77e-02 2.46e-02 4.36e-03 1.91e-03 1.45e-04 1.57e-04

Ba-133 7.91e-03 1.24e-02 2.56e-03 1.12e-03 8.40e-05 9.34e-05

Ce-139 1.40e-03 2.60e-03 7.88e-04 2.84e-04 2.08e-05 2.82e-05

Ce-141 5.98e-04 1.14e-03 3.75e-04 1.29e-04 9.38e-06 1.37e-05

Ce-144 1.73e-03 1.92e-03 3.70e-04 1.90e-04 1.43e-05 1.01e-05

Pm-147 1.47e-07 2.04e-07 1.34e-07 3.52e-08 2.48e-09 5.95e-10
Appendix C External Exposure Dose Coefficients

Table C.82 Effective dose equivalent coefficients for copper scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Baghouse Large metal

object

Small metal

object

Small object 

on body

C-89 NUREG-1640

Sm-151 1.45e-09 3.52e-09 1.11e-08 3.46e-10 2.37e-11 4.33e-11

Eu-152 3.73e-02 4.88e-02 8.74e-03 3.61e-03 2.76e-04 3.05e-04

Eu-154 3.68e-02 4.78e-02 8.50e-03 3.50e-03 2.67e-04 2.96e-04

Eu-155 1.79e-04 4.35e-04 2.56e-04 4.41e-05 3.11e-06 6.47e-06

Gd-153 2.31e-04 5.60e-04 4.23e-04 5.67e-05 4.00e-06 8.54e-06

Tb-160 3.68e-02 4.85e-02 8.57e-03 3.59e-03 2.74e-04 3.02e-04

Tm-170 2.95e-05 3.94e-05 2.07e-05 5.66e-06 4.10e-07 3.05e-07

Tm-171 5.59e-07 1.84e-06 2.40e-06 1.35e-07 9.32e-09 2.94e-08

Ta-182 4.22e-02 5.40e-02 9.64e-03 3.88e-03 2.97e-04 3.31e-04

W-181 4.11e-05 1.34e-04 1.57e-04 9.99e-06 6.89e-07 2.12e-06

W-185 1.77e-06 2.03e-06 8.36e-07 3.82e-07 2.75e-08 8.09e-07

Os-185 2.05e-02 2.84e-02 5.18e-03 2.20e-03 1.67e-04 1.82e-04

Ir-192 2.02e-02 3.07e-02 5.82e-03 2.68e-03 2.02e-04 2.20e-04

Tl-204 1.36e-05 1.67e-05 7.44e-06 2.63e-06 1.91e-07 3.66e-06

Pb-210 4.09e-05 3.78e-05 1.47e-05 6.84e-06 5.04e-07 9.83e-06

Bi-207 4.92e-02 6.53e-02 1.16e-02 4.87e-03 3.71e-04 4.08e-04

Po-210 3.23e-07 4.34e-07 7.61e-08 3.26e-08 2.48e-09 2.70e-09

Ra-226 5.76e-02 7.37e-02 1.30e-02 5.43e-03 4.15e-04 4.53e-04

Ra-228 2.82e-02 3.72e-02 6.57e-03 2.77e-03 2.12e-04 2.32e-04

Ac-227 8.27e-03 1.29e-02 2.71e-03 1.17e-03 8.77e-05 9.92e-05

Th-228 4.86e-02 5.89e-02 1.04e-02 4.20e-03 3.23e-04 3.53e-04

Th-229 6.06e-03 9.03e-03 1.97e-03 7.78e-04 5.83e-05 6.81e-05

Th-230 1.79e-06 3.83e-06 2.16e-06 3.67e-07 2.65e-08 4.81e-08

Th-232 4.85e-07 1.28e-06 1.23e-06 1.13e-07 8.02e-09 2.01e-08

Pa-231 6.54e-04 1.05e-03 2.25e-04 9.79e-05 7.33e-06 8.28e-06

U-232 1.20e-06 2.50e-06 1.84e-06 2.46e-07 1.78e-08 3.43e-08

U-233 2.59e-06 4.57e-06 1.69e-06 4.42e-07 3.26e-08 4.54e-08

U-234 4.10e-07 9.96e-07 1.21e-06 9.67e-08 6.86e-09 1.74e-08

U-235 1.93e-03 3.54e-03 1.08e-03 3.72e-04 2.73e-05 3.68e-05

U-236 1.77e-07 4.82e-07 8.78e-07 4.31e-08 3.04e-09 1.01e-08

U-238 8.86e-04 1.05e-03 2.11e-04 9.95e-05 7.50e-06 5.82e-06

Np-237 4.12e-03 6.68e-03 1.47e-03 6.21e-04 4.64e-05 5.42e-05

Pu-236 2.30e-07 5.56e-07 1.16e-06 4.39e-08 3.13e-09 1.12e-08

Pu-238 1.01e-07 3.20e-07 9.82e-07 2.34e-08 1.64e-09 8.33e-09

Pu-239 8.05e-07 1.39e-06 7.54e-07 1.25e-07 9.27e-09 1.45e-08

Pu-240 9.26e-08 3.03e-07 9.40e-07 2.22e-08 1.55e-09 7.95e-09

Pu-241 7.41e-09 1.59e-08 6.91e-09 1.74e-09 1.24e-10 2.20e-10

Pu-242 8.23e-08 2.66e-07 7.85e-07 2.02e-08 1.41e-09 6.83e-09

Pu-244 1.02e-02 1.38e-02 2.48e-03 1.08e-03 8.22e-05 8.78e-05

Am-241 2.40e-05 7.89e-05 9.55e-05 5.84e-06 4.03e-07 1.26e-06

Am-242m 1.66e-04 2.68e-04 9.00e-05 2.49e-05 1.83e-06 2.73e-06

Am-243 2.16e-03 3.91e-03 1.18e-03 3.84e-04 2.83e-05 3.92e-05

Cm-242 1.42e-07 3.84e-07 1.13e-06 2.67e-08 1.89e-09 8.86e-09

Cm-243 1.57e-03 2.74e-03 7.00e-04 2.73e-04 2.02e-05 2.58e-05

Cm-244 1.21e-07 3.25e-07 9.57e-07 2.25e-08 1.60e-09 7.52e-09

Cm-245 5.66e-04 1.16e-03 4.54e-04 1.28e-04 9.18e-06 1.52e-05

Cm-246 4.01e-08 1.72e-07 7.49e-07 9.98e-09 6.84e-10 5.27e-09

Cm-247 8.07e-03 1.23e-02 2.37e-03 1.07e-03 8.07e-05 8.84e-05

Cm-248 3.69e-08 1.59e-07 6.93e-07 9.18e-09 6.29e-10 4.87e-09

Bk-249 2.21e-08 3.52e-08 2.36e-08 4.13e-09 2.95e-10 1.63e-10

Cf-248 1.30e-07 4.08e-07 1.13e-06 3.22e-08 2.25e-09 9.40e-09

Cf-249 7.88e-03 1.21e-02 2.30e-03 1.07e-03 8.03e-05 8.73e-05

Cf-250 4.54e-08 1.92e-07 8.43e-07 1.11e-08 7.62e-10 5.55e-09

Cf-251 1.08e-03 2.00e-03 5.99e-04 2.11e-04 1.54e-05 2.17e-05

Cf-252 1.29e-07 3.72e-07 9.30e-07 3.06e-08 2.15e-09 8.03e-09

Cf-254 5.96e-01 7.86e-01 1.37e-01 5.76e-02 4.40e-03 4.82e-03

Es-254 3.09e-02 4.02e-02 7.01e-03 2.91e-03 2.23e-04 2.45e-04
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-90

Table C.83 Effective dose equivalent coefficients for copper scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Scrap truck Dust truck Slag truck Truck loaded with metal product

Driver’s seat Sleeper Driver’s seat Sleeper

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 7.37e-10 5.82e-09 1.05e-08 6.51e-09 4.85e-09 6.48e-09

Na-22 2.02e-02 1.48e-02 2.67e-02 1.26e-02 1.32e-02 1.79e-02

P-32 4.00e-05 2.36e-05 4.16e-05 1.86e-05 2.95e-05 3.89e-05

S-35 1.06e-09 6.82e-09 1.23e-08 7.55e-09 5.73e-09 7.62e-09

Cl-36 4.14e-06 3.25e-06 5.70e-06 2.80e-06 3.39e-06 4.45e-06

K-40 1.61e-03 1.11e-03 2.04e-03 9.28e-04 1.02e-03 1.41e-03

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 2.17e-08 4.74e-08 8.38e-08 4.84e-08 4.31e-08 5.61e-08

Sc-46 1.95e-02 1.39e-02 2.52e-02 1.17e-02 1.25e-02 1.71e-02

Cr-51 2.08e-04 1.79e-04 3.14e-04 1.65e-04 1.41e-04 1.86e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 7.86e-03 5.71e-03 1.03e-02 4.85e-03 5.10e-03 6.93e-03

Fe-55 1.65e-13 3.62e-13 6.27e-13 4.26e-13 2.07e-13 2.66e-13

Fe-59 1.18e-02 8.26e-03 1.51e-02 6.95e-03 7.50e-03 1.03e-02

Co-56 3.51e-02 2.46e-02 4.52e-02 2.08e-02 2.23e-02 3.08e-02

Co-57 1.24e-04 2.67e-04 4.63e-04 3.14e-04 1.54e-04 1.99e-04

Co-58 8.92e-03 6.58e-03 1.18e-02 5.61e-03 5.84e-03 7.90e-03

Co-60 2.51e-02 1.75e-02 3.20e-02 1.47e-02 1.60e-02 2.19e-02

Ni-59 1.30e-07 1.03e-07 1.82e-07 8.96e-08 8.78e-08 1.18e-07

Ni-63 3.36e-14 2.26e-11 4.31e-11 2.77e-11 1.78e-11 2.72e-11

Zn-65 5.68e-03 4.02e-03 7.31e-03 3.38e-03 3.64e-03 4.98e-03

As-73 5.05e-09 1.25e-06 2.31e-06 1.89e-06 5.75e-07 7.83e-07

Se-75 1.76e-03 1.73e-03 3.02e-03 1.68e-03 1.29e-03 1.69e-03

Sr-85 3.98e-03 3.15e-03 5.60e-03 2.75e-03 2.70e-03 3.62e-03

Sr-89 2.85e-05 1.74e-05 3.05e-05 1.38e-05 2.12e-05 2.80e-05

Sr-90 9.28e-05 5.15e-05 9.10e-05 3.94e-05 6.61e-05 8.79e-05

Y-91 6.63e-05 4.35e-05 7.81e-05 3.56e-05 4.55e-05 6.13e-05

Zr-93 1.12e-13 2.72e-11 5.17e-11 3.32e-11 2.14e-11 3.24e-11

Zr-95 6.73e-03 4.96e-03 8.92e-03 4.23e-03 4.40e-03 5.95e-03

Nb-93m 3.55e-18 3.47e-12 6.25e-12 4.71e-12 1.45e-12 2.73e-12

Nb-94 1.45e-02 1.06e-02 1.91e-02 9.02e-03 9.44e-03 1.28e-02

Nb-95 7.07e-03 5.20e-03 9.35e-03 4.42e-03 4.62e-03 6.25e-03

Mo-93 0.00e+00 5.88e-12 8.93e-12 6.60e-12 9.28e-13 2.37e-12

Tc-97 0.00e+00 2.68e-11 4.38e-11 3.41e-11 5.68e-12 1.33e-11

Tc-97m 7.14e-08 4.06e-07 7.13e-07 5.25e-07 2.13e-07 2.75e-07

Tc-99 6.68e-08 1.12e-07 1.97e-07 1.11e-07 1.05e-07 1.36e-07

Ru-103 3.98e-03 3.16e-03 5.62e-03 2.76e-03 2.70e-03 3.62e-03

Ru-106 2.02e-03 1.48e-03 2.65e-03 1.26e-03 1.35e-03 1.81e-03

Ag-108m 1.38e-02 1.05e-02 1.88e-02 9.11e-03 9.16e-03 1.23e-02

Ag-110m 2.57e-02 1.86e-02 3.36e-02 1.58e-02 1.66e-02 2.27e-02

Cd-109 3.67e-07 3.35e-06 5.91e-06 4.50e-06 1.69e-06 2.18e-06

Sn-113 1.89e-03 1.55e-03 2.72e-03 1.39e-03 1.27e-03 1.68e-03

Sb-124 1.78e-02 1.27e-02 2.32e-02 1.08e-02 1.15e-02 1.57e-02

Sb-125 3.39e-03 2.67e-03 4.74e-03 2.34e-03 2.27e-03 3.05e-03

Te-123m 2.97e-04 4.26e-04 7.37e-04 4.64e-04 2.69e-04 3.46e-04

Te-127m 3.75e-05 3.09e-05 5.45e-05 2.77e-05 2.59e-05 3.43e-05

I-125 3.72e-12 2.38e-07 4.61e-07 3.79e-07 1.06e-07 1.83e-07

I-129 8.70e-10 3.70e-07 7.10e-07 5.77e-07 1.70e-07 2.73e-07

I-131 2.79e-03 2.28e-03 4.02e-03 2.05e-03 1.87e-03 2.48e-03

Cs-134 1.40e-02 1.04e-02 1.87e-02 8.94e-03 9.21e-03 1.25e-02

Cs-135 3.87e-08 7.41e-08 1.31e-07 7.46e-08 6.85e-08 8.91e-08

Cs-137 5.00e-03 3.75e-03 6.72e-03 3.22e-03 3.30e-03 4.45e-03

Ba-133 2.28e-03 1.95e-03 3.42e-03 1.79e-03 1.55e-03 2.05e-03

Ce-139 3.23e-04 4.42e-04 7.65e-04 4.75e-04 2.84e-04 3.66e-04

Ce-141 1.22e-04 1.98e-04 3.43e-04 2.22e-04 1.21e-04 1.55e-04

Ce-144 4.66e-04 3.22e-04 5.82e-04 2.76e-04 3.16e-04 4.29e-04

Pm-147 1.09e-08 3.02e-08 5.34e-08 3.28e-08 2.43e-08 3.18e-08
Appendix C External Exposure Dose Coefficients

Table C.83 Effective dose equivalent coefficients for copper scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Scrap truck Dust truck Slag truck Truck loaded with metal product

Driver’s seat Sleeper Driver’s seat Sleeper

C-91 NUREG-1640

Sm-151 2.05e-13 5.97e-11 1.13e-10 7.26e-11 4.68e-11 6.96e-11

Eu-152 1.04e-02 7.58e-03 1.37e-02 6.47e-03 6.76e-03 9.22e-03

Eu-154 1.03e-02 7.41e-03 1.34e-02 6.30e-03 6.64e-03 9.07e-03

Eu-155 1.21e-05 6.38e-05 1.12e-04 8.30e-05 3.31e-05 4.28e-05

Gd-153 1.58e-05 7.92e-05 1.39e-04 1.03e-04 4.12e-05 5.35e-05

Tb-160 1.03e-02 7.48e-03 1.35e-02 6.37e-03 6.67e-03 9.08e-03

Tm-170 5.51e-06 6.20e-06 1.09e-05 6.51e-06 5.58e-06 7.29e-06

Tm-171 1.52e-09 1.60e-07 2.93e-07 2.38e-07 7.42e-08 9.99e-08

Ta-182 1.17e-02 8.38e-03 1.53e-02 7.11e-03 7.55e-03 1.03e-02

W-181 2.12e-07 1.24e-05 2.28e-05 1.85e-05 5.81e-06 7.77e-06

W-185 2.82e-07 3.59e-07 6.29e-07 3.55e-07 3.34e-07 4.33e-07

Os-185 5.75e-03 4.32e-03 7.75e-03 3.72e-03 3.80e-03 5.13e-03

Ir-192 5.77e-03 4.79e-03 8.45e-03 4.33e-03 3.91e-03 5.19e-03

Tl-204 2.61e-06 2.73e-06 4.81e-06 2.76e-06 2.60e-06 3.39e-06

Pb-210 9.83e-06 6.81e-06 1.20e-05 5.77e-06 7.88e-06 1.03e-05

Bi-207 1.38e-02 1.01e-02 1.82e-02 8.58e-03 8.96e-03 1.22e-02

Po-210 9.08e-08 6.63e-08 1.19e-07 5.64e-08 5.91e-08 8.01e-08

Ra-226 1.61e-02 1.16e-02 2.11e-02 9.90e-03 1.04e-02 1.42e-02

Ra-228 7.92e-03 5.76e-03 1.04e-02 4.91e-03 5.13e-03 6.98e-03

Ac-227 2.30e-03 2.03e-03 3.58e-03 1.89e-03 1.61e-03 2.13e-03

Th-228 1.34e-02 9.57e-03 1.76e-02 8.18e-03 8.57e-03 1.19e-02

Th-229 1.64e-03 1.41e-03 2.51e-03 1.30e-03 1.15e-03 1.53e-03

Th-230 3.29e-07 5.51e-07 9.66e-07 6.35e-07 3.41e-07 4.43e-07

Th-232 4.81e-08 1.55e-07 2.75e-07 2.01e-07 8.36e-08 1.09e-07

Pa-231 1.87e-04 1.67e-04 2.92e-04 1.56e-04 1.29e-04 1.70e-04

U-232 2.17e-07 3.63e-07 6.34e-07 4.14e-07 2.24e-07 2.91e-07

U-233 6.49e-07 7.13e-07 1.24e-06 7.22e-07 5.08e-07 6.64e-07

U-234 4.55e-08 1.29e-07 2.25e-07 1.59e-07 7.09e-08 9.18e-08

U-235 4.48e-04 5.85e-04 1.01e-03 6.16e-04 3.88e-04 5.02e-04

U-236 1.40e-08 5.07e-08 8.91e-08 6.43e-08 2.71e-08 3.51e-08

U-238 2.39e-04 1.69e-04 3.05e-04 1.45e-04 1.63e-04 2.20e-04

Np-237 1.15e-03 1.06e-03 1.85e-03 1.01e-03 8.12e-04 1.07e-03

Pu-236 3.50e-08 5.06e-08 8.95e-08 5.60e-08 3.38e-08 4.47e-08

Pu-238 7.76e-09 1.86e-08 3.28e-08 2.26e-08 1.08e-08 1.41e-08

Pu-239 2.02e-07 2.04e-07 3.58e-07 2.01e-07 1.52e-07 2.01e-07

Pu-240 5.65e-09 1.70e-08 3.01e-08 2.14e-08 9.43e-09 1.23e-08

Pu-241 9.39e-10 2.60e-09 4.52e-09 3.17e-09 1.44e-09 1.86e-09

Pu-242 4.68e-09 1.67e-08 2.93e-08 2.11e-08 8.94e-09 1.17e-08

Pu-244 2.85e-03 2.14e-03 3.84e-03 1.84e-03 1.88e-03 2.55e-03

Am-241 1.56e-07 7.21e-06 1.32e-05 1.07e-05 3.38e-06 4.52e-06

Am-242m 3.55e-05 4.24e-05 7.53e-05 4.43e-05 3.06e-05 4.09e-05

Am-243 5.09e-04 6.18e-04 1.08e-03 6.46e-04 4.26e-04 5.56e-04

Cm-242 2.07e-08 2.27e-08 4.03e-08 2.33e-08 1.67e-08 2.23e-08

Cm-243 3.95e-04 4.43e-04 7.73e-04 4.50e-04 3.13e-04 4.09e-04

Cm-244 1.82e-08 1.92e-08 3.41e-08 1.94e-08 1.43e-08 1.91e-08

Cm-245 8.65e-05 1.93e-04 3.35e-04 2.28e-04 1.11e-04 1.44e-04

Cm-246 9.96e-13 1.10e-09 2.08e-09 1.70e-09 5.06e-10 7.33e-10

Cm-247 2.31e-03 1.91e-03 3.38e-03 1.73e-03 1.57e-03 2.08e-03

Cm-248 8.06e-13 9.48e-10 1.79e-09 1.46e-09 4.36e-10 6.34e-10

Bk-249 3.69e-09 4.42e-09 7.84e-09 4.41e-09 3.47e-09 4.62e-09

Cf-248 5.56e-09 2.76e-08 4.85e-08 3.56e-08 1.44e-08 1.87e-08

Cf-249 2.28e-03 1.89e-03 3.33e-03 1.71e-03 1.54e-03 2.04e-03

Cf-250 3.36e-13 5.79e-10 1.10e-09 9.00e-10 2.64e-10 3.96e-10

Cf-251 2.35e-04 3.31e-04 5.75e-04 3.58e-04 2.15e-04 2.79e-04

Cf-252 1.11e-08 2.94e-08 5.12e-08 3.57e-08 1.64e-08 2.13e-08

Cf-254 1.67e-01 1.20e-01 2.18e-01 1.02e-01 1.08e-01 1.47e-01

Es-254 8.67e-03 6.18e-03 1.12e-02 5.22e-03 5.57e-03 7.61e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-92

Table C.84 Effective dose coefficients for external exposure in copper scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Baghouse Large metal

object

Small metal

object

Small object 

on body

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 3.59e-08 4.89e-08 4.60e-08 8.72e-09 6.03e-10 2.40e-08

Na-22 7.16e-02 9.33e-02 1.64e-02 7.08e-03 5.40e-04 2.74e-04

P-32 1.51e-04 1.18e-04 1.94e-05 2.24e-05 1.67e-06 1.12e-05

S-35 4.09e-08 5.46e-08 4.86e-08 9.93e-09 6.88e-10 2.42e-08

Cl-36 1.74e-05 1.74e-05 3.79e-06 2.95e-06 2.17e-07 1.79e-08

K-40 5.75e-03 6.87e-03 1.18e-03 4.91e-04 3.77e-05 1.91e-05

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 2.51e-07 2.87e-07 1.65e-07 5.93e-08 4.18e-09 2.75e-16

Sc-46 6.89e-02 8.82e-02 1.54e-02 6.48e-03 4.96e-04 2.53e-04

Cr-51 7.10e-04 1.09e-03 2.12e-04 1.03e-04 7.76e-06 3.82e-06

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 2.76e-02 3.65e-02 6.40e-03 2.76e-03 2.10e-04 1.06e-04

Fe-55 1.03e-12 2.04e-12 7.45e-13 2.38e-13 1.71e-14 1.41e-14

Fe-59 4.17e-02 5.20e-02 9.04e-03 3.75e-03 2.87e-04 1.48e-04

Co-56 1.25e-01 1.52e-01 2.63e-02 1.09e-02 8.35e-04 4.30e-04

Co-57 7.74e-04 1.52e-03 5.56e-04 1.75e-04 1.26e-05 1.04e-05

Co-58 3.13e-02 4.20e-02 7.41e-03 3.23e-03 2.46e-04 1.24e-04

Co-60 8.91e-02 1.10e-01 1.90e-02 7.85e-03 6.03e-04 3.10e-04

Ni-59 4.57e-07 6.53e-07 1.18e-07 5.41e-08 4.10e-09 2.02e-09

Ni-63 4.58e-10 7.65e-10 1.65e-09 1.09e-10 7.41e-12 0.00e+00

Zn-65 2.01e-02 2.54e-02 4.42e-03 1.85e-03 1.41e-04 7.25e-05

As-73 4.53e-06 1.44e-05 2.12e-05 1.09e-06 7.47e-08 1.32e-07

Se-75 6.43e-03 1.04e-02 2.29e-03 1.03e-03 7.70e-05 4.21e-05

Sr-85 1.41e-02 2.01e-02 3.63e-03 1.66e-03 1.26e-04 6.21e-05

Sr-89 1.09e-04 8.76e-05 1.48e-05 1.64e-05 1.22e-06 1.10e-08

Sr-90 3.43e-04 2.60e-04 4.04e-05 4.69e-05 3.51e-06 5.08e-12

Y-91 2.43e-04 2.50e-04 4.28e-05 2.88e-05 2.17e-06 4.50e-07

Zr-93 5.36e-10 8.95e-10 1.93e-09 1.28e-10 8.69e-12 0.00e+00

Zr-95 2.36e-02 3.18e-02 5.59e-03 2.45e-03 1.86e-04 9.33e-05

Nb-93m 3.19e-08 1.42e-07 6.67e-07 8.10e-09 5.58e-10 2.84e-09

Nb-94 5.09e-02 6.78e-02 1.19e-02 5.17e-03 3.94e-04 1.98e-04

Nb-95 2.48e-02 3.32e-02 5.84e-03 2.55e-03 1.94e-04 9.74e-05

Mo-93 1.72e-07 7.69e-07 3.61e-06 4.36e-08 3.00e-09 1.54e-08

Tc-97 2.30e-07 9.83e-07 4.54e-06 5.73e-08 3.93e-09 1.83e-08

Tc-97m 1.39e-06 3.57e-06 5.76e-06 3.45e-07 2.42e-08 3.73e-08

Tc-99 5.84e-07 6.30e-07 3.03e-07 1.34e-07 9.54e-09 1.64e-07

Ru-103 1.40e-02 2.01e-02 3.65e-03 1.67e-03 1.26e-04 6.25e-05

Ru-106 7.13e-03 9.25e-03 1.63e-03 7.97e-04 6.04e-05 2.60e-05

Ag-108m 4.84e-02 6.72e-02 1.20e-02 5.40e-03 4.10e-04 2.03e-04

Ag-110m 9.05e-02 1.18e-01 2.07e-02 8.88e-03 6.78e-04 3.43e-04

Cd-109 1.06e-05 2.78e-05 3.31e-05 2.63e-06 1.84e-07 2.54e-07

Sn-113 6.46e-03 9.63e-03 1.82e-03 8.60e-04 6.48e-05 3.18e-05

Sb-124 6.34e-02 7.93e-02 1.38e-02 5.84e-03 4.47e-04 2.28e-04

Sb-125 1.19e-02 1.69e-02 3.11e-03 1.41e-03 1.06e-04 5.29e-05

Te-123m 1.32e-03 2.40e-03 7.09e-04 2.73e-04 2.00e-05 1.34e-05

Te-127m 1.34e-04 1.96e-04 5.38e-05 1.81e-05 1.36e-06 6.57e-07

I-125 5.31e-06 1.81e-05 6.61e-05 1.23e-06 8.35e-08 1.99e-07

I-129 4.42e-06 1.47e-05 4.79e-05 1.03e-06 6.97e-08 1.51e-07

I-131 9.56e-03 1.42e-02 2.66e-03 1.26e-03 9.52e-05 4.68e-05

Cs-134 4.92e-02 6.67e-02 1.18e-02 5.19e-03 3.95e-04 1.98e-04

Cs-135 3.89e-07 4.32e-07 2.27e-07 9.10e-08 6.44e-09 1.23e-07

Cs-137 1.75e-02 2.40e-02 4.25e-03 1.89e-03 1.44e-04 7.15e-05

Ba-133 7.85e-03 1.20e-02 2.46e-03 1.11e-03 8.35e-05 4.22e-05

Ce-139 1.40e-03 2.52e-03 7.52e-04 2.83e-04 2.07e-05 1.35e-05

Ce-141 5.95e-04 1.11e-03 3.62e-04 1.29e-04 9.35e-06 6.75e-06

Ce-144 1.72e-03 1.87e-03 3.59e-04 1.89e-04 1.43e-05 4.86e-06

Pm-147 1.45e-07 1.92e-07 1.18e-07 3.47e-08 2.44e-09 3.05e-10
Appendix C External Exposure Dose Coefficients

Table C.84 Effective dose coefficients for external exposure in copper scenarios—part 1 (:Sv/h per Bq/g)

Nuclide Scrap pile Slag pile Baghouse Large metal

object

Small metal

object

Small object 

on body

C-93 NUREG-1640

Sm-151 1.18e-09 2.56e-09 7.75e-09 2.80e-10 1.91e-11 1.67e-11

Eu-152 3.70e-02 4.77e-02 8.55e-03 3.59e-03 2.74e-04 1.41e-04

Eu-154 3.65e-02 4.67e-02 8.33e-03 3.47e-03 2.65e-04 1.37e-04

Eu-155 1.80e-04 4.21e-04 2.45e-04 4.43e-05 3.12e-06 3.41e-06

Gd-153 2.29e-04 5.37e-04 3.91e-04 5.63e-05 3.97e-06 4.44e-06

Tb-160 3.64e-02 4.73e-02 8.40e-03 3.56e-03 2.72e-04 1.39e-04

Tm-170 2.94e-05 3.80e-05 1.96e-05 5.66e-06 4.09e-07 1.61e-07

Tm-171 5.50e-07 1.71e-06 2.24e-06 1.33e-07 9.16e-09 1.53e-08

Ta-182 4.18e-02 5.28e-02 9.47e-03 3.85e-03 2.95e-04 1.54e-04

W-181 4.08e-05 1.26e-04 1.47e-04 9.94e-06 6.84e-07 1.11e-06

W-185 1.76e-06 1.95e-06 7.74e-07 3.81e-07 2.73e-08 3.27e-07

Os-185 2.02e-02 2.77e-02 5.05e-03 2.17e-03 1.65e-04 8.34e-05

Ir-192 2.00e-02 2.98e-02 5.64e-03 2.66e-03 2.01e-04 9.93e-05

Tl-204 1.36e-05 1.61e-05 7.09e-06 2.64e-06 1.91e-07 1.50e-06

Pb-210 4.06e-05 3.62e-05 1.34e-05 6.80e-06 5.01e-07 3.96e-06

Bi-207 4.87e-02 6.38e-02 1.14e-02 4.83e-03 3.68e-04 1.88e-04

Po-210 3.19e-07 4.24e-07 7.44e-08 3.23e-08 2.46e-09 1.24e-09

Ra-226 5.73e-02 7.21e-02 1.27e-02 5.40e-03 4.13e-04 2.10e-04

Ra-228 2.80e-02 3.63e-02 6.44e-03 2.75e-03 2.10e-04 1.07e-04

Ac-227 8.21e-03 1.25e-02 2.63e-03 1.17e-03 8.74e-05 4.54e-05

Th-228 4.85e-02 5.77e-02 1.02e-02 4.19e-03 3.23e-04 1.67e-04

Th-229 6.01e-03 8.79e-03 1.91e-03 7.73e-04 5.80e-05 3.17e-05

Th-230 1.79e-06 3.68e-06 1.97e-06 3.66e-07 2.64e-08 2.38e-08

Th-232 4.81e-07 1.20e-06 1.08e-06 1.12e-07 7.94e-09 1.00e-08

Pa-231 6.50e-04 1.02e-03 2.15e-04 9.74e-05 7.30e-06 3.74e-06

U-232 1.18e-06 2.37e-06 1.55e-06 2.43e-07 1.75e-08 1.66e-08

U-233 2.58e-06 4.40e-06 1.51e-06 4.39e-07 3.24e-08 2.12e-08

U-234 3.98e-07 9.21e-07 9.64e-07 9.37e-08 6.66e-09 8.32e-09

U-235 1.92e-03 3.42e-03 1.01e-03 3.71e-04 2.73e-05 1.73e-05

U-236 1.67e-07 4.27e-07 6.65e-07 4.06e-08 2.86e-09 4.60e-09

U-238 8.78e-04 1.03e-03 2.05e-04 9.88e-05 7.45e-06 2.75e-06

Np-237 4.09e-03 6.48e-03 1.42e-03 6.18e-04 4.62e-05 2.50e-05

Pu-236 2.14e-07 4.76e-07 8.39e-07 4.00e-08 2.87e-09 4.80e-09

Pu-238 8.79e-08 2.53e-07 6.87e-07 2.00e-08 1.41e-09 3.45e-09

Pu-239 7.93e-07 1.32e-06 6.16e-07 1.23e-07 9.12e-09 6.64e-09

Pu-240 7.99e-08 2.39e-07 6.61e-07 1.89e-08 1.33e-09 3.31e-09

Pu-241 7.40e-09 1.55e-08 6.70e-09 1.74e-09 1.24e-10 1.14e-10

Pu-242 7.19e-08 2.12e-07 5.54e-07 1.75e-08 1.23e-09 2.88e-09

Pu-244 1.01e-02 1.35e-02 2.42e-03 1.07e-03 8.16e-05 4.02e-05

Am-241 2.38e-05 7.39e-05 8.82e-05 5.79e-06 3.98e-07 6.58e-07

Am-242m 1.64e-04 2.61e-04 8.57e-05 2.48e-05 1.82e-06 1.37e-06

Am-243 2.16e-03 3.79e-03 1.14e-03 3.84e-04 2.82e-05 1.89e-05

Cm-242 1.26e-07 3.04e-07 7.78e-07 2.26e-08 1.62e-09 3.59e-09

Cm-243 1.57e-03 2.66e-03 6.79e-04 2.72e-04 2.01e-05 1.22e-05

Cm-244 1.07e-07 2.57e-07 6.60e-07 1.91e-08 1.36e-09 3.03e-09

Cm-245 5.65e-04 1.13e-03 4.41e-04 1.28e-04 9.16e-06 7.79e-06

Cm-246 2.93e-08 1.20e-07 5.12e-07 7.24e-09 4.96e-10 2.07e-09

Cm-247 7.99e-03 1.20e-02 2.30e-03 1.06e-03 8.02e-05 4.01e-05

Cm-248 2.69e-08 1.10e-07 4.73e-07 6.65e-09 4.56e-10 1.91e-09

Bk-249 2.14e-08 3.25e-08 1.98e-08 3.97e-09 2.84e-10 7.44e-11

Cf-248 1.15e-07 3.29e-07 7.89e-07 2.84e-08 1.98e-09 4.02e-09

Cf-249 7.81e-03 1.17e-02 2.22e-03 1.06e-03 7.98e-05 3.94e-05

Cf-250 3.29e-08 1.31e-07 5.73e-07 8.02e-09 5.49e-10 2.16e-09

Cf-251 1.07e-03 1.94e-03 5.80e-04 2.10e-04 1.54e-05 1.05e-05

Cf-252 1.16e-07 3.05e-07 6.54e-07 2.74e-08 1.93e-09 3.43e-09

Cf-254 5.89e-01 7.67e-01 1.34e-01 5.71e-02 4.36e-03 2.21e-03

Es-254 3.06e-02 3.93e-02 6.87e-03 2.89e-03 2.21e-04 1.13e-04
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-94

Table C.85 Effective dose coefficients for external exposure in copper scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Scrap truck Dust truck Slag truck Truck loaded with metal product

Driver’s seat Sleeper Driver’s seat Sleeper

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 6.64e-10 4.91e-09 8.87e-09 5.43e-09 4.11e-09 6.40e-09

Na-22 1.89e-02 1.38e-02 2.50e-02 1.18e-02 1.23e-02 1.78e-02

P-32 3.72e-05 2.19e-05 3.85e-05 1.71e-05 2.73e-05 3.87e-05

S-35 9.59e-10 5.79e-09 1.04e-08 6.34e-09 4.89e-09 7.55e-09

Cl-36 3.84e-06 2.99e-06 5.24e-06 2.57e-06 3.13e-06 4.44e-06

K-40 1.51e-03 1.04e-03 1.91e-03 8.71e-04 9.57e-04 1.40e-03

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 1.99e-08 4.19e-08 7.41e-08 4.24e-08 3.82e-08 5.61e-08

Sc-46 1.83e-02 1.30e-02 2.37e-02 1.10e-02 1.18e-02 1.70e-02

Cr-51 1.94e-04 1.66e-04 2.91e-04 1.53e-04 1.31e-04 1.85e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 7.36e-03 5.33e-03 9.66e-03 4.54e-03 4.78e-03 6.86e-03

Fe-55 1.52e-13 3.31e-13 5.74e-13 3.89e-13 1.89e-13 2.67e-13

Fe-59 1.10e-02 7.71e-03 1.42e-02 6.52e-03 7.03e-03 1.02e-02

Co-56 3.29e-02 2.30e-02 4.24e-02 1.95e-02 2.09e-02 3.07e-02

Co-57 1.14e-04 2.44e-04 4.24e-04 2.86e-04 1.41e-04 1.99e-04

Co-58 8.36e-03 6.14e-03 1.11e-02 5.25e-03 5.46e-03 7.83e-03

Co-60 2.35e-02 1.64e-02 3.01e-02 1.38e-02 1.50e-02 2.18e-02

Ni-59 1.21e-07 9.56e-08 1.70e-07 8.35e-08 8.20e-08 1.16e-07

Ni-63 2.51e-14 1.54e-11 2.92e-11 1.86e-11 1.22e-11 2.43e-11

Zn-65 5.33e-03 3.75e-03 6.87e-03 3.18e-03 3.41e-03 4.94e-03

As-73 3.91e-09 9.98e-07 1.85e-06 1.50e-06 4.58e-07 7.58e-07

Se-75 1.63e-03 1.60e-03 2.80e-03 1.55e-03 1.19e-03 1.68e-03

Sr-85 3.73e-03 2.93e-03 5.21e-03 2.56e-03 2.52e-03 3.58e-03

Sr-89 2.65e-05 1.61e-05 2.82e-05 1.27e-05 1.96e-05 2.78e-05

Sr-90 8.66e-05 4.77e-05 8.44e-05 3.64e-05 6.14e-05 8.73e-05

Y-91 6.20e-05 4.04e-05 7.29e-05 3.32e-05 4.24e-05 6.09e-05

Zr-93 9.13e-14 1.88e-11 3.57e-11 2.27e-11 1.50e-11 2.93e-11

Zr-95 6.30e-03 4.63e-03 8.35e-03 3.96e-03 4.12e-03 5.90e-03

Nb-93m 1.95e-18 1.86e-12 3.37e-12 2.56e-12 7.26e-13 2.15e-12

Nb-94 1.36e-02 9.89e-03 1.79e-02 8.45e-03 8.83e-03 1.27e-02

Nb-95 6.63e-03 4.84e-03 8.75e-03 4.14e-03 4.32e-03 6.19e-03

Mo-93 0.00e+00 3.52e-12 5.72e-12 4.24e-12 3.49e-13 1.64e-12

Tc-97 0.00e+00 1.20e-11 2.01e-11 1.55e-11 2.03e-12 9.31e-12

Tc-97m 6.46e-08 3.65e-07 6.41e-07 4.70e-07 1.91e-07 2.77e-07

Tc-99 6.14e-08 9.99e-08 1.76e-07 9.82e-08 9.42e-08 1.37e-07

Ru-103 3.73e-03 2.94e-03 5.22e-03 2.57e-03 2.52e-03 3.58e-03

Ru-106 1.89e-03 1.38e-03 2.47e-03 1.18e-03 1.26e-03 1.80e-03

Ag-108m 1.30e-02 9.82e-03 1.76e-02 8.51e-03 8.56e-03 1.22e-02

Ag-110m 2.41e-02 1.74e-02 3.15e-02 1.48e-02 1.56e-02 2.25e-02

Cd-109 3.29e-07 2.99e-06 5.28e-06 3.99e-06 1.51e-06 2.21e-06

Sn-113 1.76e-03 1.44e-03 2.53e-03 1.29e-03 1.18e-03 1.67e-03

Sb-124 1.67e-02 1.19e-02 2.17e-02 1.01e-02 1.07e-02 1.56e-02

Sb-125 3.18e-03 2.48e-03 4.41e-03 2.18e-03 2.12e-03 3.02e-03

Te-123m 2.75e-04 3.92e-04 6.79e-04 4.26e-04 2.47e-04 3.47e-04

Te-127m 3.51e-05 2.87e-05 5.05e-05 2.57e-05 2.40e-05 3.41e-05

I-125 2.27e-12 1.28e-07 2.46e-07 2.00e-07 6.00e-08 1.52e-07

I-129 7.72e-10 2.34e-07 4.50e-07 3.63e-07 1.10e-07 2.38e-07

I-131 2.60e-03 2.12e-03 3.74e-03 1.91e-03 1.74e-03 2.47e-03

Cs-134 1.31e-02 9.74e-03 1.75e-02 8.36e-03 8.62e-03 1.23e-02

Cs-135 3.56e-08 6.58e-08 1.16e-07 6.57e-08 6.11e-08 8.90e-08

Cs-137 4.68e-03 3.50e-03 6.28e-03 3.01e-03 3.08e-03 4.41e-03

Ba-133 2.12e-03 1.81e-03 3.17e-03 1.66e-03 1.44e-03 2.03e-03

Ce-139 2.99e-04 4.07e-04 7.04e-04 4.35e-04 2.61e-04 3.66e-04

Ce-141 1.13e-04 1.82e-04 3.16e-04 2.04e-04 1.11e-04 1.55e-04

Ce-144 4.37e-04 3.00e-04 5.43e-04 2.56e-04 2.95e-04 4.27e-04

Pm-147 1.00e-08 2.67e-08 4.72e-08 2.88e-08 2.15e-08 3.17e-08
Appendix C External Exposure Dose Coefficients

Table C.85 Effective dose coefficients for external exposure in copper scenarios—part 2 (:Sv/h per Bq/g)

Nuclide Scrap truck Dust truck Slag truck Truck loaded with metal product

Driver’s seat Sleeper Driver’s seat Sleeper

C-95 NUREG-1640

Sm-151 1.60e-13 4.23e-11 8.00e-11 5.10e-11 3.35e-11 6.35e-11

Eu-152 9.80e-03 7.07e-03 1.29e-02 6.06e-03 6.32e-03 9.15e-03

Eu-154 9.63e-03 6.91e-03 1.26e-02 5.91e-03 6.22e-03 9.00e-03

Eu-155 1.10e-05 5.72e-05 1.01e-04 7.40e-05 2.97e-05 4.30e-05

Gd-153 1.44e-05 7.05e-05 1.24e-04 9.10e-05 3.69e-05 5.35e-05

Tb-160 9.66e-03 6.97e-03 1.27e-02 5.97e-03 6.24e-03 9.01e-03

Tm-170 5.10e-06 5.59e-06 9.85e-06 5.79e-06 5.08e-06 7.28e-06

Tm-171 1.25e-09 1.31e-07 2.40e-07 1.94e-07 6.06e-08 9.80e-08

Ta-182 1.10e-02 7.82e-03 1.43e-02 6.67e-03 7.07e-03 1.03e-02

W-181 1.83e-07 1.03e-05 1.89e-05 1.52e-05 4.82e-06 7.68e-06

W-185 2.60e-07 3.25e-07 5.69e-07 3.18e-07 3.03e-07 4.33e-07

Os-185 5.39e-03 4.03e-03 7.24e-03 3.47e-03 3.55e-03 5.07e-03

Ir-192 5.38e-03 4.46e-03 7.85e-03 4.02e-03 3.64e-03 5.15e-03

Tl-204 2.42e-06 2.47e-06 4.34e-06 2.46e-06 2.37e-06 3.39e-06

Pb-210 9.13e-06 6.23e-06 1.09e-05 5.22e-06 7.25e-06 1.03e-05

Bi-207 1.29e-02 9.38e-03 1.70e-02 8.03e-03 8.38e-03 1.21e-02

Po-210 8.51e-08 6.18e-08 1.12e-07 5.28e-08 5.53e-08 7.94e-08

Ra-226 1.51e-02 1.08e-02 1.98e-02 9.26e-03 9.71e-03 1.41e-02

Ra-228 7.42e-03 5.37e-03 9.77e-03 4.60e-03 4.80e-03 6.93e-03

Ac-227 2.14e-03 1.89e-03 3.31e-03 1.75e-03 1.49e-03 2.12e-03

Th-228 1.26e-02 8.95e-03 1.65e-02 7.64e-03 8.02e-03 1.19e-02

Th-229 1.53e-03 1.31e-03 2.33e-03 1.21e-03 1.07e-03 1.53e-03

Th-230 3.05e-07 5.00e-07 8.76e-07 5.71e-07 3.10e-07 4.43e-07

Th-232 4.43e-08 1.38e-07 2.44e-07 1.76e-07 7.42e-08 1.09e-07

Pa-231 1.74e-04 1.55e-04 2.70e-04 1.45e-04 1.20e-04 1.69e-04

U-232 2.01e-07 3.29e-07 5.76e-07 3.74e-07 2.04e-07 2.91e-07

U-233 6.02e-07 6.56e-07 1.15e-06 6.62e-07 4.68e-07 6.62e-07

U-234 4.19e-08 1.16e-07 2.03e-07 1.42e-07 6.40e-08 9.17e-08

U-235 4.14e-04 5.38e-04 9.33e-04 5.64e-04 3.56e-04 5.02e-04

U-236 1.28e-08 4.52e-08 7.94e-08 5.70e-08 2.42e-08 3.50e-08

U-238 2.24e-04 1.57e-04 2.84e-04 1.35e-04 1.52e-04 2.19e-04

Np-237 1.07e-03 9.80e-04 1.71e-03 9.28e-04 7.52e-04 1.06e-03

Pu-236 3.26e-08 4.57e-08 8.10e-08 5.02e-08 3.09e-08 4.44e-08

Pu-238 7.17e-09 1.66e-08 2.93e-08 2.01e-08 9.69e-09 1.40e-08

Pu-239 1.88e-07 1.88e-07 3.30e-07 1.84e-07 1.41e-07 2.00e-07

Pu-240 5.20e-09 1.51e-08 2.66e-08 1.88e-08 8.41e-09 1.23e-08

Pu-241 8.63e-10 2.36e-09 4.11e-09 2.87e-09 1.31e-09 1.86e-09

Pu-242 4.28e-09 1.48e-08 2.60e-08 1.86e-08 7.98e-09 1.16e-08

Pu-244 2.68e-03 1.99e-03 3.59e-03 1.72e-03 1.76e-03 2.53e-03

Am-241 1.38e-07 6.00e-06 1.10e-05 8.84e-06 2.81e-06 4.47e-06

Am-242m 3.31e-05 3.89e-05 6.95e-05 4.07e-05 2.83e-05 4.07e-05

Am-243 4.72e-04 5.68e-04 9.91e-04 5.90e-04 3.92e-04 5.55e-04

Cm-242 1.94e-08 2.07e-08 3.68e-08 2.10e-08 1.54e-08 2.21e-08

Cm-243 3.66e-04 4.09e-04 7.12e-04 4.13e-04 2.89e-04 4.08e-04

Cm-244 1.70e-08 1.76e-08 3.12e-08 1.76e-08 1.32e-08 1.89e-08

Cm-245 7.96e-05 1.76e-04 3.06e-04 2.07e-04 1.02e-04 1.44e-04

Cm-246 7.03e-13 8.02e-10 1.52e-09 1.23e-09 3.71e-10 6.77e-10

Cm-247 2.16e-03 1.78e-03 3.13e-03 1.60e-03 1.46e-03 2.06e-03

Cm-248 5.66e-13 6.89e-10 1.31e-09 1.06e-09 3.19e-10 5.85e-10

Bk-249 3.43e-09 3.96e-09 7.01e-09 3.91e-09 3.11e-09 4.56e-09

Cf-248 5.05e-09 2.47e-08 4.35e-08 3.18e-08 1.29e-08 1.87e-08

Cf-249 2.13e-03 1.76e-03 3.09e-03 1.59e-03 1.43e-03 2.02e-03

Cf-250 2.32e-13 3.96e-10 7.52e-10 6.11e-10 1.83e-10 3.57e-10

Cf-251 2.17e-04 3.04e-04 5.28e-04 3.27e-04 1.97e-04 2.79e-04

Cf-252 1.02e-08 2.65e-08 4.63e-08 3.21e-08 1.49e-08 2.13e-08

Cf-254 1.57e-01 1.12e-01 2.04e-01 9.55e-02 1.01e-01 1.46e-01

Es-254 8.12e-03 5.77e-03 1.05e-02 4.90e-03 5.22e-03 7.54e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-96

Table C.86 Effective dose equivalent coefficients for aluminum scenarios (:Sv/h per Bq/g)

Nuclide Scrap pile Dross pile Baghouse Large

object

Small

object

Scrap

truck

Dross

truck Dust truck Truck: ingots

Engine

block

Cooking

pot

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.32e-07 1.04e-07 4.32e-08 1.06e-08 7.71e-10 1.03e-09 1.15e-08 8.32e-09 7.47e-09 7.82e-09 2.36e-09

Na-22 1.03e-01 1.11e-01 1.68e-02 3.09e-03 2.45e-04 2.41e-02 1.80e-02 1.86e-02 9.37e-03 5.69e-03 4.31e-04

P-32 1.37e-04 1.28e-04 1.67e-05 6.12e-06 4.77e-07 2.29e-05 2.22e-05 1.86e-05 1.32e-05 1.06e-05 9.55e-07

S-35 1.45e-07 1.15e-07 4.53e-08 1.15e-08 8.36e-10 1.40e-09 1.31e-08 9.53e-09 8.46e-09 8.92e-09 2.52e-09

Cl-36 2.33e-05 2.18e-05 3.42e-06 1.13e-06 8.75e-08 3.33e-06 3.71e-06 3.24e-06 2.16e-06 1.82e-06 1.84e-07

K-40 7.69e-03 8.54e-03 1.20e-03 2.03e-04 1.61e-05 1.84e-03 1.32e-03 1.36e-03 6.66e-04 3.68e-04 2.79e-05

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 6.47e-07 5.34e-07 1.48e-07 4.57e-08 3.40e-09 2.07e-08 7.50e-08 5.62e-08 4.64e-08 4.92e-08 9.08e-09

Sc-46 9.63e-02 1.04e-01 1.57e-02 2.78e-03 2.20e-04 2.29e-02 1.67e-02 1.72e-02 8.61e-03 5.09e-03 3.85e-04

Cr-51 1.33e-03 1.36e-03 2.19e-04 5.11e-05 4.02e-06 2.83e-04 2.43e-04 2.47e-04 1.34e-04 9.64e-05 7.30e-06

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 3.95e-02 4.23e-02 6.53e-03 1.20e-03 9.46e-05 9.31e-03 6.91e-03 7.11e-03 3.60e-03 2.21e-03 1.67e-04

Fe-55 4.69e-12 4.41e-12 7.63e-13 2.41e-13 1.89e-14 4.60e-13 7.92e-13 7.51e-13 4.36e-13 4.20e-13 3.68e-14

Fe-59 5.74e-02 6.28e-02 9.19e-03 1.59e-03 1.26e-04 1.37e-02 9.91e-03 1.02e-02 5.05e-03 2.90e-03 2.20e-04

Co-56 1.72e-01 1.92e-01 2.68e-02 4.57e-03 3.64e-04 4.11e-02 2.97e-02 3.07e-02 1.50e-02 8.34e-03 6.30e-04

Co-57 3.47e-03 3.26e-03 5.69e-04 1.79e-04 1.40e-05 3.34e-04 5.84e-04 5.53e-04 3.21e-04 3.09e-04 2.74e-05

Co-58 4.56e-02 4.86e-02 7.57e-03 1.41e-03 1.12e-04 1.07e-02 8.01e-03 8.24e-03 4.20e-03 2.62e-03 1.98e-04

Co-60 1.21e-01 1.34e-01 1.93e-02 3.31e-03 2.63e-04 2.91e-02 2.10e-02 2.16e-02 1.06e-02 6.03e-03 4.56e-04

Ni-59 7.20e-07 7.52e-07 1.22e-07 2.47e-08 1.95e-09 1.62e-07 1.29e-07 1.32e-07 6.92e-08 4.61e-08 3.49e-09

Ni-63 2.61e-09 1.93e-09 1.77e-09 2.52e-10 1.73e-11 4.50e-14 5.88e-11 4.17e-11 5.83e-11 2.75e-11 7.23e-11

Zn-65 2.79e-02 3.04e-02 4.50e-03 7.87e-04 6.24e-05 6.64e-03 4.82e-03 4.97e-03 2.47e-03 1.44e-03 1.09e-04

As-73 5.37e-05 4.46e-05 2.29e-05 4.32e-06 3.15e-07 2.16e-08 5.25e-06 4.62e-06 3.10e-06 3.45e-06 8.89e-07

Se-75 1.45e-02 1.45e-02 2.36e-03 6.06e-04 4.76e-05 2.64e-03 2.61e-03 2.60e-03 1.44e-03 1.12e-03 8.84e-05

Sr-85 2.21e-02 2.31e-02 3.74e-03 7.56e-04 5.97e-05 4.97e-03 3.94e-03 4.05e-03 2.12e-03 1.41e-03 1.07e-04

Sr-89 1.03e-04 9.66e-05 1.28e-05 4.65e-06 3.62e-07 1.69e-05 1.67e-05 1.41e-05 9.90e-06 7.99e-06 7.28e-07

Sr-90 2.88e-04 2.72e-04 3.49e-05 1.22e-05 9.49e-07 5.20e-05 4.66e-05 3.94e-05 2.76e-05 2.10e-05 1.88e-06

Y-91 2.82e-04 2.92e-04 4.11e-05 9.67e-06 7.61e-07 5.93e-05 4.75e-05 4.56e-05 2.57e-05 1.71e-05 1.42e-06

Zr-93 3.04e-09 2.24e-09 2.07e-09 2.93e-10 2.02e-11 2.02e-13 6.96e-11 4.94e-11 6.80e-11 3.36e-11 8.43e-11

Zr-95 3.43e-02 3.65e-02 5.72e-03 1.07e-03 8.47e-05 8.03e-03 6.03e-03 6.21e-03 3.17e-03 1.98e-03 1.50e-04

Nb-93m 5.52e-07 4.23e-07 9.99e-07 5.88e-08 4.04e-09 9.24e-18 1.26e-11 1.11e-11 2.10e-10 1.09e-12 2.04e-08

Nb-94 7.33e-02 7.84e-02 1.22e-02 2.25e-03 1.78e-04 1.72e-02 1.29e-02 1.32e-02 6.73e-03 4.16e-03 3.15e-04

Nb-95 3.59e-02 3.83e-02 5.97e-03 1.11e-03 8.79e-05 8.42e-03 6.30e-03 6.49e-03 3.31e-03 2.06e-03 1.55e-04

Mo-93 2.98e-06 2.29e-06 5.42e-06 3.18e-07 2.19e-08 0.00e+00 1.63e-11 1.56e-11 1.04e-09 3.01e-16 1.10e-07

Tc-97 4.01e-06 3.08e-06 6.82e-06 4.16e-07 2.85e-08 0.00e+00 8.84e-11 8.33e-11 2.86e-09 1.37e-14 1.41e-07

Tc-97m 1.13e-05 9.66e-06 7.97e-06 8.42e-07 6.13e-08 2.97e-07 1.10e-06 1.01e-06 6.10e-07 6.53e-07 2.08e-07

Tc-99 1.32e-06 1.11e-06 2.69e-07 8.90e-08 6.67e-09 5.84e-08 1.65e-07 1.26e-07 1.01e-07 1.06e-07 1.70e-08

Ru-103 2.22e-02 2.32e-02 3.75e-03 7.63e-04 6.03e-05 4.98e-03 3.97e-03 4.07e-03 2.14e-03 1.43e-03 1.08e-04

Ru-106 1.01e-02 1.06e-02 1.66e-03 3.34e-04 2.64e-05 2.30e-03 1.78e-03 1.81e-03 9.53e-04 6.18e-04 4.73e-05

Ag-108m 7.35e-02 7.74e-02 1.23e-02 2.42e-03 1.91e-04 1.69e-02 1.30e-02 1.34e-02 6.94e-03 4.50e-03 3.41e-04

Ag-110m 1.29e-01 1.39e-01 2.11e-02 3.84e-03 3.04e-04 3.04e-02 2.25e-02 2.32e-02 1.17e-02 7.07e-03 5.35e-04

Cd-109 8.75e-05 7.58e-05 4.25e-05 6.12e-06 4.53e-07 1.88e-06 9.92e-06 9.03e-06 5.54e-06 6.13e-06 1.31e-06

Sn-113 1.12e-02 1.15e-02 1.89e-03 4.09e-04 3.23e-05 2.45e-03 2.01e-03 2.06e-03 1.10e-03 7.65e-04 5.87e-05

Sb-124 8.84e-02 9.69e-02 1.41e-02 2.49e-03 1.98e-04 2.09e-02 1.54e-02 1.59e-02 7.87e-03 4.57e-03 3.45e-04

Sb-125 1.89e-02 1.97e-02 3.21e-03 6.50e-04 5.13e-05 4.23e-03 3.36e-03 3.45e-03 1.81e-03 1.21e-03 9.25e-05

Te-123m 4.50e-03 4.33e-03 7.35e-04 2.13e-04 1.67e-05 6.32e-04 7.90e-04 7.65e-04 4.37e-04 3.82e-04 3.19e-05

Te-127m 2.47e-04 2.47e-04 6.07e-05 1.05e-05 8.05e-07 4.73e-05 4.04e-05 4.07e-05 2.23e-05 1.56e-05 1.79e-06

I-125 8.46e-05 6.64e-05 8.99e-05 7.82e-06 5.32e-07 1.08e-11 1.14e-06 1.01e-06 1.62e-06 1.81e-07 2.17e-06

I-129 6.71e-05 5.32e-05 6.26e-05 6.11e-06 4.19e-07 1.30e-09 1.72e-06 1.52e-06 1.75e-06 5.32e-07 1.61e-06

I-131 1.65e-02 1.70e-02 2.74e-03 6.02e-04 4.74e-05 3.62e-03 2.98e-03 3.04e-03 1.62e-03 1.13e-03 8.57e-05

Cs-134 7.23e-02 7.69e-02 1.21e-02 2.28e-03 1.81e-04 1.68e-02 1.27e-02 1.31e-02 6.72e-03 4.23e-03 3.20e-04

Cs-135 9.41e-07 7.83e-07 2.03e-07 6.49e-08 4.85e-09 3.54e-08 1.13e-07 8.53e-08 6.96e-08 7.34e-08 1.26e-08

Cs-137 2.60e-02 2.75e-02 4.36e-03 8.36e-04 6.60e-05 6.03e-03 4.59e-03 4.72e-03 2.43e-03 1.55e-03 1.17e-04

Ba-133 1.48e-02 1.50e-02 2.56e-03 5.78e-04 4.54e-05 3.05e-03 2.65e-03 2.69e-03 1.45e-03 1.06e-03 8.48e-05

Ce-139 4.57e-03 4.41e-03 7.88e-04 2.16e-04 1.69e-05 6.57e-04 7.98e-04 7.75e-04 4.42e-04 3.80e-04 3.29e-05

Ce-141 2.27e-03 2.16e-03 3.75e-04 1.11e-04 8.70e-06 2.84e-04 3.91e-04 3.76e-04 2.16e-04 1.96e-04 1.69e-05

Ce-144 2.33e-03 2.44e-03 3.58e-04 8.08e-05 6.36e-06 4.69e-04 3.95e-04 3.88e-04 2.10e-04 1.42e-04 1.19e-05

Pm-147 4.60e-07 3.87e-07 1.10e-07 3.19e-08 2.37e-09 1.70e-08 5.52e-08 4.43e-08 3.33e-08 3.47e-08 6.28e-09

Sm-151 9.97e-09 7.56e-09 1.03e-08 9.56e-10 6.56e-11 3.26e-13 1.52e-10 1.08e-10 1.54e-10 8.01e-11 2.83e-10
Appendix C External Exposure Dose Coefficients

Table C.86 Effective dose equivalent coefficients for aluminum scenarios (:Sv/h per Bq/g)

Nuclide Scrap pile Dross pile Baghouse Large

object

Small

object

Scrap

truck

Dross

truck Dust truck Truck: ingots

Engine

block

Cooking

pot

C-97 NUREG-1640

Eu-152 5.36e-02 5.78e-02 8.74e-03 1.60e-03 1.27e-04 1.24e-02 9.31e-03 9.56e-03 4.81e-03 2.91e-03 2.25e-04

Eu-154 5.22e-02 5.65e-02 8.50e-03 1.54e-03 1.22e-04 1.21e-02 9.05e-03 9.31e-03 4.67e-03 2.81e-03 2.16e-04

Eu-155 1.18e-03 1.06e-03 2.56e-04 7.14e-05 5.48e-06 4.74e-05 1.76e-04 1.62e-04 9.70e-05 1.05e-04 1.20e-05

Gd-153 1.57e-03 1.40e-03 4.23e-04 9.93e-05 7.52e-06 6.07e-05 2.18e-04 2.01e-04 1.22e-04 1.26e-04 1.78e-05

Tb-160 5.25e-02 5.65e-02 8.57e-03 1.57e-03 1.24e-04 1.23e-02 9.14e-03 9.39e-03 4.73e-03 2.87e-03 2.19e-04

Tm-170 8.47e-05 7.48e-05 1.98e-05 5.34e-06 4.05e-07 4.21e-06 1.18e-05 1.03e-05 6.73e-06 7.10e-06 9.46e-07

Tm-171 6.13e-06 5.14e-06 2.40e-06 4.79e-07 3.52e-08 8.90e-09 6.42e-07 5.67e-07 3.73e-07 4.25e-07 9.62e-08

Ta-182 5.94e-02 6.45e-02 9.64e-03 1.72e-03 1.36e-04 1.38e-02 1.02e-02 1.05e-02 5.24e-03 3.11e-03 2.42e-04

W-181 4.37e-04 3.69e-04 1.57e-04 3.33e-05 2.47e-06 9.46e-07 4.91e-05 4.33e-05 2.78e-05 3.32e-05 6.51e-06

W-185 3.85e-06 3.36e-06 7.10e-07 2.36e-07 1.79e-08 2.61e-07 5.42e-07 4.45e-07 3.20e-07 3.22e-07 4.19e-08

Os-185 3.04e-02 3.21e-02 5.18e-03 9.96e-04 7.85e-05 6.93e-03 5.33e-03 5.48e-03 2.82e-03 1.81e-03 1.42e-04

Ir-192 3.50e-02 3.60e-02 5.82e-03 1.29e-03 1.01e-04 7.56e-03 6.32e-03 6.43e-03 3.44e-03 2.41e-03 1.84e-04

Tl-204 3.33e-05 2.93e-05 6.95e-06 2.06e-06 1.57e-07 1.82e-06 4.72e-06 4.02e-06 2.71e-06 2.87e-06 3.59e-07

Pb-210 5.64e-05 5.01e-05 1.35e-05 3.28e-06 2.47e-07 5.92e-06 7.76e-06 6.45e-06 4.68e-06 4.07e-06 6.05e-07

Bi-207 7.06e-02 7.58e-02 1.16e-02 2.15e-03 1.70e-04 1.64e-02 1.23e-02 1.27e-02 6.40e-03 3.93e-03 3.02e-04

Po-210 4.58e-07 4.90e-07 7.61e-08 1.40e-08 1.11e-09 1.08e-07 8.03e-08 8.27e-08 4.20e-08 2.59e-08 1.96e-09

Ra-226 8.16e-02 8.92e-02 1.30e-02 2.36e-03 1.87e-04 1.91e-02 1.42e-02 1.46e-02 7.30e-03 4.31e-03 3.28e-04

Ra-228 4.04e-02 4.35e-02 6.57e-03 1.21e-03 9.59e-05 9.42e-03 7.04e-03 7.24e-03 3.65e-03 2.22e-03 1.69e-04

Ac-227 1.61e-02 1.63e-02 2.71e-03 6.40e-04 5.03e-05 3.12e-03 2.86e-03 2.87e-03 1.56e-03 1.17e-03 9.39e-05

Th-228 6.84e-02 7.68e-02 1.04e-02 1.83e-03 1.46e-04 1.60e-02 1.18e-02 1.22e-02 5.96e-03 3.31e-03 2.54e-04

Th-229 1.14e-02 1.16e-02 1.97e-03 4.46e-04 3.50e-05 2.15e-03 1.99e-03 1.99e-03 1.07e-03 7.89e-04 6.62e-05

Th-230 8.16e-06 7.48e-06 2.16e-06 4.84e-07 3.69e-08 6.32e-07 1.22e-06 1.15e-06 6.76e-07 6.77e-07 8.58e-08

Th-232 3.41e-06 2.99e-06 1.23e-06 2.33e-07 1.75e-08 1.22e-07 4.44e-07 4.05e-07 2.47e-07 2.74e-07 4.56e-08

Pa-231 1.30e-03 1.31e-03 2.25e-04 5.22e-05 4.10e-06 2.60e-04 2.34e-04 2.36e-04 1.29e-04 9.57e-05 7.69e-06

U-232 5.41e-06 4.94e-06 1.84e-06 3.26e-07 2.46e-08 4.44e-07 7.81e-07 7.39e-07 4.33e-07 4.18e-07 6.24e-08

U-233 7.17e-06 6.92e-06 1.69e-06 3.51e-07 2.70e-08 1.02e-06 1.19e-06 1.16e-06 6.55e-07 5.48e-07 5.91e-08

U-234 2.55e-06 2.26e-06 1.21e-06 1.72e-07 1.28e-08 1.33e-07 3.23e-07 3.00e-07 1.80e-07 1.82e-07 3.67e-08

U-235 5.86e-03 5.67e-03 1.08e-03 2.75e-04 2.15e-05 8.37e-04 1.02e-03 9.96e-04 5.65e-04 4.82e-04 4.26e-05

U-236 1.29e-06 1.11e-06 8.77e-07 9.65e-08 7.06e-09 4.60e-08 1.35e-07 1.25e-07 7.61e-08 7.70e-08 2.34e-08

U-238 1.24e-03 1.28e-03 2.05e-04 4.52e-05 3.54e-06 2.44e-04 2.09e-04 2.05e-04 1.11e-04 7.75e-05 6.79e-06

Np-237 8.68e-03 8.69e-03 1.47e-03 3.60e-04 2.83e-05 1.61e-03 1.54e-03 1.54e-03 8.47e-04 6.53e-04 5.32e-05

Pu-236 1.28e-06 1.10e-06 1.16e-06 1.01e-07 7.24e-09 5.95e-08 1.06e-07 1.01e-07 6.01e-08 5.48e-08 2.75e-08

Pu-238 8.27e-07 6.79e-07 9.82e-07 7.34e-08 5.18e-09 1.82e-08 4.62e-08 4.30e-08 2.67e-08 2.53e-08 2.18e-08

Pu-239 2.16e-06 2.06e-06 7.53e-07 1.13e-07 8.55e-09 2.94e-07 3.27e-07 3.22e-07 1.80e-07 1.47e-07 2.20e-08

Pu-240 8.06e-07 6.59e-07 9.40e-07 7.18e-08 5.07e-09 1.52e-08 4.51e-08 4.17e-08 2.62e-08 2.52e-08 2.12e-08

Pu-241 3.84e-08 3.55e-08 6.91e-09 2.11e-09 1.64e-10 2.72e-09 6.21e-09 5.81e-09 3.41e-09 3.46e-09 3.34e-10

Pu-242 7.10e-07 5.85e-07 7.85e-07 6.18e-08 4.38e-09 1.46e-08 4.44e-08 4.11e-08 2.56e-08 2.51e-08 1.79e-08

Pu-244 1.49e-02 1.59e-02 2.47e-03 4.76e-04 3.76e-05 3.43e-03 2.63e-03 2.70e-03 1.39e-03 8.79e-04 6.70e-05

Am-241 2.55e-04 2.16e-04 9.55e-05 1.95e-05 1.44e-06 5.24e-07 2.84e-05 2.51e-05 1.61e-05 1.94e-05 3.86e-06

Am-242m 4.82e-04 4.65e-04 8.98e-05 2.33e-05 1.81e-06 5.44e-05 7.83e-05 7.53e-05 4.23e-05 3.80e-05 3.69e-06

Am-243 6.53e-03 6.28e-03 1.18e-03 3.20e-04 2.49e-05 8.28e-04 1.10e-03 1.07e-03 6.07e-04 5.38e-04 4.98e-05

Cm-242 9.04e-07 7.43e-07 1.13e-06 8.01e-08 5.59e-09 3.06e-08 4.10e-08 3.97e-08 2.40e-08 1.91e-08 2.45e-08

Cm-243 4.18e-03 4.09e-03 7.00e-04 1.90e-04 1.48e-05 6.32e-04 7.33e-04 7.19e-04 4.04e-04 3.37e-04 2.84e-05

Cm-244 7.57e-07 6.23e-07 9.57e-07 6.72e-08 4.69e-09 2.67e-08 3.36e-08 3.26e-08 1.96e-08 1.52e-08 2.07e-08

Cm-245 2.61e-03 2.44e-03 4.54e-04 1.39e-04 1.08e-05 2.21e-04 4.31e-04 4.07e-04 2.37e-04 2.33e-04 2.17e-05

Cm-246 4.86e-07 3.76e-07 7.49e-07 4.92e-08 3.39e-09 3.32e-12 4.95e-09 4.36e-09 3.92e-09 2.80e-09 1.59e-08

Cm-247 1.41e-02 1.44e-02 2.37e-03 5.25e-04 4.14e-05 3.01e-03 2.53e-03 2.58e-03 1.38e-03 9.76e-04 7.55e-05

Cm-248 4.47e-07 3.46e-07 6.93e-07 4.53e-08 3.12e-09 2.67e-12 4.28e-09 3.77e-09 3.45e-09 2.40e-09 1.47e-08

Bk-249 6.30e-08 5.48e-08 1.94e-08 4.23e-09 3.09e-10 5.14e-09 7.16e-09 6.47e-09 4.29e-09 3.59e-09 9.14e-10

Cf-248 1.14e-06 9.48e-07 1.12e-06 9.51e-08 6.75e-09 2.16e-08 7.45e-08 6.88e-08 4.31e-08 4.32e-08 2.64e-08

Cf-249 1.38e-02 1.42e-02 2.30e-03 5.13e-04 4.04e-05 2.99e-03 2.50e-03 2.54e-03 1.36e-03 9.63e-04 7.32e-05

Cf-250 5.58e-07 4.31e-07 8.43e-07 5.58e-08 3.82e-09 1.09e-12 2.64e-09 2.33e-09 3.22e-09 1.30e-09 1.79e-08

Cf-251 3.57e-03 3.43e-03 5.99e-04 1.73e-04 1.35e-05 4.50e-04 6.16e-04 5.95e-04 3.40e-04 3.03e-04 2.62e-05

Cf-252 9.85e-07 8.25e-07 9.30e-07 7.96e-08 5.66e-09 3.03e-08 7.04e-08 6.59e-08 4.05e-08 3.88e-08 2.18e-08

Cf-254 8.33e-01 8.98e-01 1.37e-01 2.46e-02 1.95e-03 1.97e-01 1.45e-01 1.49e-01 7.51e-02 4.52e-02 3.42e-03

Es-254 4.29e-02 4.64e-02 7.01e-03 1.24e-03 9.84e-05 1.02e-02 7.44e-03 7.67e-03 3.83e-03 2.27e-03 1.73e-04
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-98

Table C.87 Effective dose coefficients for external exposure in aluminum scenarios (:Sv/h per Bq/g)

Nuclide Scrap pile Dross pile Baghouse Large

object

Small

object

Scrap

truck

Dross

truck Dust truck Truck: ingots

Engine

block

Cooking

pot

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.24e-07 9.88e-08 3.60e-08 9.94e-09 7.22e-10 9.29e-10 9.43e-09 6.85e-09 6.03e-09 7.48e-09 2.20e-09

Na-22 1.02e-01 1.10e-01 1.64e-02 3.06e-03 2.43e-04 2.26e-02 1.68e-02 1.74e-02 8.73e-03 5.54e-03 4.19e-04

P-32 1.37e-04 1.27e-04 1.59e-05 6.08e-06 4.74e-07 2.12e-05 2.03e-05 1.71e-05 1.21e-05 1.02e-05 9.25e-07

S-35 1.37e-07 1.09e-07 3.81e-08 1.08e-08 7.86e-10 1.27e-09 1.08e-08 7.90e-09 6.88e-09 8.55e-09 2.34e-09

Cl-36 2.32e-05 2.17e-05 3.25e-06 1.12e-06 8.68e-08 3.09e-06 3.38e-06 2.96e-06 1.96e-06 1.77e-06 1.77e-07

K-40 7.67e-03 8.50e-03 1.18e-03 2.02e-04 1.61e-05 1.73e-03 1.24e-03 1.28e-03 6.24e-04 3.59e-04 2.72e-05

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 6.30e-07 5.22e-07 1.30e-07 4.42e-08 3.29e-09 1.89e-08 6.48e-08 4.86e-08 3.96e-08 4.74e-08 8.57e-09

Sc-46 9.56e-02 1.04e-01 1.54e-02 2.75e-03 2.19e-04 2.15e-02 1.56e-02 1.62e-02 8.03e-03 4.96e-03 3.75e-04

Cr-51 1.33e-03 1.35e-03 2.12e-04 5.08e-05 4.00e-06 2.63e-04 2.25e-04 2.28e-04 1.23e-04 9.34e-05 7.11e-06

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 3.91e-02 4.20e-02 6.40e-03 1.18e-03 9.38e-05 8.72e-03 6.45e-03 6.65e-03 3.35e-03 2.14e-03 1.62e-04

Fe-55 4.69e-12 4.40e-12 7.45e-13 2.41e-13 1.89e-14 4.23e-13 7.21e-13 6.84e-13 3.95e-13 4.07e-13 3.58e-14

Fe-59 5.70e-02 6.24e-02 9.04e-03 1.58e-03 1.26e-04 1.28e-02 9.28e-03 9.59e-03 4.72e-03 2.83e-03 2.14e-04

Co-56 1.71e-01 1.91e-01 2.63e-02 4.55e-03 3.63e-04 3.85e-02 2.78e-02 2.88e-02 1.41e-02 8.11e-03 6.14e-04

Co-57 3.47e-03 3.26e-03 5.56e-04 1.79e-04 1.40e-05 3.08e-04 5.31e-04 5.04e-04 2.91e-04 3.00e-04 2.66e-05

Co-58 4.52e-02 4.82e-02 7.41e-03 1.40e-03 1.11e-04 9.98e-03 7.46e-03 7.70e-03 3.91e-03 2.54e-03 1.92e-04

Co-60 1.21e-01 1.33e-01 1.90e-02 3.28e-03 2.62e-04 2.73e-02 1.96e-02 2.03e-02 9.95e-03 5.87e-03 4.44e-04

Ni-59 7.14e-07 7.46e-07 1.18e-07 2.44e-08 1.92e-09 1.51e-07 1.19e-07 1.23e-07 6.42e-08 4.47e-08 3.39e-09

Ni-63 2.12e-09 1.57e-09 1.30e-09 2.04e-10 1.40e-11 3.39e-14 3.94e-11 2.79e-11 3.69e-11 2.54e-11 6.42e-11

Zn-65 2.77e-02 3.02e-02 4.42e-03 7.80e-04 6.21e-05 6.23e-03 4.52e-03 4.66e-03 2.31e-03 1.40e-03 1.06e-04

As-73 5.18e-05 4.33e-05 2.12e-05 4.19e-06 3.05e-07 1.68e-08 4.17e-06 3.66e-06 2.45e-06 3.23e-06 8.32e-07

Se-75 1.45e-02 1.44e-02 2.29e-03 6.04e-04 4.75e-05 2.45e-03 2.40e-03 2.39e-03 1.32e-03 1.09e-03 8.61e-05

Sr-85 2.19e-02 2.29e-02 3.63e-03 7.49e-04 5.90e-05 4.65e-03 3.66e-03 3.77e-03 1.97e-03 1.37e-03 1.04e-04

Sr-89 1.03e-04 9.61e-05 1.22e-05 4.62e-06 3.60e-07 1.57e-05 1.53e-05 1.29e-05 9.04e-06 7.75e-06 7.04e-07

Sr-90 2.86e-04 2.70e-04 3.33e-05 1.20e-05 9.40e-07 4.84e-05 4.29e-05 3.63e-05 2.53e-05 2.04e-05 1.82e-06

Y-91 2.81e-04 2.90e-04 4.00e-05 9.60e-06 7.57e-07 5.55e-05 4.42e-05 4.25e-05 2.38e-05 1.67e-05 1.38e-06

Zr-93 2.46e-09 1.83e-09 1.51e-09 2.37e-10 1.63e-11 1.69e-13 4.73e-11 3.35e-11 4.35e-11 3.11e-11 7.48e-11

Zr-95 3.40e-02 3.62e-02 5.59e-03 1.06e-03 8.39e-05 7.52e-03 5.62e-03 5.80e-03 2.95e-03 1.93e-03 1.46e-04

Nb-93m 3.75e-07 2.88e-07 6.67e-07 4.00e-08 2.75e-09 5.04e-18 6.94e-12 6.16e-12 1.03e-10 9.89e-13 1.68e-08

Nb-94 7.27e-02 7.78e-02 1.19e-02 2.23e-03 1.77e-04 1.61e-02 1.20e-02 1.24e-02 6.27e-03 4.04e-03 3.06e-04

Nb-95 3.56e-02 3.80e-02 5.84e-03 1.10e-03 8.71e-05 7.89e-03 5.88e-03 6.07e-03 3.08e-03 2.00e-03 1.51e-04

Mo-93 2.03e-06 1.56e-06 3.61e-06 2.16e-07 1.49e-08 0.00e+00 1.04e-11 9.90e-12 5.11e-10 2.54e-16 9.10e-08

Tc-97 2.75e-06 2.11e-06 4.54e-06 2.86e-07 1.96e-08 0.00e+00 3.97e-11 3.75e-11 1.23e-09 1.17e-14 1.18e-07

Tc-97m 1.01e-05 8.71e-06 5.74e-06 7.15e-07 5.28e-08 2.70e-07 9.82e-07 9.03e-07 5.40e-07 6.34e-07 1.85e-07

Tc-99 1.30e-06 1.09e-06 2.40e-07 8.67e-08 6.51e-09 5.35e-08 1.45e-07 1.10e-07 8.76e-08 1.02e-07 1.61e-08

Ru-103 2.20e-02 2.30e-02 3.65e-03 7.56e-04 5.96e-05 4.66e-03 3.68e-03 3.79e-03 1.98e-03 1.38e-03 1.05e-04

Ru-106 1.00e-02 1.06e-02 1.61e-03 3.31e-04 2.61e-05 2.15e-03 1.66e-03 1.69e-03 8.85e-04 6.00e-04 4.59e-05

Ag-108m 7.29e-02 7.68e-02 1.20e-02 2.39e-03 1.89e-04 1.58e-02 1.21e-02 1.25e-02 6.45e-03 4.37e-03 3.31e-04

Ag-110m 1.28e-01 1.38e-01 2.07e-02 3.80e-03 3.02e-04 2.85e-02 2.10e-02 2.17e-02 1.09e-02 6.88e-03 5.20e-04

Cd-109 8.26e-05 7.20e-05 3.31e-05 5.63e-06 4.20e-07 1.70e-06 8.77e-06 8.00e-06 4.82e-06 5.97e-06 1.22e-06

Sn-113 1.11e-02 1.14e-02 1.82e-03 4.06e-04 3.19e-05 2.28e-03 1.86e-03 1.91e-03 1.02e-03 7.42e-04 5.70e-05

Sb-124 8.80e-02 9.64e-02 1.38e-02 2.48e-03 1.97e-04 1.97e-02 1.44e-02 1.49e-02 7.36e-03 4.44e-03 3.36e-04

Sb-125 1.87e-02 1.95e-02 3.11e-03 6.43e-04 5.07e-05 3.96e-03 3.12e-03 3.21e-03 1.68e-03 1.17e-03 8.98e-05

Te-123m 4.49e-03 4.32e-03 7.09e-04 2.12e-04 1.66e-05 5.83e-04 7.23e-04 7.01e-04 3.98e-04 3.71e-04 3.11e-05

Te-127m 2.41e-04 2.42e-04 5.34e-05 1.01e-05 7.73e-07 4.41e-05 3.72e-05 3.76e-05 2.04e-05 1.52e-05 1.70e-06

I-125 6.85e-05 5.38e-05 6.61e-05 6.35e-06 4.32e-07 6.54e-12 6.00e-07 5.35e-07 8.66e-07 1.65e-07 1.96e-06

I-129 5.67e-05 4.49e-05 4.79e-05 5.17e-06 3.54e-07 1.13e-09 1.08e-06 9.54e-07 1.07e-06 4.88e-07 1.47e-06

I-131 1.64e-02 1.69e-02 2.66e-03 5.97e-04 4.71e-05 3.38e-03 2.76e-03 2.82e-03 1.50e-03 1.10e-03 8.33e-05

Cs-134 7.17e-02 7.63e-02 1.18e-02 2.26e-03 1.79e-04 1.58e-02 1.19e-02 1.23e-02 6.25e-03 4.11e-03 3.11e-04

Cs-135 9.20e-07 7.67e-07 1.79e-07 6.30e-08 4.71e-09 3.24e-08 9.84e-08 7.43e-08 5.99e-08 7.08e-08 1.20e-08

Cs-137 2.58e-02 2.73e-02 4.25e-03 8.26e-04 6.53e-05 5.64e-03 4.27e-03 4.41e-03 2.26e-03 1.51e-03 1.14e-04

Ba-133 1.47e-02 1.50e-02 2.46e-03 5.74e-04 4.50e-05 2.84e-03 2.45e-03 2.48e-03 1.34e-03 1.02e-03 8.23e-05

Ce-139 4.56e-03 4.40e-03 7.52e-04 2.15e-04 1.68e-05 6.07e-04 7.30e-04 7.10e-04 4.02e-04 3.68e-04 3.19e-05

Ce-141 2.26e-03 2.16e-03 3.62e-04 1.11e-04 8.69e-06 2.62e-04 3.57e-04 3.43e-04 1.96e-04 1.90e-04 1.64e-05

Ce-144 2.33e-03 2.43e-03 3.48e-04 8.03e-05 6.33e-06 4.39e-04 3.67e-04 3.60e-04 1.94e-04 1.38e-04 1.15e-05

Pm-147 4.48e-07 3.78e-07 9.69e-08 3.07e-08 2.29e-09 1.56e-08 4.80e-08 3.87e-08 2.86e-08 3.35e-08 5.93e-09

Sm-151 7.72e-09 5.86e-09 7.15e-09 7.40e-10 5.09e-11 2.60e-13 1.06e-10 7.50e-11 9.61e-11 7.43e-11 2.50e-10
Appendix C External Exposure Dose Coefficients

Table C.87 Effective dose coefficients for external exposure in aluminum scenarios (:Sv/h per Bq/g)

Nuclide Scrap pile Dross pile Baghouse Large

object

Small

object

Scrap

truck

Dross

truck Dust truck Truck: ingots

Engine

block

Cooking

pot

C-99 NUREG-1640

Eu-152 5.32e-02 5.75e-02 8.55e-03 1.59e-03 1.26e-04 1.16e-02 8.69e-03 8.95e-03 4.48e-03 2.83e-03 2.19e-04

Eu-154 5.19e-02 5.61e-02 8.33e-03 1.53e-03 1.21e-04 1.14e-02 8.46e-03 8.71e-03 4.35e-03 2.73e-03 2.10e-04

Eu-155 1.18e-03 1.07e-03 2.45e-04 7.14e-05 5.49e-06 4.31e-05 1.57e-04 1.44e-04 8.58e-05 1.02e-04 1.16e-05

Gd-153 1.55e-03 1.38e-03 3.91e-04 9.75e-05 7.39e-06 5.53e-05 1.92e-04 1.77e-04 1.07e-04 1.22e-04 1.70e-05

Tb-160 5.21e-02 5.62e-02 8.40e-03 1.56e-03 1.23e-04 1.15e-02 8.53e-03 8.79e-03 4.41e-03 2.79e-03 2.14e-04

Tm-170 8.46e-05 7.47e-05 1.88e-05 5.32e-06 4.04e-07 3.87e-06 1.04e-05 9.02e-06 5.89e-06 6.87e-06 9.09e-07

Tm-171 5.98e-06 5.04e-06 2.23e-06 4.69e-07 3.44e-08 7.48e-09 5.21e-07 4.59e-07 3.00e-07 4.03e-07 9.06e-08

Ta-182 5.90e-02 6.42e-02 9.47e-03 1.71e-03 1.36e-04 1.29e-02 9.57e-03 9.85e-03 4.89e-03 3.03e-03 2.35e-04

W-181 4.31e-04 3.65e-04 1.47e-04 3.30e-05 2.44e-06 8.07e-07 4.03e-05 3.56e-05 2.28e-05 3.17e-05 6.18e-06

W-185 3.82e-06 3.33e-06 6.58e-07 2.32e-07 1.77e-08 2.40e-07 4.81e-07 3.96e-07 2.83e-07 3.11e-07 4.01e-08

Os-185 3.01e-02 3.19e-02 5.05e-03 9.85e-04 7.77e-05 6.48e-03 4.96e-03 5.11e-03 2.62e-03 1.76e-03 1.38e-04

Ir-192 3.48e-02 3.58e-02 5.64e-03 1.28e-03 1.01e-04 7.05e-03 5.84e-03 5.96e-03 3.18e-03 2.34e-03 1.78e-04

Tl-204 3.35e-05 2.95e-05 6.63e-06 2.07e-06 1.58e-07 1.67e-06 4.16e-06 3.55e-06 2.38e-06 2.79e-06 3.48e-07

Pb-210 5.52e-05 4.92e-05 1.23e-05 3.19e-06 2.40e-07 5.49e-06 6.88e-06 5.72e-06 4.13e-06 3.91e-06 5.71e-07

Bi-207 7.01e-02 7.53e-02 1.14e-02 2.13e-03 1.69e-04 1.53e-02 1.15e-02 1.18e-02 5.96e-03 3.82e-03 2.94e-04

Po-210 4.54e-07 4.86e-07 7.44e-08 1.39e-08 1.10e-09 1.01e-07 7.49e-08 7.73e-08 3.91e-08 2.52e-08 1.90e-09

Ra-226 8.13e-02 8.87e-02 1.27e-02 2.34e-03 1.86e-04 1.79e-02 1.33e-02 1.37e-02 6.81e-03 4.20e-03 3.19e-04

Ra-228 4.01e-02 4.32e-02 6.44e-03 1.20e-03 9.53e-05 8.82e-03 6.57e-03 6.77e-03 3.40e-03 2.16e-03 1.65e-04

Ac-227 1.60e-02 1.62e-02 2.63e-03 6.38e-04 5.01e-05 2.90e-03 2.64e-03 2.65e-03 1.44e-03 1.13e-03 9.14e-05

Th-228 6.83e-02 7.65e-02 1.02e-02 1.82e-03 1.46e-04 1.49e-02 1.10e-02 1.14e-02 5.57e-03 3.22e-03 2.47e-04

Th-229 1.14e-02 1.16e-02 1.90e-03 4.44e-04 3.48e-05 2.01e-03 1.83e-03 1.84e-03 9.85e-04 7.66e-04 6.43e-05

Th-230 8.14e-06 7.46e-06 1.97e-06 4.80e-07 3.67e-08 5.82e-07 1.09e-06 1.03e-06 5.99e-07 6.56e-07 8.20e-08

Th-232 3.36e-06 2.96e-06 1.08e-06 2.28e-07 1.71e-08 1.12e-07 3.85e-07 3.52e-07 2.13e-07 2.65e-07 4.28e-08

Pa-231 1.30e-03 1.31e-03 2.15e-04 5.19e-05 4.07e-06 2.41e-04 2.16e-04 2.18e-04 1.18e-04 9.28e-05 7.46e-06

U-232 5.26e-06 4.83e-06 1.55e-06 3.11e-07 2.36e-08 4.09e-07 6.98e-07 6.62e-07 3.85e-07 4.04e-07 5.80e-08

U-233 7.08e-06 6.85e-06 1.51e-06 3.42e-07 2.64e-08 9.44e-07 1.08e-06 1.06e-06 5.95e-07 5.31e-07 5.61e-08

U-234 2.42e-06 2.16e-06 9.64e-07 1.59e-07 1.19e-08 1.22e-07 2.86e-07 2.66e-07 1.58e-07 1.76e-07 3.33e-08

U-235 5.84e-03 5.65e-03 1.01e-03 2.73e-04 2.14e-05 7.71e-04 9.34e-04 9.12e-04 5.14e-04 4.67e-04 4.11e-05

U-236 1.17e-06 1.02e-06 6.65e-07 8.45e-08 6.23e-09 4.21e-08 1.18e-07 1.09e-07 6.62e-08 7.40e-08 2.06e-08

U-238 1.24e-03 1.28e-03 1.99e-04 4.49e-05 3.53e-06 2.28e-04 1.93e-04 1.91e-04 1.03e-04 7.53e-05 6.59e-06

Np-237 8.65e-03 8.66e-03 1.42e-03 3.59e-04 2.82e-05 1.49e-03 1.42e-03 1.42e-03 7.77e-04 6.33e-04 5.18e-05

Pu-236 1.10e-06 9.59e-07 8.38e-07 8.25e-08 5.97e-09 5.52e-08 9.39e-08 8.93e-08 5.24e-08 5.27e-08 2.38e-08

Pu-238 6.69e-07 5.58e-07 6.87e-07 5.67e-08 4.04e-09 1.67e-08 4.04e-08 3.77e-08 2.29e-08 2.44e-08 1.86e-08

Pu-239 2.08e-06 2.00e-06 6.15e-07 1.05e-07 8.02e-09 2.73e-07 2.98e-07 2.94e-07 1.63e-07 1.43e-07 2.02e-08

Pu-240 6.55e-07 5.43e-07 6.61e-07 5.59e-08 3.98e-09 1.40e-08 3.90e-08 3.61e-08 2.22e-08 2.42e-08 1.81e-08

Pu-241 3.85e-08 3.56e-08 6.70e-09 2.12e-09 1.65e-10 2.49e-09 5.60e-09 5.25e-09 3.06e-09 3.36e-09 3.25e-10

Pu-242 5.85e-07 4.89e-07 5.54e-07 4.87e-08 3.48e-09 1.34e-08 3.87e-08 3.58e-08 2.19e-08 2.41e-08 1.53e-08

Pu-244 1.48e-02 1.58e-02 2.41e-03 4.72e-04 3.73e-05 3.21e-03 2.45e-03 2.52e-03 1.29e-03 8.54e-04 6.51e-05

Am-241 2.51e-04 2.13e-04 8.82e-05 1.92e-05 1.42e-06 4.47e-07 2.34e-05 2.07e-05 1.32e-05 1.85e-05 3.65e-06

Am-242m 4.80e-04 4.64e-04 8.55e-05 2.31e-05 1.80e-06 5.05e-05 7.14e-05 6.87e-05 3.83e-05 3.69e-05 3.56e-06

Am-243 6.54e-03 6.28e-03 1.14e-03 3.21e-04 2.50e-05 7.65e-04 1.00e-03 9.73e-04 5.50e-04 5.22e-04 4.85e-05

Cm-242 7.10e-07 5.94e-07 7.78e-07 6.02e-08 4.24e-09 2.84e-08 3.64e-08 3.53e-08 2.06e-08 1.84e-08 2.09e-08

Cm-243 4.17e-03 4.08e-03 6.79e-04 1.89e-04 1.48e-05 5.84e-04 6.70e-04 6.59e-04 3.68e-04 3.27e-04 2.76e-05

Cm-244 5.92e-07 4.96e-07 6.60e-07 5.02e-08 3.53e-09 2.49e-08 2.99e-08 2.92e-08 1.69e-08 1.47e-08 1.76e-08

Cm-245 2.62e-03 2.44e-03 4.41e-04 1.39e-04 1.08e-05 2.03e-04 3.90e-04 3.69e-04 2.14e-04 2.26e-04 2.10e-05

Cm-246 3.53e-07 2.75e-07 5.12e-07 3.56e-08 2.45e-09 2.34e-12 3.60e-09 3.16e-09 2.62e-09 2.58e-09 1.35e-08

Cm-247 1.40e-02 1.44e-02 2.30e-03 5.22e-04 4.10e-05 2.80e-03 2.34e-03 2.39e-03 1.27e-03 9.47e-04 7.34e-05

Cm-248 3.25e-07 2.52e-07 4.73e-07 3.27e-08 2.26e-09 1.87e-12 3.10e-09 2.72e-09 2.28e-09 2.21e-09 1.25e-08

Bk-249 5.96e-08 5.22e-08 1.64e-08 3.92e-09 2.88e-10 4.77e-09 6.26e-09 5.73e-09 3.68e-09 3.45e-09 8.47e-10

Cf-248 9.53e-07 8.01e-07 7.89e-07 7.58e-08 5.44e-09 1.97e-08 6.61e-08 6.11e-08 3.71e-08 4.18e-08 2.31e-08

Cf-249 1.37e-02 1.41e-02 2.22e-03 5.09e-04 4.01e-05 2.79e-03 2.31e-03 2.36e-03 1.26e-03 9.33e-04 7.12e-05

Cf-250 4.02e-07 3.11e-07 5.73e-07 4.01e-08 2.75e-09 7.51e-13 1.80e-09 1.58e-09 1.77e-09 1.20e-09 1.54e-08

Cf-251 3.57e-03 3.43e-03 5.80e-04 1.73e-04 1.35e-05 4.15e-04 5.62e-04 5.43e-04 3.09e-04 2.93e-04 2.55e-05

Cf-252 8.28e-07 7.04e-07 6.54e-07 6.37e-08 4.58e-09 2.78e-08 6.29e-08 5.89e-08 3.53e-08 3.76e-08 1.91e-08

Cf-254 8.26e-01 8.91e-01 1.34e-01 2.43e-02 1.93e-03 1.85e-01 1.36e-01 1.40e-01 7.01e-02 4.40e-02 3.33e-03

Es-254 4.26e-02 4.61e-02 6.87e-03 1.23e-03 9.78e-05 9.53e-03 6.96e-03 7.18e-03 3.58e-03 2.21e-03 1.68e-04
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-100

Table C.88 Dose coefficients for external exposure in concrete scenarios (:Sv/h per Bq/g)

Nuclide Effective dose equivalent Effective dose

Concrete pile Concrete truck Concrete pile Concrete truck

H-3 0.00e+00 0.00e+00 0.00e+00 0.00e+00

C-14 1.35e-07 1.56e-08 1.44e-07 1.27e-08

Na-22 1.60e-01 2.55e-02 1.61e-01 2.39e-02

P-32 1.47e-04 2.48e-05 1.48e-04 2.27e-05

S-35 1.49e-07 1.76e-08 1.58e-07 1.45e-08

Cl-36 2.79e-05 4.64e-06 2.81e-05 4.23e-06

K-40 1.21e-02 1.84e-03 1.22e-02 1.73e-03

Ca-41 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Ca-45 6.83e-07 9.58e-08 7.04e-07 8.20e-08

Sc-46 1.49e-01 2.36e-02 1.51e-01 2.21e-02

Cr-51 2.05e-03 3.57e-04 2.06e-03 3.30e-04

Mn-53 0.00e+00 0.00e+00 0.00e+00 0.00e+00

Mn-54 6.08e-02 9.79e-03 6.14e-02 9.18e-03

Fe-55 7.39e-12 1.30e-12 7.40e-12 1.18e-12

Fe-59 8.96e-02 1.39e-02 9.03e-02 1.31e-02

Co-56 2.74e-01 4.15e-02 2.75e-01 3.89e-02

Co-57 5.47e-03 9.56e-04 5.48e-03 8.67e-04

Co-58 7.02e-02 1.14e-02 7.08e-02 1.07e-02

Co-60 1.90e-01 2.94e-02 1.92e-01 2.76e-02

Ni-59 1.10e-06 1.85e-07 1.11e-06 1.72e-07

Ni-63 2.30e-09 8.86e-11 2.84e-09 5.91e-11

Zn-65 4.34e-02 6.79e-03 4.37e-02 6.38e-03

As-73 8.67e-05 1.09e-05 9.00e-05 8.63e-06

Se-75 2.24e-02 3.93e-03 2.25e-02 3.62e-03

Sr-85 3.39e-02 5.68e-03 3.42e-02 5.29e-03

Sr-89 1.13e-04 1.90e-05 1.13e-04 1.74e-05

Sr-90 3.08e-04 5.16e-05 3.11e-04 4.74e-05

Y-91 3.88e-04 6.18e-05 3.91e-04 5.76e-05

Zr-93 2.68e-09 1.04e-10 3.31e-09 7.03e-11

Zr-95 5.27e-02 8.58e-03 5.32e-02 8.03e-03

Nb-93m 6.20e-07 2.48e-11 9.12e-07 1.38e-11

Nb-94 1.13e-01 1.83e-02 1.14e-01 1.71e-02

Nb-95 5.52e-02 8.96e-03 5.57e-02 8.39e-03

Mo-93 3.35e-06 2.66e-11 4.94e-06 1.71e-11

Tc-97 4.56e-06 1.57e-10 6.65e-06 6.98e-11

Tc-97m 1.61e-05 1.91e-06 1.82e-05 1.70e-06

Tc-99 1.41e-06 2.08e-07 1.44e-06 1.80e-07

Ru-103 3.41e-02 5.72e-03 3.43e-02 5.32e-03

Ru-106 1.53e-02 2.51e-03 1.54e-02 2.34e-03

Ag-108m 1.13e-01 1.87e-02 1.14e-01 1.74e-02

Ag-110m 2.00e-01 3.18e-02 2.01e-01 2.99e-02

Cd-109 1.34e-04 1.77e-05 1.43e-04 1.56e-05

Sn-113 1.71e-02 2.93e-03 1.72e-02 2.72e-03

Sb-124 1.39e-01 2.16e-02 1.40e-01 2.02e-02

Sb-125 2.90e-02 4.85e-03 2.92e-02 4.51e-03

Te-123m 7.01e-03 1.24e-03 7.03e-03 1.13e-03

Te-127m 3.70e-04 5.86e-05 3.79e-04 5.40e-05

I-125 1.16e-04 2.56e-06 1.43e-04 1.35e-06

I-129 9.59e-05 3.84e-06 1.14e-04 2.41e-06

I-131 2.53e-02 4.34e-03 2.55e-02 4.02e-03

Cs-134 1.11e-01 1.82e-02 1.12e-01 1.70e-02

Cs-135 9.96e-07 1.43e-07 1.02e-06 1.23e-07

Cs-137 3.99e-02 6.55e-03 4.03e-02 6.13e-03

Ba-133 2.28e-02 3.91e-03 2.29e-02 3.61e-03

Ce-139 7.11e-03 1.25e-03 7.14e-03 1.14e-03

Ce-141 3.54e-03 6.23e-04 3.55e-03 5.68e-04

Ce-144 3.46e-03 5.47e-04 3.48e-03 5.07e-04

Pm-147 5.37e-07 7.77e-08 5.53e-07 6.73e-08
Appendix C External Exposure Dose Coefficients

Table C.88 Dose coefficients for external exposure in concrete scenarios (:Sv/h per Bq/g)

Nuclide Effective dose equivalent Effective dose

Concrete pile Concrete truck Concrete pile Concrete truck

C-101 NUREG-1640

Sm-151 1.06e-08 2.28e-10 1.39e-08 1.57e-10

Eu-152 8.34e-02 1.32e-02 8.40e-02 1.24e-02

Eu-154 8.13e-02 1.28e-02 8.20e-02 1.20e-02

Eu-155 1.90e-03 3.10e-04 1.90e-03 2.74e-04

Gd-153 2.50e-03 3.86e-04 2.54e-03 3.37e-04

Tb-160 8.14e-02 1.30e-02 8.21e-02 1.21e-02

Tm-170 1.24e-04 1.92e-05 1.24e-04 1.67e-05

Tm-171 9.95e-06 1.31e-06 1.02e-05 1.05e-06

Ta-182 9.28e-02 1.45e-02 9.35e-02 1.36e-02

W-181 7.15e-04 9.85e-05 7.27e-04 8.07e-05

W-185 4.65e-06 7.38e-07 4.70e-06 6.52e-07

Os-185 4.68e-02 7.65e-03 4.72e-02 7.14e-03

Ir-192 5.37e-02 9.20e-03 5.40e-02 8.54e-03

Tl-204 4.66e-05 7.33e-06 4.64e-05 6.40e-06

Pb-210 6.77e-05 1.00e-05 6.96e-05 8.71e-06

Bi-207 1.10e-01 1.75e-02 1.10e-01 1.64e-02

Po-210 7.05e-07 1.14e-07 7.12e-07 1.07e-07

Ra-226 1.28e-01 2.00e-02 1.29e-01 1.87e-02

Ra-228 6.27e-02 9.98e-03 6.32e-02 9.35e-03

Ac-227 2.48e-02 4.25e-03 2.49e-02 3.92e-03

Th-228 1.11e-01 1.65e-02 1.11e-01 1.54e-02

Th-229 1.77e-02 2.96e-03 1.78e-02 2.73e-03

Th-230 1.30e-05 2.08e-06 1.31e-05 1.85e-06

Th-232 5.45e-06 8.12e-07 5.55e-06 6.99e-07

Pa-231 2.01e-03 3.47e-04 2.01e-03 3.21e-04

U-232 8.40e-06 1.31e-06 8.65e-06 1.17e-06

U-233 1.11e-05 1.85e-06 1.13e-05 1.68e-06

U-234 3.90e-06 5.61e-07 4.12e-06 4.93e-07

U-235 9.10e-03 1.59e-03 9.14e-03 1.45e-03

U-236 1.90e-06 2.39e-07 2.09e-06 2.07e-07

U-238 1.84e-03 2.94e-04 1.85e-03 2.72e-04

Np-237 1.34e-02 2.32e-03 1.35e-02 2.13e-03

Pu-236 1.79e-06 1.81e-07 2.09e-06 1.58e-07

Pu-238 1.09e-06 8.11e-08 1.36e-06 7.01e-08

Pu-239 3.27e-06 5.09e-07 3.40e-06 4.62e-07

Pu-240 1.07e-06 8.08e-08 1.32e-06 6.90e-08

Pu-241 6.11e-08 1.04e-08 6.11e-08 9.39e-09

Pu-242 9.57e-07 7.90e-08 1.16e-06 6.81e-08

Pu-244 2.30e-02 3.74e-03 2.32e-02 3.50e-03

Am-241 4.16e-04 5.71e-05 4.24e-04 4.68e-05

Am-242m 7.56e-04 1.25e-04 7.61e-04 1.14e-04

Am-243 1.03e-02 1.76e-03 1.03e-02 1.59e-03

Cm-242 1.16e-06 6.77e-08 1.48e-06 5.93e-08

Cm-243 6.51e-03 1.13e-03 6.52e-03 1.04e-03

Cm-244 9.67e-07 5.45e-08 1.24e-06 4.81e-08

Cm-245 4.14e-03 7.14e-04 4.14e-03 6.44e-04

Cm-246 5.88e-07 1.08e-08 8.08e-07 7.83e-09

Cm-247 2.16e-02 3.70e-03 2.17e-02 3.43e-03

Cm-248 5.40e-07 9.34e-09 7.44e-07 6.76e-09

Bk-249 7.68e-08 1.04e-08 8.07e-08 9.14e-09

Cf-248 1.56e-06 1.30e-07 1.88e-06 1.15e-07

Cf-249 2.12e-02 3.65e-03 2.13e-02 3.38e-03

Cf-250 6.69e-07 5.79e-09 9.28e-07 3.93e-09

Cf-251 5.59e-03 9.77e-04 5.60e-03 8.89e-04

Cf-252 1.35e-06 1.20e-07 1.61e-06 1.06e-07

Cf-254 1.29e+00 2.05e-01 1.30e+00 1.93e-01

Es-254 6.64e-02 1.05e-02 6.71e-02 9.86e-03
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-102

References

American Nuclear Society. 1987. “Calculation and Measurement of Direct and Scattered Gamma

Radiation from LWR Nuclear Power Plants,”ANSI/ANS 6.6.1-1987. Author. 

Anigstein, R., et al. 2001. “Technical Support Document: Potential Recycling of Scrap Metal

from Nuclear Facilities, Part I: Radiological Assessment of Exposed Individuals.” Washington,

DC: U.S. Environmental Protection Agency, Office of Radiation and Indoor Air.

http://www.epa.gov/radiation/cleanmetals/docs/tsd/scrap_tsd_041802_vol1cvr_toc1.pdf

(August 12, 2002).

Brezonick, M. 1999. “New Technology Means Greater Precision, Capabilities for Engine

Castings Manufacturer.” Diesel Progress, North American Edition, March 1999.

Briesmeister, J. F. (Ed.) 2000. “MCNP - A General Monte Carlo N-Particle Transport Code,

Version 4C,” LA-13709-M. Los Alamos, NM: Los Alamos National Laboratory.

Eckerman, K. F., and J. C. Ryman. 1993. “External Exposure to Radionuclides in Air, Water,

and Soil,” Federal Guidance Report No. 12, EPA 402-R-93-081. Washington, DC: U.S.

Environmental Protection Agency, Office of Radiation and Indoor Air.

Eckerman, K. F. (Oak Ridge National Laboratory). 2002. <eckermankf@ornl.gov> “Re:

Electron bremsstrahlung data” July 26, 2002, personal e-mail to Robert Anigstein, SC&A, Inc.

General Motors Corp. (n/d). “2002 Chevrolet Impala.”

http://www.chevrolet.com/impala/features.htm (March 9, 2002).

GMPartsDirect.com. (n/d). “Chevy 90-Degree V6."

http://www.gmpartsdirect.com/performance_parts/store/catalog/Category.jhtml¿CATID=274.ht

ml (February 18, 2002)

International Commission on Radiological Protection (ICRP). 1977. “Recommendations of the

ICRP,” ICRP Publication 26. Annals of the ICRP, 1(3). Oxford: Pergamon Press.

International Commission on Radiation Protection (ICRP). 1987. “Data for Use in Protection

Against External Radiation,” ICRP Publication 51. Annals of the ICRP, 17 (2/3). Oxford:

Pergamon Press.

International Commission on Radiological Protection (ICRP). 1991. “1990 Recommendations of

the ICRP,” ICRP Publication 60. Annals of the ICRP, 21(1-3). Oxford: Pergamon Press.

International Commission on Radiological Protection (ICRP). 1996. “Conversion Coefficients

for use in Radiological Protection against External Radiation,” ICRP Publication 74. Annals of

the ICRP, 26 (3/4). Tarrytown, NY: Elsevier Science, Inc.
Appendix C External Exposure Dose Coefficients

C-103 NUREG-1640

Kenworth Truck Company, a division of PACCAR, Inc. 2001. “T2000," sales brochure.

http://www.kenworth.com/brochures/T2000.pdf (March 31, 2002)

Kramer, R., et al. 1982. “The Calculation of Dose from External Photon Exposures Using

Reference Human Phantoms and Monte Carlo Methods, Part I: The Male (Adam) and Female

(Eva) Adult Mathematical Phantoms,” GSF-Bericht S-885. Munich, Germany: GSF – National

Research Center for Environment and Health.

Lide, D. R. (Ed.) 1995. CRC Handbook of Chemistry and Physics (76th ed.) Boca Raton, FL:

CRC Press.

Logan, S. E. 1993. “Risk Assessment of Options for Disposition of EAF Dust Following a

Meltdown Incident of Radioactive Cesium Source in Scrap Steel,” SELA-9301. Santa Fe, NM:

S. E. Logan and Associates, Inc. (U.S. Nuclear Regulatory Commission Public Document Room

[PDR]: ADAMS Accession Number ML031990418.)

Los Alamos National Laboratory (LANL). 2001. MCNP4C: Monte Carlo N-Particle Transport

Code System, RSICC Computer Code Collection [Computer software and manual]. Oak Ridge,

TN: Oak Ridge National Laboratory.

McKenzie-Carter, M.A., et al. 1995. “Dose Evaluation of the Disposal of Electric Arc Furnace

Dust Contaminated by an Accidental Melting of a Cs-137 Source,” Draft Final, SAIC95/2467&01. Idaho Falls, ID: Science Applications International Corporation.

Nabelssi, B. K. 1993. “Calculations of Dose Equivalent Quantities for High-Energy Neutrons

using Homogeneous and Heterogeneous Phantoms,” doctoral dissertation, The University of

Texas, Austin.

Snyder, W. S., et al. 1969. “Estimates of Absorbed Fractions for Monoenergetic Photon Sources

Uniformly Distributed in Various Organs of a Heterogeneous Phantom,” Medical Internal

Radiation Dose (MIRD) Pamphlet No. 5. New York: Society of Nuclear Medicine.

Snyder, W. S., M. R. Ford, and G. G. Warner. 1978. “Estimates of Specific Absorbed Fractions

for Photon Sources Uniformly Distributed in Various Organs of a Heterogeneous Phantom,”

Medical Internal Radiation Dose (MIRD) Pamphlet No. 5, Revised. New York: Society of

Nuclear Medicine.

South St. Paul Steel Supply Co., Inc. 2004. “Hot Rolled Steel Products.” South St. Paul, MN.

http://www.sspss.com (May 6, 2004).

Storm, E., and H. I. Israel. 1970. “Photon Cross Sections from 1 keV to 100 MeV for Elements

Z = 1 to Z = 100.” Nuclear Data Tables, A7, 565-681.

Tanner, J. E. 1988. “The Effect of Gender and Remainder on Effective Dose Equivalent,” Trans.

Amer. Nucl. Soc. 57, 217–218.
External Exposure Dose Coefficients Appendix C

NUREG-1640 C-104

Tokai Research Establishment, JAERI. 2001. DECDC 1.0: Nuclear Decay Data Files for

Radiation Dosimetry Calculations, DLC-213, RSICC Data Library Collection [Computer

software and manual]. Oak Ridge, TN: Oak Ridge National Laboratory.

Yielding, B. (Heil Trailer International). 2002. <byielding@Heiltrailer.com> “RE: FW: PDF”

March 18, 2002, personal e-mail to Robert Anigstein, SC&A, Inc.

Zankl, M., N. Petoussi, and G. Drexler. 1992. “Effective Dose and Effective Dose EquivalentThe Impact of the New ICRP Definitions for External Photon Irradiation,” Health Physics 62(5),

395–399.
APPENDIX D

MIXING OF CLEARED MATERIALS

Appendix D Mixing of Cleared Materials

D-iii NUREG-1640

CONTENTS

Page

Appendix D Mixing of Cleared Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-1

D.1 Mixing Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-1

D.2 Calculation of Mixing Factors for Steel Scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-2

D.2.1 Annual-Average Mixing Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-2

D.2.1.1 Disposal in Municipal or Industrial Landfills . . . . . . . . . . . . . . . . . . . . . . . . D-2

D.2.1.2 Scrap Processing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-4

D.2.2 Maximum Single-Heat Mixing Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-7

D.3 Calculation of Mixing Factors for Copper Scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-8

D.3.1 Processing of Copper Scrap by Scrap Dealers . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-9

D.3.2 Fire-Refining of Copper Scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-10

D.4 Calculation of Mixing Factors for Aluminum Scrap . . . . . . . . . . . . . . . . . . . . . . . . . . . D-13

D.4.1 Processing of Aluminum Scrap by Scrap Dealers . . . . . . . . . . . . . . . . . . . . . . . . D-13

D.4.2 Secondary Smelter Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-14

D.4.2.1 Annual-Average Mixing Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-14

D.4.2.2 Maximum Single-Heat Mixing Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-15

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-16

Figure

D.1 Distribution of nonferrous metal scrap dealers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-10

Tables

D.1 Annual waste streams of municipal landfills . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-3

D.2 Annual waste streams of industrial landfills . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-4

D.3 Annual throughput of ferrous metal scrap dealers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-5

D.4 Annual scrap consumption of BOF mills (tons/y) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-6

D.5 Annual scrap consumption of EAF mills . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-6

D.6 Annual scrap consumption of iron and steel foundries . . . . . . . . . . . . . . . . . . . . . . . . . . D-7

D.7 Annual capacities of U.S. secondary copper fire refineries . . . . . . . . . . . . . . . . . . . . . . D-10

D.8 Reactor dismantlement schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-12

D.9 Annual number of reactors undergoing dismantlement . . . . . . . . . . . . . . . . . . . . . . . . . D-13

D.10 Annual capacities of U.S. secondary aluminum smelters . . . . . . . . . . . . . . . . . . . . . . D-14

D.11 Sizes of reverberatory furnaces at U.S. secondary aluminum smelters . . . . . . . . . . . D-15

Appendix D Mixing of Cleared Materials

D-1 NUREG-1640

D MIXING OF CLEARED MATERIALS

The goal of the analysis of clearance of material is to develop realistic exposure scenarios based

on actual industry practices. The mixing of scrap metal and concrete, cleared from nuclear

facilities, with similar materials from non-nuclear facilities, could significantly decrease the

concentrations of residually radioactive materials in the process streams. In the present analysis,

various degrees of mixing are assumed to occur at each stage of the processing or disposal of

cleared materials. For example, steel scrap from a nuclear facility is transported to a scrap

dealer, where it is mixed with scrap from other sources. Scrap melted in a steel mill or foundry

is charged to the furnace together with metal from other sources.

Mixing of cleared material reduces the radiological impacts from recycling and disposal in a

linear fashion (i.e., a 10-fold mixing would result in a 10-fold reduction in the normalized doses

from a given scenario).

D.1 Mixing Factors

A mixing factor is defined as the ratio of cleared material to the total amount of material in a

given process stream. Two general types of mixing factors are developed for use with different

exposure scenarios. For situations in which an individual is exposed to a steady stream of

residually radioactive material, the radiological assessment is based on annual-average

radionuclide concentrations. Although the activity levels would vary among individual batches

of material, the radiation dose to that individual during the assessment period (one year in most

cases) would be the same as if the radionuclide concentrations were constant. These

concentrations in turn depend on the average fraction of cleared materials in a given process

stream. This fraction is called the “annual-average” mixing factor.

In most of the product-use scenarios in the present analysis, an individual is exposed to a single

product over an extended period of time. An example would be the owner-operator of a

commercial truck with a diesel engine block made from cast iron. The cast iron is assumed to be

made from iron and steel scrap, including scrap from nuclear facilities. Since a diesel engine

would be in use for more than one year, this individual would be exposed to a single source of

activity, which would vary only with the decay of radionuclides initially present in the cast iron,

and the ingrowth of the radioactive progenies of these nuclides, as discussed in Appendix E of

the present report. In such a case, the annual-average mixing factor is no longer applicable. Due

to the random variation of scrap sources used by a given iron foundry, some furnace heats would

include scrap with a higher-than-average mixing factor, while others would have lower-thanaverage fractions of cleared scrap. A “maximum single-heat” mixing factor is defined as the

highest likely fraction of cleared scrap in any single heat over the course of one year at a given

melt shop. The same concept applies to the analysis of other products made from cleared

materials.
Mixing of Cleared Materials Appendix D

1

 It is assumed that scrap or furnace by-products would be sent only to landfills with waste streams at least equal to

the mass of materials requiring disposal.

2

 See Section B.2.6 for a discussion of custom distributions constructed for the present analysis.

3

 Landfill data for the other six states did not distinguish between municipal and industrial landfills. Landfills not

explicitly identified as industrial or C&D were classified as MSW.

NUREG-1640 D-2

D.2 Calculation of Mixing Factors for Steel Scrap

The sources of cleared steel scrap are discussed in Section 3.2.1 of the main report. The mixing

factors for the various process streams are discussed in the following sections.

D.2.1 Annual-Average Mixing Factors

In calculating annual-average mixing factors, we assume that, once they leave the nuclear

facility, cleared materials would be indistinguishable from similar materials from non-nuclear

sources. The same assumption applies to cleared materials that have been processed or recycled. 

Consequently, these materials are assumed to join the nationwide stream of similar materials,

whether it be steel scrap destined for recycling at steel mills or foundries, or scrap, slag, dust, or

other by-products destined for landfill disposal or other uses.

We assume that all the material cleared in one year from a given nuclear facility is conveyed to a

single facility for processing, disposal, or recycling. Each facility is selected by random

sampling from a weighted distribution of such facilities (e.g., scrap processors, landfills, or steel

mills and foundries). The construction of these distributions is discussed in more detail in the

following sections.

D.2.1.1 Disposal in Municipal or Industrial Landfills

As discussed in Section 3.4.2.3 of the main report, the analyses of the landfill disposal of cleared

scrap, slag, or BOF/foundry dust include the assumption that one year’s material from a given

nuclear power plant or melt shop would be emplaced in a single landfill, commingled with other

wastes received at that landfill over the course of a year. The mixing factor for the scrap or byproduct is determined by dividing the quantity of such material by the annual quantity of wastes

received by a given landfill.1

 A discrete distribution2 of waste streams is constructed from data

on 814 municipal solid waste (MSW) landfills in 10 states: California, Illinois, Michigan,

Nebraska, New Jersey, New York, North Carolina, Ohio, South Carolina, and Wisconsin. A

second discrete distribution, used to determine mixing factors for scrap or dust disposed of in

industrial landfills, is constructed using data on 98 industrial and construction and demolition

(C&D) landfills in 4 states: Michigan, New Jersey, North Carolina and Ohio.3

The first step in constructing the distribution is ranking all the landfills of a given type (i.e.,

MSW or industrial) in order of annual quantity of waste received. The landfills are then grouped

by waste stream interval—the first column of Table D.1 shows the upper bound of each interval
Appendix D Mixing of Cleared Materials

D-3 NUREG-1640

for the case of municipal landfills. The number of landfills in each interval is listed in the

second column, while the third column shows the average waste stream of these landfills. The

total waste stream of all the landfills in the interval is listed in the fourth column, while the fifth

column lists the cumulative waste stream of each successive interval. The last column lists the

cumulative waste stream as a percentage of the total waste stream of all the landfills listed in the

table. These last values constitute a cumulative distribution function (CDF) of the annual waste

streams of MSW landfills. Similar data for industrial landfills are shown in Table D.2.

Table D.1 Annual waste streams of municipal landfills (tons)

Waste stream

intervala No. landfills Average waste

stream

Total waste

per interval

Cumulative 

waste stream CDF (%)

100 10 27 267 267 0.00010

250 4 170 679 946 0.00035

500 3 400 1,200 2,146 0.00080

1,000 7 732 5,125 7,271 0.0027

2,500 19 1,743 33,113 40,384 0.0150

5,000 17 3,635 61,798 102,182 0.0379

10,000 24 7,324 175,771 277,953 0.103

25,000 106 17,083 1,810,754 2,088,707 0.775

50,000 104 34,681 3,606,803 5,695,510 2.114

100,000 116 75,678 8,778,685 14,474,194 5.373

125,000 36 111,128 4,000,622 18,474,817 6.858

150,000 39 137,001 5,343,040 23,817,856 8.841

200,000 73 177,376 12,948,475 36,766,331 13.648

300,000 88 245,263 21,583,153 58,349,485 21.659

500,000 70 380,242 26,616,958 84,966,442 31.540

1,000,000 51 706,171 36,014,725 120,981,167 44.908

2,000,000 29 1,311,179 38,024,193 159,005,360 59.023

3,000,000 9 2,462,894 22,166,050 181,171,410 67.251

4,000,000 3 3,411,066 10,233,197 191,404,607 71.050

5,000,000 2 4,225,619 8,451,237 199,855,844 74.187

6,000,000 1 5,337,441 5,337,441 205,193,285 76.168

7,000,000 1 6,792,024 6,792,024 211,985,309 78.689

25,000,000 1 20,949,781 20,949,781 232,935,090 86.466

40,000,000 1 36,460,691 36,460,691 269,395,781 100.000

Total 814 269,395,781

a

 Upper bound of interval

The CDFs are used to construct a discrete distribution that is used to generate an array of annual

waste streams that serves as an input to the probabilistic calculations. The frequency with which

the average annual waste stream of a given interval appears in the array is proportional to the

total waste stream of that interval. Thus, the likelihood that a given batch of material would be

disposed of in a landfill with a given waste stream depends on the magnitude of that waste
Mixing of Cleared Materials Appendix D

4

 It is assumed that the cleared scrap would be consigned only to a dealer whose annual throughput is greater than

or equal to the amount of cleared scrap in given realization. 

NUREG-1640 D-4

stream and on the number of landfills having waste streams that fall into the same interval. To

give a concrete example, Table D.1 lists 88 MSW landfills that receive between 200,000 and

300,000 tons of waste per year. The average waste stream of these landfills is 245,263.1 tons per

year, for a total waste stream of 21,583,153 tons per year (245,263.1 × 88 = 21,583,153). This

tonnage constitutes 8.01% of the total waste stream of all MSW landfills listed: 269,395,781

tons per year. (The value of 8.01% is the difference between the CDF for the 200,000 – 300,000

ton/y interval and the CDF for the previous interval: 21.66% ! 13.65% = 8.01%). Therefore, in

the analysis of the scenarios that model the disposal of scrap metal in an MSW landfill, the scrap

cleared in one year is diluted into a total waste stream of 245,263.1 tons in about 8% of the

realizations.

Table D.2 Annual waste streams of industrial landfills (tons)

Waste stream

intervala No. landfills Average wastestream

Total waste

per interval

Cumulative 

waste stream CDF (%)

100 2 2 4 4 0.00005

1,000 4 717 2,870 2,874 0.03529

2,500 2 2243 4,486 7,360 0.09037

5,000 12 3,679 44,150 51,510 0.63248

10,000 11 6785 74,638 126,148 1.54895

25,000 17 17,666 300,314 426,461 5.23645

50,000 18 34,842 627,155 1,053,616 12.93719

100,000 14 72,842 1,019,783 2,073,399 25.45895

125,000 2 107,435 214,871 2,288,270 28.09731

150,000 2 140,158 280,317 2,568,587 31.53928

200,000 5 164,942 824,710 3,393,296 41.66576

300,000 4 235,490 941,960 4,335,257 53.23195

500,000 2 355,795 711,590 5,046,847 61.96946

1,000,000 2 641,939 1,283,879 6,330,726 77.73401

2,000,000 1 1,813,362 1,813,362 8,144,088 100.00000

Total 98 8,144,088

a

 Upper bound of interval

D.2.1.2 Scrap Processing

In analyzing the scrap handling scenario, we assume that all the steel scrap cleared during the

dismantlement of a commercial nuclear power plant during one year is processed by a single

scrap dealer.4

 No data on the annual volume of scrap processed by individual dealers could be

obtained in the course of the present analysis. However, a 1997 economic census (Bureau of the

Census 2000) presents data on sales revenues of ferrous scrap dealers and brokers, listing the

number of dealers in each revenue range (e.g., <$100,000/y, $100,000/y – $249,000/y, etc.), as

well as the total revenue for dealers in each range. These data are listed in Table D.3. Fenton
Appendix D Mixing of Cleared Materials

5

 See Note 2 on page D-2.

6

 It is assumed that the cleared scrap would be melted only at a melt shop whose annual capacity is greater than or

equal to the amount of cleared scrap in given realization. 

D-5 NUREG-1640

(1998) reported that a total of 52 Mt of ferrous scrap was handled by dealers and brokers in

1997. Dividing the total revenue listed in Table D.3 by the cited throughput of ferrous scrap

yields an average price of $340.28/t. These data enable an estimate of the average annual

tonnage handled by the individual dealers in each revenue range. A CDF of scrap dealer

throughput is constructed in the same manner as is described for the landfills discussed in

Section D.2.1.1. This CDF is used to construct a continuous cumulative distribution, rather than

a discrete distribution, as was the case for the landfills.5 Mixing factors are determined by

dividing the amount of scrap cleared in one year by the average amount of scrap processed

annually by a dealer in a given revenue range.

Table D.3 Annual throughput of ferrous metal scrap dealers (t/y)

Revenue

intervala

 ($) No. dealers Totals sales ($1,000) 

Throughput

per interval

Average

throughput

Cumulative

throughput CDF (%)

100,000 171 10,084 29,635 173 29,635 0.057

250,000 345 58,769 172,709 501 202,343 0.389

500,000 422 150,767 443,070 1,050 645,414 1.241

1,000,000 488 350,231 1,029,250 2,109 1,674,664 3.221

2,500,000 645 1,027,461 3,019,476 4,681 4,694,140 9.027

5,000,000 371 1,307,336 3,841,966 10,356 8,536,105 16.416

10,000,000 266 1,866,414 5,484,970 20,620 14,021,075 26.964

25,000,000 212 3,248,981 9,548,022 45,038 23,569,097 45.325

>25,000,000 151 9,674,408 28,430,903 188,284 52,000,000 100.000

Total 3,071 17,694,451 52,000,000

a

 Upper bound of interval

D.2.1.3 Melting and Refining

Similar to the analyses of the landfill disposal and scrap processing scenarios, the analysis of the

melting and refining of steel scrap incorporates the assumption that all scrap cleared during one

year of dismantlement of a given nuclear power plant would be melted at a single facility.6

 As

described in Section 3.2.3 of the main report, the scrap would be melted in one of three types of

furnaces. The mixing factors for each of these three furnace types are calculated in the same

manner as for the landfills and scrap dealers.

Table D.4 presents the data for BOFs at integrated steel mills, based on the individual mills listed

in Table 3.2 of the main report. Table D.5 presents corresponding data on EAFs, while data on

iron and steel foundries are presented in Table D.6. The discrete distributions of annual rates of

scrap consumption by these different types of facilities are constructed in the same way as the

distributions of landfill waste streams described in Section D.2.1.1.
Mixing of Cleared Materials Appendix D

NUREG-1640 D-6

Table D.4 Annual scrap consumption of BOF mills (tons/y)

Scrap intervala No. mills Average

scrap use

Total scrap

per interval

Cumulative

scrap use CDF (%) Heats/y

400,000 2 310,800 621,600 621,600 3.78 5,252

500,000 1 414,720 414,720 1,036,320 6.31 5,082

600,000 2 524,105 1,048,211 2,084,531 12.69 4,844

700,000 8 629,743 5,037,946 7,122,476 43.36 5,675

800,000 3 755,435 2,266,304 9,388,781 57.15 5,002

900,000 1 801,600 801,600 10,190,381 62.03 7,591

1,000,000 4 975,229 3,900,915 14,091,296 85.78 7,338

1,100,000 1 1,051,200 1,051,200 15,142,496 92.18 9,955

1,300,000 1 1,284,840 1,284,840 16,427,336 100.00 5,948

Total 23 16,427,336

a

 Upper bound of interval

Table D.5 Annual scrap consumption of EAF mills (tons/y)

Scrap intervala No. mills Average

scrap use

Total scrap

per interval

Cumulative

scrap use CDF (%) Heats/y

10,000 1 5,730 5,730 5,730 0.01 1,000

25,000 3 21,010 63,030 68,760 0.09 1,044

50,000 10 41,161 411,605 480,365 0.66 1,569

75,000 13 60,385 785,010 1,265,375 1.74 1,996

100,000 4 92,874 371,495 1,636,870 2.25 2,219

200,000 27 145,089 3,917,410 5,554,280 7.62 2,732

300,000 17 262,288 4,458,895 10,013,175 13.74 3,904

400,000 20 345,567 6,911,335 16,924,510 23.22 3,088

500,000 19 459,405 8,728,700 25,653,210 35.19 5,682

600,000 9 553,900 4,985,100 30,638,310 42.03 5,744

700,000 7 648,445 4,539,115 35,177,425 48.26 6,280

800,000 6 740,125 4,440,750 39,618,175 54.35 7,143

900,000 10 826,075 8,260,750 47,878,925 65.69 6,200

1,000,000 5 955,000 4,775,000 52,653,925 72.24 7,305

1,100,000 5 1,050,500 5,252,500 57,906,425 79.44 6,598

1,200,000 6 1,160,325 6,961,950 64,868,375 88.99 7,669

1,300,000 2 1,289,250 2,578,500 67,446,875 92.53 10,800

1,400,000 3 1,337,000 4,011,000 71,457,875 98.03 6,935

1,500,000 1 1,432,500 1,432,500 72,890,375 100.00 8,333

Total 168 72,890,375

Source: “EAF Roundup” 2001

a

 Upper bound of interval
Appendix D Mixing of Cleared Materials

7

 As was stated in Section 3.4.2.2 of the main report, each EAF heat consumes 5 – 20 different grades of scrap. 

D-7 NUREG-1640

(0 # i # n)

Table D.6 Annual scrap consumption of iron and steel foundries (tons/y)

Scrap intervala No. mills Average

scrap use

Total scrap

per interval

Cumulative

scrap use CDF (%)

100 122 48 5,877 5,877 0.018

250 123 164 20,174 26,051 0.078

500 161 363 58,519 84,570 0.252

1,000 219 698 152,868 237,438 0.707

2,500 277 1,631 451,734 689,172 2.052

5,000 183 3,693 675,791 1,364,962 4.064

10,000 167 7,413 1,237,937 2,602,900 7.750

25,000 192 15,539 2,983,510 5,586,410 16.633

50,000 121 34,510 4,175,725 9,762,135 29.067

75,000 48 60,187 2,888,972 12,651,107 37.668

100,000 33 86,282 2,847,311 15,498,417 46.146

200,000 18 129,869 2,337,643 17,836,060 53.107

300,000 21 233,219 4,897,596 22,733,656 67.689

400,000 6 354,073 2,124,438 24,858,094 74.015

500,000 7 450,970 3,156,792 28,014,886 83.414

600,000 1 563,048 563,048 28,577,934 85.090

1,300,000 4 1,251,873 5,007,491 33,585,425 100.000

Total 1,703 33,585,426

Source: Jim Maysilles, Metals Group, Emission Standards Division, U.S. Environmental Protection Agency, Research

Triangle Park, NC, private communication with Kathleen Behling, SC&A, Inc., September 25, 2001.

a

 Upper bound of interval

D.2.2 Maximum Single-Heat Mixing Factors

As is mentioned in Section 3.7.5 of the main report, the analysis of several of the product use

scenarios utilize the maximum single-heat mixing factor. To calculate this mixing factor, we

assume that the old scrap charged to the furnace is evenly divided among a number different

grades or types of scrap.7

 We further assume that each grade of scrap charged to the furnace is

from a separate lot and that the same annual-average mixing factor applies to each of these

grades of scrap (i.e., over the course of one year, each grade of scrap comprises the same fraction

of cleared scrap). The mixing factor for any given heat is , where n is the total number of lots

of old scrap and i is the number of lots that consist of cleared scrap. The following binomial

expression denotes the probability that, out of n randomly chosen lots charged to a given

furnace, i lots would consist of cleared scrap:

Pijn = probability that a given heat melted in furnace j contains i lots of cleared scrap
Mixing of Cleared Materials Appendix D

NUREG-1640 D-8

(k # n)

n = total number of lots (= number of grades of scrap) in each heat in furnace j

fjm = annual-average mixing factor for furnace j

The maximum single heat is defined as that heat, of all the heats produced in one year, that

contains the highest fraction of cleared scrap. The probability that no one heat produced in a

given year contains more than k lots of cleared scrap is:

P1jkn = probability that no heat melted in furnace j in one year contains more than k lots

of cleared scrap

N = number of heats produced in furnace j in one year

This probability distribution is used to select K, the maximum number of lots of cleared scrap in

any single heat melted in furnace j in one year. The maximum single-heat mixing factor is . 

The number of grades of scrap comprising each heat in a BOF or EAF is assigned a uniform

distribution: 5 # n # 20. The number of heats per year for each size BOF and EAF is listed in

Tables D.4 and D.5, respectively.

As stated in Section 3.4.2.2 of the main report, cupola furnaces producing cast iron can melt a

charge consisting of a single grade of scrap. Consequently, it is assumed that the old scrap in the

maximum single heat of cast iron is entirely comprised of cleared scrap.

D.3 Calculation of Mixing Factors for Copper Scrap

The sources of cleared copper scrap are discussed in Section 4.2.1 of the main report. The

mixing of copper scrap is modeled in the same manner as that of steel scrap, described above. 

Only those aspects of the analysis that are unique to copper are discussed in this section.

One major difference from the steel analysis is the amount of copper scrap that would be cleared

during the dismantlement of a commercial nuclear power plant, the assumed source of cleared

materials in the present analysis. As cited in Section 4.2.1, 62 t of copper scrap would be

potentially available for clearance. 

A second major difference is the number of copper refining facilities that could process the

cleared scrap. In the case of steel, there are approximately 1,900 melt shops (including

foundries) that are potential consumers of this material. Consequently, it is unlikely that any one

facility would receive scrap from more than one nuclear plant during any one year. In the case

of copper, four fire refineries together consume 28.6% of old, unalloyed scrap—the principal
Appendix D Mixing of Cleared Materials

8

 The fraction of scrap consumed by the fire refineries is derived in Section 4.2.2. As is explained in Section 4.6.8,

only exposure scenarios involving the fire refining of copper scrap are subject to detailed, probabilistic analyses. 

9

 Norb Geiss, David J. Joseph Company, private communication with Robert Anigstein and William C. Thurber,

SC&A, Inc., February 14, 2003.

10 Cleared scrap at a smaller scrap yard would experience less mixing, but the shorter work-hours would result in a

proportional reduction in the radiation exposure.

D-9 NUREG-1640

form of copper scrap which would be generated by the dismantlement of nuclear power plants.8

Consequently, in years during which more than one nuclear power plant would be undergoing

dismantlement, there is a small but potentially significant probability that a single refinery would

receive copper scrap from more than one plant.

D.3.1 Processing of Copper Scrap by Scrap Dealers

There are approximately 770 copper scrap dealers in the United States. This estimate is based on

the companies in the category “Copper Scrap Industry” listed by BrassMetals.com (2002). The

initial count of 979 firms is reduced by eliminating foreign firms, buyers and brokers, hauling

and trucking companies, auto salvage and crushers, marketing and investment firms, catalytic

converter recyclers, and disposal systems manufacturers.

No detailed information is available on the amounts of scrap processed by these dealers. 

However, according to an engineer at a major scrap metal dealer, the average nonferrous metal

scrap yard processes an estimated 500 tons (~450 t) of scrap per month; the largest such facility

processes 2,000 tons (~1,800 t) per month.9 There is essentially no lower limit, since some small

dealers might process as little as a barrel of copper scrap a month. However, the present analysis

assesses the radiation exposure of a full-time worker. Therefore, the smallest scrap yard

included in the analysis processes enough scrap to occupy at least one such worker.10 The manhours required to process a given quantity of scrap can be estimated by noting that a three-man

crew at a large scrap yard requires 2 days to prepare a 20-ton (~18 t) truckload.9 Assuming a

nominal 8-hour day, the processing requires 2.4 man-hours per ton. Therefore a small dealer,

with one full-time worker processing scrap, could process about 70 tons (~64 t) per month (2000

h/y ÷ [12 mo/y × 2.4 h/ton]  70 tons/mo).

The throughput of nonferrous metal scrap processors is represented by a beta function with a

range of 0 – 2,000 tons/month (~1,800 t/mo), and a mean of 500 tons (~450 t) per month. The

beta function, (x), is characterized by the following parameters: alpha = 0.5, beta = 1.5. The

function is evaluated at 193 points, 70 # xi # 1990 tons/mo, at intervals of 10

tons/mo. A normalized, mass-weighted probability distribution is determinated from the product

 and assigned to the points . This distribution is illustrated in

Figure D.1. An analysis of the distribution produced the following statistics:
Mixing of Cleared Materials Appendix D

11 Some of the variables used in the probabilistic calculation of mixing factors for copper scrap are represented by

symbols similar to those used in the calculation of maximum single heat mixing factors for steel mills, presented in

Section D.2.2. The actual variables used in these two analysis are distinct and independent.

NUREG-1640 D-10

Figure D.1 Distribution of nonferrous metal scrap dealers

median = 1,004 tons/mo

 10,930 t/y

mode = 1,000 tons/mo

 10,890 t/y

mean = 1,011 tons/mo

 11,000 t/y

D.3.2 Fire-Refining of Copper Scrap

In the background report on secondary copper production, prepared in support of Section 12.9 of

EPA’s “Compilation of Air Pollutant Emission Factors” (EPA 1995), Pacific Environmental

Services (n/d, Table 2.1-1), lists 10 secondary copper smelters and refineries. Of the 10 facilities

listed, only 4, listed in Table D.7, were fire refining copper scrap at the end of 2000. 

Table D.7 Annual capacities of U.S. secondary copper fire refineries

Operator Location Annual capacity (t/a) Fraction (%)

Cerro Copper Products Sauget, IL 125,000 46.1

Cyprus (Phelps Dodge) Warrenton, MO 32,000 11.8

Essex Fort Wayne, IN 44,000 16.2

Reading Metals Reading, PA 70,000 25.8

Total 271,000 100.0

Source: Pacific Environmental Services (n/d, Table 2.1-1)

The probability that copper scrap is processed at a given fire refinery is11

pj = probability that copper scrap is processed at fire refinery j

fr = fraction of Cu scrap consumed by all fire-refining furnaces

= 0.286

mj = annual capacity of fire refinery j (kt)
Appendix D Mixing of Cleared Materials

12 Construction recapture is defined as “[t]he maximum number of years that could be added to the license

expiration date to recover the period from the construction permit to the date when the operating license was granted. A

licensee is required to submit an application for such a change” (NRC 2000).

13 Decommissioning involves three different alternatives: DECON, SAFSTOR, or ENTOMB (NRC 2004).

• Under DECON (immediate dismantlement), soon after the nuclear facility closes, equipment, structures, and portions

of the facility containing radioactive contaminants are removed or decontaminated to a level that permits release of

the property and termination of the NRC license.

• Under SAFSTOR, often considered "delayed DECON," a nuclear facility is maintained and monitored in a condition

that allows the radioactivity to decay; afterwards, it is dismantled.

• Under ENTOMB, radioactive contaminants are encased in a structurally sound material such as concrete and

appropriately maintained and monitored until the radioactivity decays to a level permitting release of the property.

14 It is recognized that the shutdown schedule of nuclear reactors is fluid: some reactors may be granted 20-year

license renewals, while others may shut down prior to the expiration of their operating licenses.

D-11 NUREG-1640

Mr = combined capacity of all U.S. fire-refining facilities

= 271 kt

As stated on page D-9, there is a non-negligible probability that copper scrap from two or more

nuclear power plants undergoing dismantlement at the same time could be processed at the same

refinery. To assess this probability, we first need to determine how many commercial nuclear

power plants would be decommissioned in a given year. The year of projected shutdown of the

104 reactors currently licensed to operate is based on the expiration date of the current operating

license, including, in three cases, credit for construction recapture (NRC 2000, Table 12).12 In

addition to the operating reactors, there are 27 nuclear power reactors which were formerly

licensed to operate (NRC 2000, Appendix B). Of these, 6 are not light water reactors (LWRs). 

Only the 14 LWR reactors which are in SAFSTOR or scheduled for DECON are included in the

present analysis.13 Reactors where DECON is in progress or has been completed are excluded,

as are reactors which are in an ENTOMB status.14 It is assumed that dismantlement of each of

these 118 facilities will commence 10 years after reactor shutdown, except for facilities that have

elected the SAFSTOR alternative. For these latter reactors, dismantlement will be delayed by an

additional 50 years, and will therefore begin 60 years after shutdown. 

Table D.8 lists the number of reactors scheduled to begin dismantlement in each year in which

dismantlement activities occur. These data are used to construct a CDF of the number of

reactors undergoing dismantlement in any given year, as shown in Table D.9. The amount of

cleared copper scrap that would be processed at a free-standing fire refinery in any given year is

calculated as follows. We assume, for the purpose of the analysis, that the scrap from one

reactor would be processed at one of the four fire refineries listed in Table D.7. If a total of N

(N > 1) reactors undergo dismantlement in that year, the probability that scrap from i additional

reactors is processed at the same refinery during that year is
Mixing of Cleared Materials Appendix D

NUREG-1640 D-12

(i # n)

Pij (n) = probability that copper scrap from i out of n additional reactors is processed at

refinery j in a given year

n = N ! 1

N = total number of reactors undergoing dismantlement in a given year 

i = number of additional reactors feeding copper scrap to refinery j

The total number of reactors undergoing dismantlement in a given year (N) is selected by

random sampling of the distribution presented in Table D.9. The number of additional reactors

(i) feeding copper scrap to a given refinery is selected by random sampling from a distribution

with a range of 1 to N ! 1, with each value of i being assigned the probability Pij(n), presented

above.

Table D.8 Reactor dismantlement schedule 

Year No. reactors Year No. reactors

2006 2 2034 8

2007 1 2035 6

2016 1 2036 10

2019 3 2037 5

2020 3 2038 2

2021 2 2039 3

2022 6 2040 1

2023 10 2043 3

2024 11 2044 2

2025 2 2045 1

2026 6 2046 1

2027 3 2047 1

2028 3 2049 1

2030 3 2052 1

2031 4 2056 1

2032 6 2057 1

2033 4 2058 1

Total 118

The mixing factor for the cleared scrap is given by
Appendix D Mixing of Cleared Materials

D-13 NUREG-1640

fCu,j = annual-average mixing factor for copper scrap processed at fire refinery j

k = total number of reactors feeding copper scrap to fire refinery j

= i + 1

mCu = mass of copper scrap cleared during the dismantlement of one nuclear reactor

= 62 t

Table D.9 Annual number of reactors undergoing dismantlement 

No. reactors CDF (%)

1 32.35

2 47.06

3 67.65

4 73.53

5 76.47

6 88.24

8 91.18

10 97.06

11 100.00

D.4 Calculation of Mixing Factors for Aluminum Scrap

The sources of cleared aluminum scrap are discussed in Section 5.2.1 of the main report. The

mixing of aluminum scrap is modeled in the same manner as that of copper scrap, described

above. Only those aspects of the analysis that are unique to aluminum are discussed in this

section.

D.4.1 Processing of Aluminum Scrap by Scrap Dealers

The U.S. aluminum scrap industry comprises approximately 884 firms. This estimate is based

on a list of companies belonging to the aluminum scrap industry (“Metal World . . .” 2002). The

initial count of 1,199 companies was reduced by eliminating foreign-based companies,

aluminum buyers and brokers, hauling and trucking companies, aluminum can recyclers, auto

salvage and crushers, marketing and investment firms, x-ray and lithographic negative recyclers,

junk yards, handrail makers, catalytic converter recyclers, computer recyclers, and disposal

systems manufacturers. Companies that are included are generally described as scrap recyclers,

traders, dealers, and processors.

No detailed information is available on the amounts of scrap processed by these dealers. The

distribution of throughput of nonferrous metal scrap processors that is described in Section D.3.1

is therefore used to determine the mixing factor in the aluminum scrap yard scenario, which is

discussed in Section 5.4.2 of the main report.
Mixing of Cleared Materials Appendix D

NUREG-1640 D-14

D.4.2 Secondary Smelter Operations

D.4.2.1 Annual-Average Mixing Factors

As discussed in Section 5.2.3 of the main report, there are 75 producers of secondary aluminum

ingots in the United States. Not all of these operate secondary smelters. A search of published

literature yielded data on the annual production capacities of 18 secondary smelters, owned by

six different companies, as shown in Table D.10. While these facilities do not include all U.S.

secondary smelters, they are assumed to constitute a representative sample of such facilities. In

fact, the combined production capacities of these 18 facilities—1.48 Mt—is virtually the same as

the total amount of aluminum recovered from scrap by U.S. secondary smelters in 2000—

1.45 Mt, as listed in Table 5.2 of the main report.

Table D.10 Annual capacities of U.S. secondary aluminum smelters 

Company Smelter Capacity (t/y) Probability (%)

Wabash Alloys LLC Marietta, PA 27,200 1.84

Wabash Alloys LLC Checotah, OK 32,700 2.21

Wabash Alloys LLC Benton, AR 43,500 2.94

Wabash Alloys LLC Cleveland, OH 43,500 2.94

Wabash Alloys LLC Russellville, AL 43,500 2.94

Wabash Alloys LLC Ohio Valley 51,700 3.50

Wabash Alloys LLC Culp—Steele, ALa 54,400 3.68

Wabash Alloys LLC Tipton, IN 59,900 4.05

Audubon Metals b 65,800 4.45

Scepter, Inc. 70,800 4.79

Wabash Alloys LLC Dickson, TN 76,200 5.15

Wabash Alloys LLC Bellewood, VA 81,600 5.52

Wabash Alloys LLC Syracuse, NY 81,600 5.52

IMCO Recycling, Inc. Kentucky 99,800 6.75

OmniSource Corp. b 109,000 7.37

IMCO Recycling of Ohio, Inc. b 163,000 11.02

Wabash Alloys LLC Wabash, IN 185,000 12.51

Alcan Aluminum Corporation b 190,000 12.84

Total 1,479,200 100.00

a Culp Aluminum Alloys was acquired by Wabash Alloys LLC in September 2002

b Smelter location not specified

As is the case in the steel and copper recycling analyses, we assume that the probability that

cleared aluminum scrap would be recycled at a given smelter, listed in the last column of

Table D.10, is proportional to the annual capacity of that smelter. This probability is equal to the

annual capacity of the given smelter as a percentage of the total capacity of all 18 smelters.

These data are used to construct a discrete distribution of smelter capacities. The annual-average

mixing factor is the ratio of the mass of aluminum scrap cleared from a nuclear power reactor to

the annual capacity of the smelter.
Appendix D Mixing of Cleared Materials

15 This should not be confused with the annual capacities of secondary smelters listed in Table D.10

D-15 NUREG-1640

D.4.2.2 Maximum Single-Heat Mixing Factors

As is discussed in Section 5.4.3.2 of the main report, the aluminum scrap cleared from one

nuclear power plant would most likely be charged to the furnace in a single heat. Only limited

data on the sizes of reverberatory furnaces at secondary aluminum smelters were found in the

course of the present study; these data are listed in Table D.11. The total melting capacity of

furnaces of a given size, listed in the third column of Table D.11, is the product of the size of the

individual furnace and the number of furnaces of that size.15 The probability that cleared

aluminum scrap would be melted in furnace of a given size is proportional to the total melting

capacity of furnaces of that size. The probability is equal to total melting capacity of furnaces of

a given size as a percentage of the total melting capacity of all 17 furnaces listed. These data are

used to construct a discrete distribution of furnace sizes. The maximum single-heat mixing

factor is the ratio of the mass of cleared scrap to the size of the given furnace.

Table D.11 Sizes of reverberatory furnaces at U.S. secondary aluminum smelters 

Furnace size (tons) Number of furnaces Total (tons) Probability (%)

40 1 40 2.59

50 2 100 6.47

80 2 160 10.36

85 1 85 5.50

90 1 90 5.83

100 3 300 19.42

110 7 770 49.84

Total 17 1,545 100.00
Mixing of Cleared Materials Appendix D

NUREG-1640 D-16

References

BrassMetals.com. 2002. “BMX Copper Scrap Exchange.” Author. 

http://www.brassmetals.com/a/9501.html (September 5, 2002).

Bureau of the Census (U.S.) 2000. “1997 Economic Census: Wholesale Trade—Establishment

and Firm Size,” EC97W42S-SZ. http://www.census.gov/prod/ec97/97w42-sz.pdf (August 14,

2002).

“EAF Roundup.” 2001. Iron and Steelmaker, 28(5), 29–40.

Environmental Protection Agency (U.S.) (EPA). 1995. “Compilation of Air Pollutant Emission

Factors,” AP-42. 5th ed. Vol. 1, “Stationary Point and Area Sources.” Washington DC: Author.

http://www.epa.gov/ttn/chief/ap42/ch12/ (June 6, 2003).

Fenton, M. D. 1998. “Iron and Steel Scrap.” In Minerals Yearbook—1997. U.S. Geological

Survey. http://minerals.usgs.gov/minerals/pubs/commodity/iron_&_steel_scrap/360497.pdf

(April 21, 2004).

“Metal World: IME Aluminum Scrap Exchange.” http://www.metalworld.com/a/0133.html

(September 16, 2002).

Nuclear Regulatory Commission (U.S.) (NRC). 2000. “Information Digest, 2000 Edition,”

NUREG-1350. Vol. 12. Washington DC: Author.

Nuclear Regulatory Commission (U.S.), Office of Public Affairs (NRC). 2004.

“Decommissioning Nuclear Power Plants—Fact Sheet.” Washington DC: Author.

http://www.nrc.gov/reading-rm/doc-collections/fact-sheets/decommissioning.html (April 21,

2004).

Pacific Environmental Services, Inc. (n/d). “Background Report: AP-42, Section 12.9,

Secondary Copper Smelting, Refining, and Alloying.” Research Triangle Park, NC: U.S.

Environmental Protection Agency. http://www.epa.gov/ttnchie1/ap42/ch12/bgdocs/b12s09.pdf

(March 14, 2003).
APPENDIX E

INGROWTH OF RADIOACTIVE PROGENY

Appendix E Ingrowth of Radioactive Progeny

E-iii NUREG-1640

CONTENTS

Page

Appendix E Ingrowth of Radioactive Progeny . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-1

E.1 Short-lived Progeny in Secular Equilibrium with Parent . . . . . . . . . . . . . . . . . . . . . . . E-1

E.2 Calculating Progeny Ingrowth . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-2

E.2.1 Constant Source Term . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-2

E.2.2 Variable Source Term . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-2

E.2.2.1 Product-Use Scenarios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-2

E.2.2.2 Groundwater Scenarios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-5

E.2.3 Progeny That Were Omitted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-5

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-6

Tables

E.1 Progeny of nuclides selected for analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-3

E.2 Lifetime of Finished Products . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-5

Appendix E Ingrowth of Radioactive Progeny

1

 The terms “daughter product” and “daughter” refer to members of a decay chain that may include two or more

generations as well as competing decay modes (branches).

2

 The term “dose factor” is used to refer to dose conversion factors (DCFs) (Eckerman et al. 1988), effective dose

coefficients (ICRP 1994), and dose coefficients for external exposure.

E-1 NUREG-1640

E INGROWTH OF RADIOACTIVE PROGENY

This appendix describes the methodology used to model the ingrowth of radioactive progeny

over the periods of assessment used in the analysis. 

E.1 Short-lived Progeny in Secular Equilibrium with Parent

Because of the varying and largely unknown history of cleared materials, it is both reasonable

and conservative to assume that many short-lived radioactive progenies would be in secular

equilibrium with their parents at the time of release. Such daughter products1 are called the

implicit progeny of the parent. In the present analysis, these implicit progenies satisfy two

conditions: (1) the half-life of the daughter is less than 180 days, (2) the half-life of the parent is

at least 10 times the half-life of the daughter. For two-member decay chains satisfying these

conditions, 90% of full equilibrium is reached in ~ 3.3 half-lives of the daughter—about 458 d

(~15 mos) in the case of Po-210, the longest-lived nuclide in the implicit progenies in the present

analysis. The radiation from these nuclides is incorporated in the dose assessments described by

Equations 3.6 – 3.9 in Volume 1. In such cases, the dose factor2

 of the parent nuclide in these

equations is expressed as the sum of the dose factors of the parent and of the daughters

Fik = dose factor for nuclide i (parent) for exposure pathway k, adjusted for ingrowth of

short-lived progeny 

Gik = dose factor for nuclide i via exposure pathway k

n = number of nuclides comprising implicit progeny of parent

bij = branching ratio of nuclide j

Gjk = dose factor for nuclide j via exposure pathway k

In the radiological assessments, the doses calculated in each scenario are normalized to an initial

unit activity of the parent in the cleared material.

Table E.1 lists the implicit progenies included in the present analysis.
Ingrowth of Radioactive Progeny Appendix E

NUREG-1640 E-2

E.2 Calculating Progeny Ingrowth

Progenies that do not satisfy the criteria for implicit progenies, discussed above, are not assumed

to grown in prior to the release of the cleared material. Following the time of release, the

ingrowth of such nonimplict progenies is calculated by explicitly solving the Bateman equations

(Evans 1955) for the time of assessment of each scenario. The decay chains considered in the

present analysis are listed in Table E.1. The only exception to the rule presented in Section E.1

is the decay chain Ra-226 < Pb-210 < Bi-210 < Po-210. When Ra-226 is the primary nuclide,

the ingrowth of both Pb-210 and Po-210 are calculated separately and explicitly, while Bi-210 is

assumed to be in secular equilibrium with Pb-210. When Pb-210 is the primary radionuclide,

however, both Bi-210 and Po-210 are assumed to be in secular equilibrium with their parent.

E.2.1 Constant Source Term

In scenarios where the source is a steady stream of residually radioactive material, the time

following clearance is specified for each scenario—see the sections entitled “Scenario Timing”

in Chapters 3 – 6. Due to the probabilistic nature of the analysis, this time is usually described

by a probability distribution, so the decay and ingrowth of each nuclide are calculated separately

for each realization. 

E.2.2 Variable Source Term

In a number of scenarios, the source term varies with time during the assessment period. Such

variable source terms occur in the product-use and groundwater scenarios. 

E.2.2.1 Product-Use Scenarios

In the product-use scenarios, in the case of radionuclides without long-lived progenies, the

scenario begins at the time the product is first put into service, and lasts for one year. As shown

in Section 3.6.1.2, the dose is calculated by integrating the dose rate over this one-year period,

accounting for radioactive decay during this time. This is an appropriately conservative analysis,

since the doses will be highest during the first year.

For decay chains with two or more members, that is not necessarily the case. In some instances,

the dose rate would increase over some period of time before reaching a peak. The time of peak

dose depends on the half-lives of all of the nuclides in the chain (other than the implicit

progenies), and the dose factor of each nuclide for the pathway and scenario in question. The

year of peak dose is determined separately for each parent nuclide in each product-use scenario. 

It is calculated by adjusting the start time of each scenario by small increments, beginning with

the time the product is put in service, and continuing over the useful life of the given product,

which is listed in Table E.2. At each time step, the dose from all the nuclides in the given decay

chain is integrated over a one-year period—the one-year period corresponding to the highest

integrated dose is the year of peak dose for that decay chain in that scenario. Thus, the time of

assessment may be different for different nuclides in the same scenario.
Appendix E Ingrowth of Radioactive Progeny

E-3 NUREG-1640

Table E.1 Progeny of nuclides selected for analysis

Parent Implicit progeny of parenta Daughter Granddaughter

Nuclide t1⁄2 (y)b Nuclide BRc (%) t1⁄2 Nuclide BRc (%) t1⁄2 (y)b Nuclide BRc (%) t1⁄2 (y)

Sr-90 28.78 Y-90 100.00 64.1 h

Zr-93 1.53e+06 Nb-93m 97.50 16.13

Zr-95 64.02 d Nb-95m 1.13 86.6 h Nb-95 99.94 34.975 d

Mo-93 4.0e+03 Nb-93m 88 16.13

Ru-103 39.26 d Rh-103m 99.76 56.12 m

Ru-106 373.59 d Rh-106 100.00 29.8 s

Ag-108m 418 Ag-108 8.7 2.37 m

Ag-110m 249.79 d Ag-110 1.36 24.6 s

Cd-109 462.6 d Ag-109m 100.00 39.6 s

Sn-113 115.09 d In-113m 100.00 1.6582 h

Sb-125 2.7582 Te-125m 22.8 57.4 d

Te-127m 109 d Te-127 97.6 9.35 h

Cs-137 30.07 Ba-137m 94.4 2.552 m

Ce-144 0.781

Pr-144m 1.43 7.2 m

Pr-144 98.60 17.28 m

Pb-210 22.3

Bi-210 100.00 5.013 d

Po-210 100.00 138.376 d

Ra-226 1600

Rn-222 100.00 3.8235 d

Po-218 100.00 3.10 m

Pb-214 99.98 26.8 m

Bi-214 100.00 19.9 m

Po-214 99.97 164.3 :s Pb-210 100.00 22.3 Po-210 100.00 138.376 d

Ra-228 5.75 Ac-228 100.00 6.15 h Th-228 100.00 1.9131

Ac-227 21.772

Fr-223 1.38 21.8 m

Th-227 98.62 18.68 d

Ra-223 100.00 11.435 d

Rn-219 100.00 3.96 s

Po-215 100.00 1.781 ms

Pb-211 100.00 36.1 m

Bi-211 100.00 2.14 m

Tl-207 99.724 4.77 m

Po-211 0.276 0.516 s

Th-228 1.9131

Ra-224 100.00 3.66 d

Rn-220 100.00 55.6 s

Po-216 100.00 0.145 s

Pb-212 100.00 10.64 h

Bi-212 100.00 60.56 m

Tl-208 35.94 3.053 m

Po-212 64.06 0.299 :s
Ingrowth of Radioactive Progeny Appendix E

Table E.1 Progeny of nuclides selected for analysis

Parent Implicit progeny of parenta Daughter Granddaughter

Nuclide t1⁄2 (y)b Nuclide BRc (%) t1⁄2 Nuclide BRc (%) t1⁄2 (y)b Nuclide BRc (%) t1⁄2 (y)

NUREG-1640 E-4

Th-229 7340 

Ra-225 100.00 14.9 d

Ac-225 100.00 10.0 d

Fr-221 100.00 4.9 m

At-217 100.00 32.3 ms

Bi-213 99.988 45.59 m

Tl-209 2.09 2.20 m

Po-213 97.91 4.2 :s

Pb-209 100.00 3.253 h

Th-230 7.538e+04 Ra-226 100.00 1600 Pb-210 100.00 2.23e+01

Th-232 1.405e+10 Ra-228 100.00 5.75 Th-228 100.00 1.9131 

Pa-231 32760 Ac-227 100.00 21.77

U-232 68.9 Th-228 100.00 1.9131

U-233 1.592e+05 Th-229 100.00 7340

U-234 2.455e+05 Th-230 100.00 7.538e+04 Ra-226 100.00 1.60e+03

U-235 7.038e+08 Th-231 100.00 25.52 h Pa-231 100.00 32760 Ac-227 100.00 21.772

U-238 4.47e+09

Th-234 100.00 24.1 d

Pa-234m 100.00 1.17 m

Pa-234 0.16 6.7 h

Np-237 2.14e+06 Pa-233 100.00 26.967 d U-233 100.00 1.59e+05

Pu-236 2.858 U-232 100.00 68.9 Th-228 100.00 1.9131

Pu-241 14.35 Am-241 99.998 432.2

Pu-244 8.08e+07

U-240 100.00 14.1 h

Np-240m 100.00 7.22 m Pu-240 100.00 6563

Np-240 0.11 61.9 m

Am-242m 141

Am-242 99.541 16.02 h

Cm-242 82.3 162.8 d

Pu-238 82.7 87.7

Np-238 0.46 2.117 d

Am-243 7370 Np-239 100.00 2.3565 d Pu-239 100.00 24110

Cm-242 162.8 d Pu-238 100.00 87.7

Cm-243 29.1 Pu-239 100.00 24110

Cm-244 18.1 Pu-240 100.00 6563

Cm-245 8500 Pu-241 100.00 14.35 Am-241 99.998 432.2

Cm-246 4730 Pu-242 99.97 3.733e+05

Cm-247 1.56e+07 Pu-243 100.00 4.956 h Am-243 100.00 7370 Pu-239 100.00 24110

Bk-249 320 d Cf-249 99.986 351

Cf-248 333.5 d Cm-244 99.997 18.1 Pu-240 100.00 6563

Cf-249d 351 Cm-245 100.00 8500 Pu-241 100.00 14.35

Cf-250 13.08 Cm-246 99.923 4730

Es-254 275.7 d Bk-250 100.00 3.217 h Cf-250 100.00 13.08 Cm-246 99.923 4730

a

 Implicit progeny: t1⁄2 (daughter) < 180 d and t1⁄2 (parent) > 10 t1⁄2 (daughter)

b

 Units are years unless otherwise specified

c

 BR = branching ratio

d

 Four-member decay chain: last member = Am-241, BR = 99.998%, t1⁄2 = 432.2 y
Appendix E Ingrowth of Radioactive Progeny

E-5 NUREG-1640

Table E.2 Lifetime of Finished Products

Scenario title Product Life (y)

Steel

Sailor with watch station in operations area Ship 35 Sailor with watch station on deck

Sailor berthing near steel hull plate Hull plate 35

Driving on road built with steel slag Road 30

Living in basement built with cement made from slag Basement 100

Exposure to large metal mass Large steel mass 100

Exposure to small metal mass Small steel mass 100

Small steel object on body Steel object on body 100

Living in home built with steel studs Home with steel studs 100

Driver of automobile with cast iron engine block Cast iron engine block–automobile 5

Driver of truck with cast iron diesel engine block Cast iron diesel engine block–truck 10

Copper

Exposure to small mass of fire-refined copper Small copper mass 20

Small fire-refined copper object on body Copper object on body 20

Drinking tapwater from copper pipes Copper pipes 35

Aluminum

Exposure to large metal mass Large aluminum mass 30

Exposure to small metal mass Small aluminum mass 30

Driver of taxi with aluminum engine block Aluminum engine block–taxi 3

Use of aluminum cooking ware Aluminum cookware 20

Concrete

Driving on road built with recycled concrete Road 30

E.2.2.2 Groundwater Scenarios

The year of peak dose in the groundwater scenarios is a complicated function of progeny

ingrowth, leach rates, and the movement of the radionuclides through the hydrogeological

environment. This peak year is explicitly calculated for each radionuclide in each realization

(see discussion on pages 3-81 and 3-90 in Volume 1).

E.2.3 Progeny That Were Omitted

Some radioactive progenies were omitted from the ingrowth analyses. These included very

long-lived nuclides whose ingrowth during the maximum period of assessment—1,000 years for

the drinking water scenarios—would make no significant contribution to the calculated doses,

and the products of decay modes with very small branching ratios. An example of the former
Ingrowth of Radioactive Progeny Appendix E

NUREG-1640 E-6

case is the ingrowth of U-234 and its progeny from the decay of U-238. After 1,000 years, 1 Bq

of U-238 will yield about 2.8 mBq of U-234, 13 :Bq of Th-230, and less than 1.7 :Bq each of

Ra-226 and the members of its decay chain. The effective dose from drinking water containing

these nuclides would be 0.0474 :Sv per Bq of U-238 ingested if only the contribution of U-238

and its implicit progeny were considered, and 1.4 × 10-4 :Sv more if the dose contribution from

the entire decay chain were included, a difference of 0.3%.

As a rule of thumb, progenies estimated to contribute about 1% or less to the total dose from any

exposure scenario were omitted.

References

Eckerman, K. F., A. B. Wolbarst, and A. C. B. Richardson. 1988. “Limiting Values of

Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation,

Submersion, and Ingestion,” Federal Guidance Report No. 11, EPA-520/1-88-020. Washington,

DC: U.S. Environmental Protection Agency, Office of Radiation Programs.

Evans, R. D. 1955. The Atomic Nucleus. New York: McGraw-Hill Book Company, Inc.

International Commission on Radiological Protection (ICRP). 1994. “Dose Coefficients for

Intakes of Radionuclides by Workers,” ICRP Publication 68. Annals of the ICRP, 24(4). 

Tarrytown, NY: Elsevier Science, Inc.