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Defense Threat Reduction Agency

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TECHNICAL REPORT

DTRA-TR- 07-11

FIIDOS, A Computer Code for the 

Computation of Fallout Inhalation 

and Ingestion Dose to Organs

Computer User’s Guide (Revision 4)

HDTRA1-07-C-0015

Dudley A. Raine III, et al.

Prepared by:

SAIC

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May 2007

Approved for public release; distribution is unlimited.

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4. TITLE AND SUBTITLE

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FIIDOS – A Computer Code for the Computation of Fallout 

Inhalation and Ingestion Dose to Organs 

Computer User’s Guide (Revision 4) 

5c. PROGRAM ELEMENT NUMBER

 139D 

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 CS 

6. AUTHOR(S)

5e. TASK NUMBER

 AH 

Dudley A. Raine III, Stephen D. Egbert, John H. Stiver, and David 

R. Case 

5f. WORK UNIT NUMBER

 DH21501 

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Approved for public release; distribution is unlimited. 

13. SUPPLEMENTARY NOTES

This work was sponsored by the Defense Threat Reduction Agency under RDT&E RMSS Code B 139D D R400 

CS AH 21501. 

14. ABSTRACT

This report discusses the technical aspects of the computer code FIIDOS (Fallout Inhalation and Ingestion Dose to 

Organs, Version 4), describes user inputs and operations, and includes sample problems. This report updates the 

original FIIDOS Computer User’s Guide published in 1985. 

15. SUBJECT TERMS

Nuclear Test Personnel Review, Veterans, Atmospheric Nuclear Weapons Test, Fallout, Inhalation Dose, Ingestion 

Dose, Internal Dose 

16. SECURITY CLASSIFICATION OF: 19a. NAME OF RESPONSIBLE PERSON 

Dr. Paul K. Blake

17. LIMITATION 

OF ABSTRACT 

18. NUMBER 

OF PAGES 

UU 169 a. REPORT b. 

A STRACT 

c. THIS PAGE 19b. TELEPONE NUMBER (Include area code) 

U B U 703 767-3384

U
iii

TABLE OF CONTENTS 

SECTION PAGE 

FIGURES.............................................................................................................................v 

TABLES ............................................................................................................................ vi 

1 OVERVIEW ..............................................................................................................................1

1.1 INTRODUCTION ......................................................................................................1 

1.2 HISTORY OF THE CODE ........................................................................................2 

1.2.1 FIIDOS1.......................................................................................................2 

1.2.2 FIIDOS2.......................................................................................................2 

1.2.3 FIIDOS3.......................................................................................................4 

1.2.4 FIIDOS4.......................................................................................................5 

1.3 SUMMARY................................................................................................................6 

2 TECHNICAL APPROACH.....................................................................................................14 

2.1 INTRODUCTION ....................................................................................................14 

2.2 EQUATIONS AND PARAMETERS.......................................................................16 

2.2.1 Duration of Exposure...................................................................................20 

2.2.2 Breathing Rate ...........................................................................................20 

2.2.3 Airborne Activity-Surface Activity Ratio..................................................21 

2.2.3.1 Deposition from Aerosol Cloud..................................................21 

2.2.3.2 Resuspension of Deposited Material ..........................................22 

2.2.4 Dose Coefficients.......................................................................................26 

2.2.5 Relative Radionuclide Inventory ...............................................................31 

2.2.6 Radiological Contamination Scaling Factor..............................................36 

2.2.6.1 Radiological Measurement Quantities........................................38 

2.2.6.2 Total Activity of Relative Radionuclide Inventory ....................38 

2.2.6.3 Gamma-ray Emission Spectrum .................................................39 

2.2.6.4 Gamma-ray Exposure Factor......................................................41 

2.3 LIMITATIONS OF TECHNICAL APPROACH.....................................................48 

3 COMPUTER PROGRAM.......................................................................................................52 

3.1 INTRODUCTION ....................................................................................................52 

3.2 EQUATIONS AND OPERATIONS ........................................................................52 

3.3 MAIN PROGRAM AND SUBROUTINES.............................................................53 

3.4 DATA LIBRARY.....................................................................................................58 

3.5 INPUT DESCRIPTION............................................................................................59 

3.6 OUTPUT DESCRIPTION........................................................................................59 

4 REFERENCES ........................................................................................................................84 

APPENDIX................................................................................................................................. A-1 
iv

A DOSE FACTORS ................................................................................................................ A-1

B CODE LISTING - FIIDOS, VERSION 4.3..........................................................................B-1 

C SAMPLE PROBLEMS.........................................................................................................C-1 
v

Figures 

Figure PAGE 

1 Key features of computer code FIIDOS .............................................................. 9 

2 Schematic for calculation of organ dose.............................................................. 10 

3 Schematic for calculation of intensity activity factors......................................... 11 

4 Comparison of time-dependent resuspension models.......................................... 27 

5 The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ dose 

from inhalation of 1-micrometer AMAD particles for selected organs .............. 29 

6 The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ dose 

from inhalation of 20-micrometer AMAD particles for selected organs ............ 30 

7 The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ dose 

from ingestion for selected organs....................................................................... 30 

8 Fission fraction results from subroutine FISFRC................................................ 33 

9 Equivalent ground roughness for soil source....................................................... 45 

10 Man phantom model ............................................................................................ 46 

11 Angular contribution of fallout intensity ............................................................. 47 

12 Dose equations for computer calculations........................................................... 54 

13 Concept of FIIDOS.............................................................................................. 55 

14 Relationship of principal subroutines.................................................................. 56 

15 Organization and hierarchy of FIIDOS ............................................................... 57 

16 FIIDOS output - all options................................................................................. 73 
Tables 

Table PAGE 

1 User-supplied input for FIIDOS .......................................................................... 12

2 Resuspension factors reported in reactor safety study......................................... 24 

3 Fission product radionuclides and standard decay times used in FIIDOS .......... 34 

4 Activation product radionuclides......................................................................... 35 

5 Actinide product radionuclides............................................................................ 35 

6 Gaseous fission product radionuclides ................................................................ 35 

7 Gamma-ray energy group structures.................................................................... 42 

8 Gamma-ray response functions............................................................................ 43 

9 Elemental composition of Nevada Test Site soil................................................. 45 

10 Gamma-ray exposure factor for surface contamination....................................... 49 

11 Gamma-ray exposure factor for airborne contamination..................................... 50 

12 FIIDOS data library ............................................................................................. 60 

13 The 40 basic time intervals that ORIGEN2-SAIC used when performing the 

decay calculations................................................................................................ 61 

14 Eighteen energy groups for gamma-ray spectra with their midpoint energies 

noted .................................................................................................................... 62 

15 Twenty one energy groups for gamma-ray exposure factors spectra with their 

midpoint energies noted....................................................................................... 62 

16 Input data required by FIIDOS ............................................................................ 63 

vi
SECTION 1 

 OVERVIEW 

1.1 INTRODUCTION 

This report discusses the technical aspects of the computer code FIIDOS (Fallout 

Inhalation and Ingestion Dose to Organs, Version 4), describes user inputs and 

operations, and includes sample problems. This report updates the original FIIDOS 

Computer User’s Guide published in 1985 (DNA, 1985). The Nuclear Test Personnel 

Review (NTPR) Program uses FIIDOS to determine the dose to internal organs from the 

inhalation or ingestion of contaminants created by a nuclear detonation under various 

conditions common to participants in atmospheric nuclear testing and the occupation of 

Hiroshima and Nagasaki, Japan (NTPR, 2006). To do this, it calculates an internal dose 

in an organ from the intake of contaminants produced by a nuclear detonation, which is 

typically determined by relating the external gamma-ray intensity rate above a fallout 

field to the fallout contamination level on the ground surface. The intake of contaminants 

may also be determined from other measurements, including air-sampling data or 

radiation intensities within a debris cloud (while on the ground or in the air). It 

determines the dose from the mixture of activation products, actinides, and fission 

products in fallout. Doses from low-linear energy transfer (LET) radiation (beta particles 

and gamma rays) are reported separately from doses from high-LET (alpha particle) 

radiation. 

The NTPR Program has prepared internal dose determinations since the early 1980s 

using methods incorporated into the FIIDOS code. Approaches to internal dose 

determination included estimates of airborne radioactivity concentrations based on 

ambient radiation dose (Lee, 1983 and Barrett, 1986). Other approaches included 

estimates based on analyses of fission products and plutonium in urine (SAIC, 1983). A 

review of those methods (NRC, 1985) concluded that personnel exposed to heavy fallout 

received internal doses that were much smaller than their external doses, with the 

possible exception of doses to the thyroid. The review also concluded that the methods 

for estimating internal doses were not as well developed or as scientifically defensible as 

the methods used to estimate external doses. These conclusions were based on a lack of 

data about the material inhaled or ingested by nuclear weapon test participants or 

occupation forces at Hiroshima or Nagasaki and on the reliability of certain assumptions 

used in the estimates. The review expressed concerns about fractionation of airborne 

radionuclides and deposited fallout, particle size distributions, and particle solubilities. 

The concerns about internal dosimetry methods discussed in NRC’s review (NRC, 1985) 

pertain to assumptions of various parameters required to estimate the dose to tissues and 

organs in the absence of measurements of radioactivity concentrations. Suggestions for 

the use of urine bioassay to estimate concentrations of radionuclides in the body 

combined with appropriate models to derive estimates of material inhaled or ingested 

1
were apparently rejected as not feasible. The NTPR Program worked to re-evaluate 

assumptions about the critical parameters used in calculating internal doses – 

resuspension factor, breathing rate, fractionation, and scenario elements – to conclude 

that reasonable margins of high-siding were applied. 

In the late 1990s, the NTPR Program studied whether bioassay testing using the 

measurement of plutonium in urine could be used to assess the reliability of the methods 

for estimating inhalation doses. The effort resolved numerous technical, analytical, and 

methodological issues, and collected and analyzed urine samples from about 100 

veterans. Results of the assessments provided the source data for several papers on the 

analytical issues involved (e.g., Klemm, 2003). However, the results did not prove useful 

in providing an assessment of the reliability of the methods for estimating internal doses. 

A more recent National Research Council review (NRC, 2003) evaluated methods for 

estimating internal dose and concluded that the methods had important shortcomings 

centered around three issues. First, the committee concluded that the reliability of 

methods for estimating concentrations of radionuclides based on measurements of 

external photon exposure had not been demonstrated. Second, the committee concluded 

that the lack of consideration of resuspension of previously deposited fallout by the blast 

wave and the neglect of fractionation in fallout could result in underestimates of 

inhalation dose. Third, the substantial uncertainty in dose coefficients for inhalation of 

radionuclides had not been taken into account. The committee summarized its evaluation 

of the methods for estimating inhalation dose by concluding that they do not consistently 

provide credible upper bounds. The committee also considered estimates of doses from 

ingestion of radionuclides, offered several examples of plausible scenarios, and 

concluded that ingestion was rarely considered in estimating internal dose. 

1.2 HISTORY OF THE CODE 

1.2.1 FIIDOS1 

The original version of FIIDOS, completed in 1985, was written in FORTRAN-IV for 

operation on a DEC PDP-11 mini-computer with problem input read from a keyboard 

and output directed to an off-line printer. The code required 32 kilobytes (Kb) of core 

memory and 100 Kb of external disk memory storage. A typical FIIDOS problem used 

10 minutes of running time. Since 1985, with the substantial increases in the available 

computing power, FIIDOS has undergone a gradual evolution to a code that, though it 

still functions in much the same way, has substantially greater capabilities. 

1.2.2 FIIDOS2 

a. Overview 

The first revision to FIIDOS in 1995, called FIIDOS2 included the following three 

significant changes: 

1) ORIGEN2 - Oak Ridge Isotope Generation and Depletion Code, 

Version 2.1 (Croff, 1980), was integrated into the FIIDOS code and 

2
its input data modified. It was run using initial fission product 

inventories directly for both fast (1-MeV) and 14-MeV fission from 

U-235, U-238 and Pu-239 datasets recommended to the Defense 

Nuclear Agency (DNA) by Tal England of Los Alamos National 

Laboratory (LANL) (England, 1993a and England, 1993b). England 

was the reviewer for these inventories in the previously released 

ENDF/B-VI fission product dataset (Rose, 1991). He made the 

recommendation to use the updated inventories because he obtained 

better agreement with fission product gamma- and beta-emission 

measurements from very early to late times. This dataset was used 

extensively for other projects such as the Japanese A-Bomb 

dosimetry study. However, because it was a work in progress at 

LANL, it was not forwarded to the Brookhaven National Laboratory 

(BNL) National Nuclear Data Center for public access. 

2) An option to include dose conversion factors from Federal Guidance 

Report 11 (FGR-11) (Eckerman, 1988) was added to supplement the 

tables of dose conversion factors used in the original version of 

FIIDOS, which are based on ORNL TM-190 (Killough, 1981) and 

ICRP-30 (ICRP, 1979). 

3) A plutonium bioassay prediction capability was included. 

4) An integrated exposure option was added to the original version’s 

three discrete exposure options to assess internal doses in situations 

where the period of intake is long enough that significant changes 

occur in the radionuclide inventory; e.g., for an extended period on a 

residence island after an operation. 

The code was rewritten in Fortran 77 and compiled for various computing platforms, 

including UNIX, Macintosh, and MS-DOS compatible systems. Runtimes on the various 

platforms ranged from 20 seconds up to 9 minutes, depending on the speed of the system 

and the compiler options specified. 

b. Data Changes 

The original FIIDOS used data tables containing time-dependent radionuclide and 

gamma-ray spectral information for various fission radionuclides produced in a fast 

reactor that were generated in the original version of ORIGEN. FIIDOS interpolated 

between the standard times of the data tables to calculate the inventory and spectra at the 

times of interest. FIIDOS2 incorporated ORIGEN2, the latest available version of that 

code, as a callable subroutine, with modifications to support the NTPR Program needs. 

Thus, many of the original data tables were no longer necessary because the required 

information was passed directly from ORIGEN2 into FIIDOS via common block 

variables, which eliminated the interpolation steps. Additional modifications to 

ORIGEN2 included: 1) expanding the gamma-ray spectral data for many more isotopes 

3
to provide accurate spectra at early times after detonation; 2) using the initial fission 

product inventories available in the fission product dataset obtained from LANL 

(England, 1993a and England, 1993b) for fission from U-235, U-238, and Pu-239; and 3) 

correcting for a few inconsistencies in the decay constants and gamma-ray spectra, which 

were found by comparing late-time decay inventory and spectra output from ORIGEN2-

SAIC with that calculated by a LANL in-house code called CINDER10 (England, 1993a 

and England, 1993b). This modified version of ORIGEN2 was called ORIGEN2-SAIC 

(Roberts, 1996). For most scenarios using ORIGEN2-SAIC, the resulting organ doses 

produced by FIIDOS2 showed only minor differences from those generated by the 

original version of FIIDOS (generally less than one to two percent at exposures more 

than one hour after detonation). 

c. Dose Conversion Factors Added 

The new dose conversion factors added into FIIDOS2 were taken from FGR-11, which 

utilized the ICRP-30 methods and models and expanded the inventory of dose conversion 

factors to 412 radionuclides. Additional large particle internal dose conversion factors 

for a particle size distribution of 10-micrometers (μm) activity median aerodynamic 

diameter (AMAD) were created using the computer code, DFINT (Eckerman, 1993). 

Inhalation dose conversion factors were selected for each nuclide according to the 

respiratory clearance class associated with the oxide form of each element. The addition 

of this data set had little, if any, impact on the internal organ doses reported by the NTPR 

Program because the organ doses resulting from ORNL TM-190 dose conversion factors 

tended to be greater than those from FGR-11. As directed by the Government for the 

NTPR program, the data set most favorable to the veterans continued to be the default 

choice. 

d. Plutonium Bioassay Added 

A plutonium bioassay capability was added using the available radionuclide inventory 

data in FIIDOS to determine the total intake of Pu-239 based on the inhaled or ingested 

total number of curies (Ci) as calculated during the internal dose calculations. The Pu239 excretion rate is represented by a five-term exponential function (Jones, 1985), 

which is used to predict the Pu-239 activity excreted in urine during any 24-hr period at 

specific times after uptake. While this modification had no effect on the resulting organ 

doses calculated by FIIDOS, it provided a tool to assess radiological uptake if a 

participant had a bioassay result greater than the population average during the period of 

the NTPR-sponsored Pu-239 bioassay program (1998-1999). 

1.2.3 FIIDOS3 

Revisions to FIIDOS in 1999, called FIIDOS3 changed the program flow so that multiple 

discrete or integrated exposures with multiple measurements (all from the same 

detonation) could be handled in a single run. Previously, each measurement could have 

multiple exposure times associated with it, but only one measurement time could be used 

in a given run. This change enabled the user to include 50 measurement/exposure pairs 

4
for discrete exposures (or any combination of measurements and exposures totaling 100), 

or 33 measurement/exposure pairs for integrated exposures. In addition, the plutonium 

bioassay capability was expanded to be more flexible by allowing the user to specify the 

number of excretion times to be evaluated and modifying the time of excretion to be 

specified relative to the detonation (instead of intake), which facilitates combining 

contributions from multiple or integrated exposures. Because of the substantial increase 

in computer power available at the time, even longer runs with a full input deck of 100 

(measurement plus exposure) times usually took less than one minute on a personal 

computer. No other technical changes were made and the code output was verified to be 

consistent with the output from FIIDOS2. 

1.2.4 FIIDOS4 

Three modifications have been made to FIIDOS since 1999. In 2001, options to include 

dose conversion factors for inhalation and ingestion from FGR-13 (EPA, 1999) were 

added to the code. The dose conversion factors presented in FGR-13 use the latest 

methods and models from the ICRP, including the ICRP-66 human respiratory tract 

model (HRTM) (ICRP, 1994a). Notably, these dose conversion factors provide the 

equivalent dose, which is the absorbed dose averaged over a tissue or organ and weighted 

by a radiation weighting factor (wR). Only one set of inhalation dose conversion factors 

for a particle size distribution of one-micrometer AMAD was incorporated into FIIDOS 

along with a new set of ingestion dose conversion factors. Because these dose 

conversion factors did not result in appreciable increases or decreases in the total reported 

organ doses for most participants relative to those calculated using the existing ICRP-30 

or FGR-11 tables, the FGR-13 tables were only used in situations requiring a dose to an 

internal organ that was not contained in the other dose conversion factor tables. 

In 2006, a second change allow the reporting of alpha-particle doses separately from beta 

particle and gamma-ray doses to accommodate the Department of Veterans Affairs’ use 

of the Interactive RadioEpidemiological Program for calculating the probability of 

causation for cancers. This modification assumes that the alpha-particle dose to an organ 

equals the total organ dose for the alpha-particle emitting radionuclides in the FIIDOS 

inventory. 

Also in 2006, a third change involved revision of the code in response to DTRA guidance 

to implement only the most current dose coefficients for determining internal dose. 

Namely, these were the dose coefficients based on ICRP-72 (ICRP, 1996). As part of 

this revision, options to use dose conversion factors previously included (ORNL TM190, ICRP-30, FGR-11, and FGR-13) were removed from the code. However, records of 

their use in generating dose factor tables were retained for legacy purposes, and the 

revised code included the flexibility to accommodate dose coefficient data sets 

(including, if necessary, the old data sets) with up to 40 organs as input. The ICRP-72 

dose conversion factors are based on the conceptual framework of ICRP-60 (ICRP, 1991) 

as implemented in the latest dosimetric and biokinetic models (ICRP, 1991; 1994a; 

1994b; 1996). The ICRP-72 inhalation dose coefficients, as input to FIIDOS, were 

5
selected to address concerns about particle size distribution. This set uses the dose 

coefficient for the particle size distribution that produces the highest dose to the organ of 

interest from among 1-, 3-, 5-, and 10-micrometer AMAD particle size distributions for 

the absorption type applicable to the oxide form of each constituent radionuclide. This 

set of “maximum dose” inhalation dose conversion factors supplants all previous sets for 

internal dose assessments. 

The changes noted above outline the major differences between the original version of 

FIIDOS and the current version. Since FIIDOS2, no changes have been made that affect 

the methods used to calculate the doses; ensuing changes involve the dose conversion 

factors, program flow, options, and output presentation. 

1.3 SUMMARY 

The purpose of FIIDOS is to calculate the 50-year committed equivalent dose to various 

body organs and tissues resulting from the inhalation or the ingestion of fallout from 

nuclear weapons. 

Figure 1 portrays the key features of FIIDOS. Four characteristics of FIIDOS enhance its 

applicability to radiation dose calculations associated with nuclear detonations: 

a) the production and radioactive decay of the radionuclides present in 

nuclear weapon fallout (including fission products, activation 

products, and actinide elements) is considered, permitting 

modifications to this radionuclide inventory to reflect detonationspecific analyses of activity fractions in the various isotopes of the 

nuclear debris; 

b) the dose calculation is based on a specific radiological measurement of 

the nuclear debris or fallout (such as a measurement of gross activity 

concentration or gamma-ray radiation intensity); 

c) calculated doses from both high linear energy transfer (LET) (alphaparticle) and low LET (beta-particle and gamma-ray) radiations 

support the calculation of probability of causation; and, 

d) the plutonium concentration in urine for times since detonation 

(corrected for time of uptake) is calculated. 

Figure 2 illustrates, in a simplified manner, the logic used in FIIDOS to calculate 

committed organ doses. The computation can begin with any one of the nine types of 

radiological measurements listed in Figure 1 and indicated in Figure 2. The most 

common calculation scheme, based on a measurement of the radiation intensity above a 

contaminated surface, is described in the following sections. 

The computation begins with the user-supplied radiation intensity, such as survey data in 

Roentgen per hour (R hr-1). FIIDOS calls the ORIGEN2-SAIC code to calculate a debris 

inventory and radiation intensity spectrum. After modifying the inventory and the 

gamma spectrum to reflect any post-detonation changes (e.g., the removal of the gases 

6
krypton and xenon or fractionation effects), FIIDOS calculates the relationship between 

the radiation intensity and the surface activity concentration in Curies per square meter 

(Ci m-2). A user-supplied resuspension factor, which relates airborne contamination to 

surface contamination, converts the surface activity concentration to an airborne activity 

concentration (Ci m-3). Using this airborne activity concentration and user-supplied 

information on the exposure duration (hr) and the breathing rate (m3

 hr-1); FIIDOS 

determines the discreet activity for each radionuclide (Ci) present in the inhaled 

radioactive material. Based on the inventory of this radionuclide activity intake and a set 

of radionuclide-specific, inhalation dose conversion factors (in dose equivalent per 

material activity, i.e., rem μCi-1) contained in FIIDOS, internal committed equivalent 

doses are calculated. Given the FIIDOS-calculated activity intake of Pu-239, a five-term 

exponential excretion function (Jones, 1985) is applied to calculate the Pu-239 activity 

concentration that is expected in 24-hour urine samples at specified times postdetonation. 

As mentioned above and indicated in Figure 2, FIIDOS calculates factors that are used to 

convert the radiation intensity into an airborne or surface activity concentration and 

factors that are used to determine the activity of specific radionuclides in the ingested or 

inhaled radioactive material. Figure 3 illustrates the approach used in FIIDOS to 

calculate these factors. 

As seen in Figure 3, the calculation of the factor used to convert radiation intensity to an 

airborne or surface activity concentration begins with the gamma-ray spectral data and 

the radionuclide inventory data for a reference amount (1014 fissions) of radioactive 

material as calculated by ORIGEN2-SAIC. In response to user-supplied information on 

the weapon, the fallout, and the radiological measurement, the spectral and inventory data 

are modified to reflect the gamma-ray emission rate (γ hr-1) and the activity (Ci) of the 

reference amount of fallout material or nuclear debris at the time of the radiological 

measurement. Gamma-ray exposure factors are used to determine the radiation intensity 

(R hr-1) of the material present as airborne or surface contamination. The ratio of the 

radiation intensity to activity gives the factor used by FIIDOS to convert the measured 

radiation intensity to a calculated airborne activity concentration (R hr-1 per Ci m-3) or 

surface activity concentration (R hr-1 per Ci m-2). The activity derived from these factors 

is adjusted within FIIDOS for the actual time of exposure (depicted in Figure 2). The 

material given above provides an overview of the calculation scheme used in FIIDOS. A 

complete description of the technical approach used in FIIDOS is provided in Section 2. 

FIIDOS can handle two types of basic dose calculation problems: single (acute) 

exposures and long duration (chronic) exposures. A single exposure problem involves a 

single radiological measurement and a single radiation exposure. This is a basic dose 

calculation handled by FIIDOS. Multiple exposures tied to single or multiple 

measurements may be entered with an equal or greater number of exposure times. A 

maximum of 100 entries, comprised of any combination of measurement and exposure 

times, may be entered for a single program execution. A long duration exposure problem 

7
involves an exposure long enough that the debris inventory significantly changes, and 

thus the dose calculation requires time integration. As with single exposures, a long 

duration problem may include multiple measurements and an equal or greater number of 

exposures. A maximum of 33 measurement or exposure times is permitted for this type 

of problem. 

Generally, the types of user-supplied input data required by FIIDOS are summarized in 

Table 1. The user input data are discussed in detail in subsequent sections of this report; 

Section 2 provides a technical discussion of the input data and Section 3 addresses the 

input data format requirements for the computer program. 

8
RADIONUCLIDES 

• ORIGEN2-SAIC - calculates decay inventory and spectra from 1600 

isotopes of which the following subsets in FIIDOS. 

o Fission Products - 148 radionuclides from fast and 14-MeV 

neutron fission of U-235, U-238, and Pu-239. 

o Activation Products - 17 radionuclides. 

o Actinide Elements - 18 radionuclides. 

RADIOLOGICAL MEASUREMENTS 

• Gross Ingestion Activity Intake (Ci). 

• Gross Inhalation Activity Intake (Ci). 

• Specific Ingestion Activity of Single Isotope as Part of Decayed 

Inventory (Ci). 

• Specific Inhalation Activity of Single Isotope as Part of Decayed 

Inventory (Ci). 

• Gross Airborne Activity Concentration (Ci m-3). 

• Gross Surface Activity Concentration (Ci m-2). 

• Radiation Intensity Aloft Inside Debris Cloud (R hr-1). 

• Radiation Intensity at Surface Inside Debris Cloud (R hr-1). 

• Radiation Intensity Above Contaminated Surface (intensity: R hr-1, 

tissue dose rate: rad hr-1, and film badge dose rate: rem hr-1). 

ORGAN DOSES 

• 50-Year Committed Equivalent Dose. 

o Ingestion or Inhalation (ICRP-72 data set). 

o Up to 40 organs or tissues; currently 23 organs (adrenals, bone 

surface, brain, breast, stomach wall, small intestine wall, upper 

large intestine wall, lower large intestine wall, kidneys, liver, extrathoracic region, lung, muscle, ovaries, pancreas, red marrow, skin, 

spleen, testes, thymus, thyroid, uterus, urinary bladder wall) plus

effective dose. 

• Plutonium Excretion Functions for Urine (Jones, 1985) 

Figure 1. Key features of computer code FIIDOS. 

9
Gross Inhalation 

Activity Intake 

(Ci)

Gross Ingestion 

Activity Intake 

(Ci)

Radiation Intensity 

Above 

 Contaminated Surface 

(R hr-1) Intensity-Activity 

Factor, Surface 

(R hr-1 per Ci m-2) Surface Activity 

Concentration 

(Ci m-2)

Gross 

 Surface Acitivity 

Concentration 

 (Ci m-2) 

Radiation Intensity 

At Surface 

Inside Debris Cloud 

(R hr-1) 

Resuspension 

Factor 

(Ci m-3 per Ci m-2)

Intensity-Activity 

Factor, Surface/Cloud

(R hr-1 per Ci m-3) Radiation Intensity 

Aloft 

Inside Debris Cloud 

(R hr-1) Intensity-Activity 

Factor, Aloft/Cloud 

(R hr-1 per Ci m-3)

Decay Adjustment 

For 

Time of Exposure

 Airborne Activity 

Concentration 

(Ci m-3)

Gross 

 Activity Airborne 

Concentration 

 (Ci m-3) 

Exposure Duration 

(hr)

Breathing Rate 

(m3

 hr-1)

Scaling 

Factor

Activity Intake of 

Specific Radionuclides 

 (Ci) 

Pu Intake Excretion 

Function 

(Ci per Ci)

Pu Excretion 

(Ci)

Inhalation Dose 

Conversion Factors

(rem Ci-1)

Ingestion Dose 

Conversion Factors 

(rem Ci-1)

Organ Dose 

Commitment 

(rem)

Figure 2. Schematic for calculation of organ dose.

10
Activity (Normalized) 

at Measurement Time 

(Ci)

ORIGEN2-SAIC 

Depletion Code

Gamma-Ray Spectral Data Radionuclide Inventory Data

Gamma-Ray Emission Rate 

(Normalized) 

at Measurement Time 

(γ/hr)

Weapon Data

Fallout Data

Measurement Data

Gamma-Ray Exposure 

Factor Surface 

(R/hr per γ/hr/m2)

Gamma-Ray Exposure 

Factor Surface-Cloud 

(R/hr per γ/hr/m3) 

Gamma-Ray Exposure 

Factor Aloft-Cloud 

(R/hr per γ/hr/m3

) 

Intensity-Activity Factor 

Aloft-Cloud 

(R/hr per Ci/m3

) 

Intensity-Activity Factor 

Surface-Cloud 

(R/hr per Ci/m3) 

Intensity-Activity Factor 

Surface 

(R/hr per Ci/m2

)

Figure 3. Schematic for calculation of intensity activity factors.

11
Table 1. User-supplied input for FIIDOS. 

Problem Identification and Control Data 

• Title of Problem 

• Type of Problem 

• Optional Output 

Weapon Data 

• Yield for Fissionable Material-Neutron 

Energy Sets 

• Activation Product Production 

• Actinide Element Production 

Radiological Measurement Data 

• Type of Measurement 

• Time of Measurement 

• Measured Value 

• Type of Measurement Device 

• Supplemental Measurement Data 

Fallout Data 

• Krypton-Xenon Removal 

• Fractionated Fission Product 

Identification 

• Fractionated Fission Product Factor 

• Fractionated Fission Product Spectrum 

Dose Calculation Data 

• Number of Exposure Incidents 

• Time of Exposure 

• Duration of Exposure 

• Breathing Rate 

• Airborne Activity - Surface Activity 

Ratio 

• Type of Dose Conversion Factor 

FIIDOS provides standard output and user-selected optional output. The standard output 

occurs automatically and provides a listing of the user-supplied problem input data and 

the basic dose results of a FIIDOS calculation. Three optional output modes can provide 

supplemental information on the details of a FIIDOS calculation. Section 3 provides a 

detailed description of the FIIDOS output. 

The computer program FIIDOS consists of a main program and 18 subroutines in 

addition to the ORIGEN2-SAIC code and its subroutines. A data library consists of 19 

files (17 read by FIIDOS and 2 read by the ORIGEN2-SAIC code) to provide capability 

to calculate a wide variety of problems. FORTRAN listings of the main program and 

subroutines are provided in Appendix B. 

FIIDOS calls the ORIGEN2-SAIC code, which is a slightly modified version of the 

ORIGEN2 code with inventory and spectra databases prepared by Science Applications 

International Corporation (SAIC). The fast fission inventories were supplied by England 

(1993a and 1993b) of LANL. SAIC corrected several inconsistencies and transcription

12
errors in the gamma-ray production data (Roberts, 1996). The results have been 

benchmarked against measurements of gamma-ray spectra from fission products 

produced from fast neutrons for measurement times of seconds to days. Previously this 

kind of agreement had been difficult. The agreement is currently good to within a few 

percent. The fission product inventories from 14 MeV neutrons were also supplied by 

England. 

Sample problems that illustrate the use of FIIDOS are given in Appendix C. They show 

FIIDOS’s capability to use different types of radiological measurements for calculating 

doses to internal organs. 

13
SECTION 2 

 TECHNICAL APPROACH 

2.1 INTRODUCTION 

The computer code FIIDOS calculates committed equivalent doses to various body 

organs that would result from the ingestion or inhalation of radioactive material produced 

by a nuclear detonation. These organ dose calculations are based on the amount of 

radioactive material ingested or inhaled, the radionuclide composition of the material, 

and organ dose conversion factors for each radionuclide. 

A variety of options is available within FIIDOS either to specify or to calculate the 

amount of radioactive material taken into the body. When the mode of intake is 

ingestion, the amount of material must be specified as input to FIIDOS. When the mode 

of intake is inhalation, the amount of material may be specified as input to FIIDOS or 

may be determined by FIIDOS for selected exposure situations. These situations include 

exposure inside a nuclear debris cloud and exposure above a contaminated surface. For 

either situation, the level of contamination may be specified in terms of activity 

concentration or radiation intensity. The time at which the level of contamination is 

specified may precede, follow, or be coincident with the time at which the inhalation 

exposure occurs. 

The radionuclide composition of the radioactive material is determined within FIIDOS by 

calling the ORIGEN2-SAIC code. It handles the production and decay of fission 

products, activation products, and actinides; it is time-dependent because of differential 

decay of the isotopic mix. FIIDOS uses data files with the fission product inventories for 

the fissioning of U-235, U-238, and Pu-239 by fast and 14-MeV neutrons; these files are 

read by ORIGEN2-SAIC. Provisions to modify the radionuclide composition to remove 

gaseous fission products and to reflect fission product fractionation effects are included 

in FIIDOS to be consistent with the original version. However, the ORIGEN2-SAIC 

code in FIIDOS could be used to allow additional fractionation by modifying the 

inventory at each time step of the calculations. This modification, if adopted, would 

allow for continuous fractionation adjustments. This is currently not done in FIIDOS 

because of the large uncertainties in the required input parameters and a systematic 

analysis of the impacts has not been performed. A fractionation report (Trabalka and 

Kocher, 2007) provides some bounding of the issue, but that is currently under peer 

review and an assessment of impact is needed before any implementation or adjustments 

to current procedures. 

The current version represents a reconfiguration of the code to include only one set of 

dose coefficients (e.g., from ICRP-72) for inhalation and one set for ingestion and has the 

capacity to work with up to 40 organs to provide for future expansion. For current use in 

the NTPR Program FIIDOS uses two sets of dose conversion factors (also called dose 

14
coefficients) to produce 50-year tissue or organ dose commitments from the ingestion 

and inhalation pathways. Conversion factors are tabulated for individual organs and 

effective dose for up to 148 fission products, 17 activation products, and 18 actinides. 

Organ dose conversion factors are available from ICRP-72 (currently 23 organs plus 

effective dose). 

Previous releases of FIIDOS included up to 11 sets of internal dose conversion factors as 

user-selectable options. ORNL TM-190 contained factors for 148 fission product 

isotopes and ICRP-30 contained factors for 104 and 42 isotopes for small and large 

particles, respectively. A third optional set of internal dose conversion factors provided 

an expanded inventory of 412 nuclides that was also based upon methods and models of 

ICRP Publication 30. 

A urinary excretion function calculation for Pu-239 is included as an option in FIIDOS. 

With this option, the activity of Pu-239 that is inhaled or ingested serves as input to an 

exponential excretion function (Jones, 1985) to predict the activity that is expected in 24-

hour urine samples at specified times post-detonation. Where F(t) is the unitless fraction 

of initial uptake (e.g., to the bloodstream) found in 24-hour urine at time t (days) after 

uptake, the function is expressed as: 

F(t) = 4.75 × 10-3 (e-(0.558 t)) + 2.39 × 10-4 (e-(.0442 t)) + 

8.55 × 10-5 (e-(0.0038 t)

) + 1.42 × 10-5 (e-(0.0000284 t)). (2.1) 

For intake I (Ci), the fraction of I that is absorbed into the bloodstream from the small 

intestine is given by an uptake fraction, f1, which is specific to the mode of intake. The 

following f1 values from ICRP-30 are used: 

for ingestion of Pu, 

-5 f1 = 1 × 10 , 

and for inhalation of Pu, 

-2 f1 = 5 × 10 . 

Then, the 24-hr urine activity U(t) (Ci) is given by: 

U(t) = F(t) × I × f1. (2.2) 

Additional details concerning the technical approach adopted for FIIDOS are described 

in the following material. Section 2.2 presents the basic equations and parameters used 

for organ dose calculations and the specific procedures used in FIIDOS to determine the 

values of the parameters in the dose equations. A discussion of the limitations of the 

methodology and data used in FIIDOS is given in Section 2.3. 

15
2.2 EQUATIONS AND PARAMETERS 

The equation for determining the committed equivalent dose to organ j resulting from the 

intake of radionuclide i is: 

Di,j = A × Pi × DCFi, x106

 (2.3) 

Where: 

Di,j = committed equivalent dose (rem) to organ j due to intake of 

radionuclide i, 

A = gross activity (Ci) of the radioactive material taken into the 

body by ingestion or inhalation, 

Pi = activity fraction of radionuclide i in the material (Ci per Ci), 

and 

DCFi,j = 50-year organ dose conversion factor (rem μCi-1) for the 

dose to organ j resulting from the intake of radionuclide i by 

ingestion or inhalation. 

As mentioned in Section 2.1, a variety of options can be used to specify or determine the 

amount of radioactive material taken into the body. These options include: 

• gross ingestion activity intake - Aing (Ci), 

• gross inhalation activity intake - Ainh (Ci), 

• gross airborne activity concentration - AC (Ci m-3), 

• gross surface activity concentration - SC (Ci m-2), 

• radiation intensity aloft inside debris cloud - Ica (R hr-1), 

• radiation intensity at surface inside debris cloud - Ics (R hr-1), and 

• radiation intensity above contaminated surface - Is (R hr-1). 

It should be noted that for the first option, Aing, the mode of intake is ingestion; for the 

other options, the mode of intake is inhalation. 

For those options in which the level of contamination is specified in terms of activity (Ci) 

or activity concentration (Ci m-3 or Ci m-2), the amount of radioactive material taken into 

the body, A (Ci), is given by one of the following equations: 

16
A = Aing (2.4) 

A = Ainh (2.5) 

A = AC × BR × T or (2.6) 

A = SC × K × BR × T (2.7) 

Where: 

BR = breathing rate (m3

 hr-1), 

T = duration of exposure (hr), and 

K = resuspension factor (Ci m-3 per Ci m-2

, or m

-1). 

For those options in which the level of contamination is specified in terms of radiation 

intensity (R hr-1), the amount of radioactive material taken into the body, A (Ci), is given 

by one of the following equations: 

A = [Ica × (∑E S × ψca)

-1] × BR × T (2.8) 

A = [Ics ×(∑E S × ψcs)

 -1] × BR × T, or (2.9) 

A = [Is × (∑E S × ψs)

 -1] × BR × T (2.10) 

Where: 

S = emission rate of gamma rays of energy E from the radioactive 

material (γ hr-1 per Ci), 

ψca = energy dependent factor relating radiation intensity aloft 

inside debris cloud to gamma ray emission rate density 

(R hr-1 per γ hr-1

m-3), 

ψcs = energy dependent factor relating radiation intensity at surface 

inside debris cloud to gamma ray emission rate density 

(R hr-1 per γ hr-1

m-3), and 

ψs = energy dependent factor relating radiation intensity above 

contaminated surface to gamma ray emission rate surface 

density (R hr-1 per γ hr-1

m

-2). 

The bracketed expression in Equations 2.8 and 2.9 provide the basis for translating 

radiation intensity (R hr-1) into an equivalent gross airborne activity concentration 

17
(Ci m-3); similarly, the bracketed expression in Equation 2.10 yields an equivalent gross 

surface activity concentration (Ci m-2). 

These equations can be used to calculate the committed organ dose resulting from the 

ingestion or inhalation of a specific radionuclide. However, a set of equations that is 

more closely related to the type of input data available to FIIDOS will be developed by 

replacing the activity fraction parameter (i.e., Pi in Equation 2.3) and the gamma-ray 

emission rate parameter (i.e., S in Equations 2.8, 2.9, and 2.10) with more basic 

parameters. 

As previously discussed, FIIDOS uses radionuclide inventory data and gamma-ray 

spectral data calculated by the computer code ORIGEN2-SAIC. The basis for these 

ORIGEN2-SAIC calculations is the number of fissions specified to have occurred in a 

fuel material (e.g., U-235). The radionuclide inventory data and the gamma-ray spectral 

data calculated for FIIDOS are based on 1014 fissions in a fuel material with the 

corresponding normalized activities of actinides and activation products. This fission 

input value for the ORIGEN2-SAIC calculations is somewhat arbitrary, but was selected 

to avoid computer arithmetic limits that could occur if very low values or very high 

values had been used. Accordingly, the parameters taken directly from the ORIGEN2-

SAIC run are: 

Ai = activity of radionuclide i resulting from 1014 fissions (Ci per 1014

fissions), 

AT = total activity resulting from 1014 fissions (Ci per 1014 fissions), 

and 

ST = rate of emission of gamma rays of energy E from the radioactive 

material produced by 1014 fissions (γ hr-1 per 1014 fissions). 

The relationships between the above parameters and the parameters Pi and S are: 

Pi = Ai ×(AT)

-1 and (2.11) 

S = ST × (AT)

-1 (2.12) 

A set of dose calculation equations, with each equation applicable to a specific material 

intake option, is constructed by successively substituting Equations 2.4 through 2.10 into 

Equation 2.3 and using Equations 2.11 and 2.12 to eliminate the parameters Pi and S. 

The resulting equations are: 

Di,j = DCFi,j × Ai × Aing × (AT)

 -1 × 106

 (2.13) 

18
Di,j = T × BR × DCFi,j × Ai × AC × (AT)

-1 6 × 10 (2.15) 

Di,j = T × BR × K × DCFi,j × Ai × SC × (AT)

-1 6 × 10 (2.16) 

Di,j = T × BR × DCFi,j × Ai × Ica × (∑EST ×ψca)

 -1 6 × 10 (2.17) 

Di,j = T × BR × DCFi,j × Ai × Ics × (∑EST × ψcs)

 -1 6 × 10 (2.18) 

Di,j = T × BR × K × DCFi,j × Ai × Is × (∑EST × ψs)

 -1 6 × 10 (2.19) 

The structure of the above set of equations suggests that a general dose calculation 

equation be defined as: 

6 Di,j = T × BR × K × DCFi,j × Ai × SF × 10 (2.20) 

Where: 

T, BR, and K are set equal to dimensionless unity if the gross ingestion intake 

(AC in Equation 2.13), or the gross inhalation intake (Ainh in Equation 2.14) is 

specified, K is set equal to dimensionless unity if the gross airborne activity 

concentration (AC in Equation 2.15), the radiation intensity aloft inside a debris 

cloud (Ica in Equation 2.17), or the radiation intensity at the surface inside a 

debris cloud (Ics in Equation 2.18) is specified, and SF is given by one of the 

following equations: 

SF = Aing × (A )

-1

T (2.21) 

SF = Ainh × (A )

-1

T (2.22) 

SF = AC × (A )

-1

T (2.23) 

SF = SC × (A )

-1

T (2.24) 

SF = Ica × (∑EST × ψca)

-1 (2.25) 

SF = Ics × (∑EST × ψcs)

-1 (2.26) 

SF = Is × (∑EST × ψs)

-1 (2.27) 

Note that in Equation 2.20 the committed equivalent dose is calculated with the 

restriction that all parameters remain constant during the period of exposure. If the 

conditions of exposure change or there is significant decay, the period of exposure should 

be subdivided into smaller intervals. Apply Equation 2.20 successively to each interval 

with the results summed to give the committed equivalent dose for the total period. The 

long duration option available in FIIDOS should be utilized for this type of "time19
dependent" dose calculation. 

The following sections provide descriptions of the six parameters in Equation 2.20. Three 

of the parameters (i.e., T, BR, and K) are user-supplied input to FIIDOS; guidance is 

provided regarding the selection of values for the parameters. The parameter DCFi,j is 

contained within FIIDOS as sets of ingestion and inhalation dose conversion factors; the 

basis for these factors is discussed. The parameters Ai and SF are calculated within 

FIIDOS; the procedures used to calculate these parameters and the required user-input for 

the calculations are discussed. 

2.2.1 Duration of Exposure 

The duration of exposure T (hr), is the amount of time the individual is exposed to the 

inhalation source. If the gross ingestion or inhalation activity intake is specified, the 

parameter T should be set to one (1.0). The duration of exposure is a user-supplied input 

to FIIDOS. 

2.2.2 Breathing Rate 

The breathing rate, BR (m3

 hr-1), is a user-supplied input. If the gross ingestion or 

inhalation activity intake is specified, the parameter BR should be set to one (1.0). Since 

the breathing rate is dependent upon the physical activity of the individual during his 

exposure, the following material assists the FIIDOS user in selecting the appropriate 

breathing rate. 

The breathing rate for a typical adult male is specified in ICRP (1975) Publication 23 and 

NCRP (1997) Report No. 125 as 1.2 m3

 hr-1 for light activity. According to Bates (1966), 

this value is the approximate breathing rate during walking on a flat surface at a speed of 

about three miles per hour. 

Higher breathing rates would result from more physically demanding activities. Based 

on the material according to Bates (1966) and ICRP (1975) Publication 23, and NCRP 

(1997) Report No. 125, breathing rates of 1.5 m3

 hr-1 for moderate activity and 2.0 m3 hr-1

for heavy activity appear reasonable. Correspondingly, lower breathing rates would 

result from less physically demanding activities. The breathing rate cited in ICRP (1975) 

Publication 23 for resting is 0.45 m3

 hr-1. That cited in NCRP (1997) Report No. 125 for 

low activity is 0.6 m3

 hr-1, where low activity is defined as approximately 30 percent 

above basal with respect to minute volume. 

20
2.2.3 Airborne Activity-Surface Activity Ratio 

The parameter K (m-1) is the ratio of the airborne activity (Ci m-3) to the surface activity 

(Ci m-2). This parameter is needed for a dose calculation if information on the airborne 

contamination is not directly available but rather must be inferred from information on 

the surface contamination. For example, a post-shot radiation survey of an area 

contaminated with fallout that measures the radiation intensity (R hr-1) of the deposited 

fallout provides information on the surface contamination, not airborne contamination. 

The airborne activity-surface activity ratio used in the dose calculation equation should 

be the ratio that is appropriate for the time at which the inhalation exposure occurred. If 

the duration of the exposure is long, it may be necessary to subdivide the period of 

exposure into smaller intervals and use different values of the ratio for each interval. 

Such a situation could occur if the phenomena or mechanisms that relate airborne activity 

and surface activity change during the exposure period. 

In the FIIDOS methodology, the parameter K is a user-supplied input and no default 

values are provided. The following material introduces approaches that can be used to 

develop estimates of the airborne activity-surface activity ratio. Section 2.2.3.1 addresses 

the relationship between airborne activity and surface activity that would occur during 

the passage of a fallout-depositing, aerosol cloud. Section 2.2.3.2 addresses the 

relationship between the airborne activity and surface activity that would occur due to the 

resuspension of previously deposited material by natural or other sources. 

2.2.3.1 Deposition from Aerosol Cloud 

An aerosol cloud with an airborne activity concentration AC (Ci m-3) deposits fallout 

material during its passage. The surface activity concentration, SC (Ci m-2), produced by 

the passing cloud is: 

SC = ∫t AC × V × dt (2.28) 

Where 

V (m sec-1) = the rate at which material falls from the cloud. 

Assuming that AC and V are independent of time, the surface activity 

concentration resulting from the cloud for a deposition period of T (sec) is: 

SC = AC × V × T (2.29) 

Thus, the ratio of the airborne activity to the surface activity, K (m-1), is: 

K = (V × T)

-1 (2.30) 

In the above equation, the fall velocity V (m sec-1) is a single-valued parameter. V could 

21
be either a nominal value or an average value. An average value could be calculated if 

information on the distribution of activity as a function of particle size were available. 

Where particle size data are unavailable, V can be obtained from the nuclear cloud 

stabilization height and time after burst. 

As an illustration, consider an exposure scenario involving a high-yield nuclear 

detonation. The time-period during which fallout deposition occurred at the location of 

interest was 10 hours. The fallout particles had a measured diameter of 60 μm and a 

density of 2 g cm-3, giving a fall velocity of 0.2 m sec-1. For these values of V and T, the 

value of K is 1.4 × 10-4

 m

-1. 

2.2.3.2 Resuspension of Deposited Material 

Resuspension refers to a process in which previously deposited radioactive particles are 

removed from the surface to form an airborne aerosol. In literature on resuspension, the 

ratio of the airborne activity (Ci m-3) to the surface activity (Ci m-2) is characterized by a 

resuspension factor (m-1). The resuspension factor is a form of the parameter K used in 

the FIIDOS methodology when the exposure scenario involves resuspension. 

The concept of a resuspension factor is best suited to situations having spatial 

independence in both airborne activity and surface activity. Nevertheless, resuspension 

factors have been reported for many situations involving disturbances to the surface of 

limited area extent. A good introduction to resuspension factors is provided in the 

Reactor Safety Study (USNRC, 1975). Table 2 shows the results of the literature survey 

cited in the study and lists the references. 

Resuspension is a rather complicated process, and the principles governing the process 

are not well understood. However, resuspension factors have been determined 

experimentally for several conditions. These results show that the resuspension factor 

depends on the activity causing resuspension, the characteristics of the surface, and the 

characteristics of the deposited particles. In addition, the resuspension factor is timedependent, is affected by the wind velocity, and is dependent upon the height above the 

surface. Unfortunately, the data on resuspension processes are not adequate to permit the 

development of a general model of resuspension that incorporates all observed effects. 

Natural resuspension refers to the wind-driven resuspension that occurs in the absence of 

any extraordinary activity that could cause resuspension. Models of natural resuspension 

are based on the resuspension of nuclear detonation fallout or dispersed plutonium in 

desert environments, because most of the available resuspension data have been taken 

from such situations. Since the resuspension factor decreases with time, the natural 

resuspension value includes a time dependent resuspension factor. 

For natural resuspension, the Reactor Safety Study proposed a time dependent 

resuspension factor of the following form: 

K(t) = K0 × e-(λt)

 + Ke (2.31) 

22
-5 The initial resuspension factor (K0) is given a value of 10 m

-1; this value is termed a 

"reasonable estimate" and generally corresponds to the values cited for natural, winddriven resuspension factors. The equilibrium resuspension factor (Ke) is given a value of 

10-9 m

-1; this value is based on measurements of the resuspension factor in aged (~17 

years) fallout fields and contaminated areas. The decay constant (λ) is given a value of 

0.677 y-1; which reflects a half-life (T = (ln 2) × λ

-1

1/2 ) of 0.977 yr; this half-life is based 

on assuming that the resuspension factor decreases exponentially from 10-5 m

-1 -9 to 10 m-1

in 17 years. 

The Reactor Safety Study resuspension factor model is "calibrated" to the long-term 

behavior of the resuspension factor and might not correctly portray the short-term 

behavior. A model which is "calibrated" to both the short-and long-term behavior of the 

resuspension factor was suggested by Anspaugh (1975). This model has the following 

form: 

-(λ × [SQRT{t}]) K(t) = K0 × e + Ke (2.32) 

-4 In this model, the initial resuspension factor (K0) is given a value of 10 m-1; this value 

has been termed “conservative”, and appears to encompass both natural resuspension and 

artificial or man-made resuspension. As with the Reactor Safety Study model, the 

equilibrium resuspension factor (K -9 e) is given a value of 10 m

-1. The decay constant (λ) 

is given a value of 0.15 in units of days-1/2. This value, along with the exp (-λ × t

1/2) 

expression, is intended to cause the resuspension factor to exhibit: a half-life of 5 weeks 

during the first 10 weeks after the initial deposition, a half-life of about 10 weeks during 

the next 30 weeks, and an equilibrium value after 17 years. 

A comparison of the Anspaugh and the Reactor Safety Study resuspension models is 

given in Figure 4. The initial order-of-magnitude difference between the two 

resuspension factor expressions disappears rapidly and the difference between the two 

factors is at most a factor of two after one year. 

Wind speed also affects the resuspension factor. The effect of the wind speed is strongly 

dependent upon the characteristics of the deposited particles and the surface material. In 

addition, as time passes and the deposited particles become more intimately mixed with 

the surface material, the effect of the wind speed is likely to be lessened. Because of 

these complications, various wind speed relationships are reported in the resuspension 

factor literature; for example, Stewart (1964) reports cases where no relationship between 

airborne concentration and wind speed was observed and cases where the value of the 

resuspension factor varied approximately as the wind speed cubed. 

23
Table 2. Resuspension factors reported in reactor safety study. 

}

}

}

}

Arid/Desert

4x10-7 near road graded in fallout field (a)

3x10-5 in Land Rover during travel to work site 

and outside during work; fission products 

(5-18 hr)(a)

3 to 10x10-4 downwind of crater (a)

for UO2

1x10-3 mechanical disturbances (a)

5x10-4 dust from vehicles

for PuO2

10-4 to 10-6 dust from pedestrians (a)

3x10-7 particles of 7 μm MMD on 6-m circles 

(sandy) furrowed and rocky with sand base 

(dry) (b)

1x10-7 to 3x10-7 (wet) (b)

1.2x10-7 in 1000 μg/m2 isopleth

PuO2

1.4x10-7 in 100 μg/m2 isopleth Safety

Test (c)

1.6x10-6 in 10 μg/m2 isopleth

~35 day half-time air concentration decay 1 to 3 μm median 

aerosol size

38 day half-time for resuspension of fission products of 

Schooner (d)

76 day half-time for resuspension of fission products from 

Baneberry (d)

3x10-10 for 8- to 10- year Pu aged deposit (e)

2x10-9 for direction of strongest wind (e)

Semiarid/Grassland

5x10-6 (ZnS) walking and loading boxes (f)

1x10-5 (±.5x10-5)limestone, rock, sand, grass, 

bushes; fission products (a)

.8 to 2x10-7 crater of tower shot; fission products; road 

graded from soil disturbance (a)

2x10-5 to 4x10-6 in vehicle on road graded through fallout (a)

8x10-6 0 to 4 μm U3O8 undisturbed

sandy soil

5x10-7 0 to 12 μm U3O8 with desert

grasses (a)

8x10-9 to 10-11 Y-91 aqueous solution on sandy soil-rain 

weathering small plot (a)

1x10-7 for particles of 7 μm MMD on 6-m circles, 

grass plot (dry) (b)

4x10-8 for particles of 7 μm MMD on 6-m circles, 

grass plot protected by snow fence (dry) (b)

2x10-7 both cases, above, wet (b)

Urban/Suburban

2.5x10-6 sandblasting for I-131 removal (g)

2x10-6 0 to 4 μm U3O8 particles on concrete slabs (a)

1.5x10-7 0 to 12 μm U3O8 particles on concrete (a)

10-4 to 10-2 fraction resuspended per pass through 

particles(h)

2x10-2 to 2x10-4 initially very rapid half-time of a few days

~2x10-5 to 2x10-3 at 4 days

Interiors

1x10-5 heavy work (i) ZnS (3.1 μm)

7x10-4 light work (i) CuO (2 μm)

2x10-3 operations (j)

.4 to 7x10-3 clothes change and other activity (k)

1.2x10-4 people walking in change room (k)

5x10-5 PuO2, many steps (l)

3x10-6 PuNO3, many steps (l)

2x10-4 to 4x10-5 in enclosed space I-131 in brick dust (a,g)

24
Table 2. Resuspension factors reported in reactor safety study (Concluded) 

(a) Stewart, K. 1964. “The Resuspension of Particulate Material from Surfaces.” in Proc. 

Symp. Surface Contamination, Gatlinburg, Tenn. 1964. Oxford, U.K.: Pergamon Press. 

(b) Healy, J. W., Fuguoy, J. J. 1959. “Wind Pickup of Radioactivity Particles from the 

Ground.” Progress in Nuclear Energy, Series 12, Vol. 1, pp. 427-436. 

(c) Wilson, R. H., Thomas, R. G., Stannard, J. N. 1960. Biomedical and Aerosol Studies 

Associated with a Field Release of Plutonium. Sandia Corporation. Report WT-1511. 

(d) Anspaugh, L. R., Phelps, P. L., Kennedy, N. C., Booth, H. G. 1973. “Wind Driven 

Redistribution of Surface-Deposited Radioactivity” in Proc. IAEA Symp. Environmental 

Behavior of Radionuclides Released In the Nuclear Industry, Aix-en-Provence, May 14-18, 

1973. 

(e) Anspaugh, L. R. 1973. “Relationship Between Resuspended Plutonium in Air and Soil.” 

U.S. Department of Energy, Nevada Operations Office. NVO-140. 

(f) Schwendiman, L. C. 1958. “Probability of Human Contact and Inhalation of Particles.” 

Health Physics, 1, 352-355. 

(g) Chamberlain, A. C., Chadwick, R. C. 1965. “Transport of Iodine from Atmosphere to 

Ground.” Harwell, Berkshire: United Kingdom Atomic Energy Authority Report AERE-R 4870. 

(h) Anspaugh, L. R., Shinn, J. H., Wilson, D. W. 1974. “Evaluation of the Resuspension 

Pathway Towards Protective Guidelines for Soil Contamination with Radioactivity,” in Proc. 

IAEA/WHO Symp. on Radiological Safety Evaluation of Population Doses and Application of 

Radiological Safety Standards to Man and the Environment, Portoroz, Yugoslavia, May 20-24, 

1974. 

(i) Fish, B. R., et al. 1965. “Redispersion of Settled Particulates.” Oak Ridge, TN: Oak 

Ridge National Laboratory. Report ORNL-TM-1049. 

(j) Bailey, J. C., Rohr, R. C. 1953. “Air-Borne Contamination Resulting from Transferable 

Contamination on Surfaces.” Oak Ridge, TN: Union Carbide Nuclear Company, Oak Gaseous 

Diffusion Plant. Report K-1088. 

(k) Brunskill. 1964. “The Relationship Between Surface and Airborne Contamination.” in 

Proc. Symp. Surface Gatlinburg, Tenn. Oxford, U.K.: Pergamon Press. 

(l) Jones, I. S., Pond, S. F. 1964. “Some Experiments to Determine the Resuspension 

Factor of Plutonium Various Surfaces.” in Proc. Symp. Surface Contamination, Gatlinburg, 

Tenn. Oxford, U.K.: Pergamon Press. 

Resuspension factor modeling by Anspaugh (1975) is most applicable to the 

resuspension of material in a desert environment. Based on soil erosion studies 

conducted at the Nevada Test Site, Anspaugh modeling suggests that the resuspension 

factor is proportional to the wind speed squared. The comparison between the model and 

experimental measurements showed good agreement. 

25
The resuspension factor is also dependent on the height above the surface at which the air 

concentration is measured. However, this effect is likely to be dependent on the 

characteristics of the deposited particles and the surface material. Not surprisingly, 

various height effects are reported in the resuspension factor literature. Stewart (1964) 

observed that the resuspension factor decreased by a factor of three as the height was 

increased from 1 to 2 feet above the surface. However, Anspaugh’s (1975) modeling 

indicates that the resuspension factor varies by only 20 percent over a height range of 0.5 

to 2 meters. The existing models of natural resuspension are very simplistic. Estimated 

resuspension factors should be considered order-of-magnitude estimates. Rather than 

estimating specific resuspension factors, it might be more appropriate to provide an 

upper-bound estimate of a resuspension factor. 

Man-made resuspension refers to the resuspension caused by human activity such as 

pedestrian and vehicular traffic. Some of the resuspension factor values cited in Table 2 

reflect man-made resuspension. The values range from 10-4 

m

-1 -6 to 10 m-1 for 

pedestrian-promoted resuspension, and from 2 × 10-5 m

-1 -6 to 4 × 10 m-1 for resuspension 

caused by vehicular traffic; however, because derivation of these data are taken from 

different experiments, direct comparisons should not be made. 

No models of man-made resuspension are proposed. Estimates of resuspension factors 

should be based on the experimental data that most adequately characterize the situation 

of interest. 

2.2.4 Dose Coefficients 

The dose coefficients, DCFi,j (rem μCi-1), used in the most recent version of FIIDOS 

provide 50-year equivalent dose commitments to organ j per unit intake of radionuclide i

and are based on the concepts in ICRP-60 and the models described in ICRP Publications 

66, 68, and 72. As discussed in Section 1.2.4, the ICRP-72 inhalation dose coefficients 

provide a maximum dose commitment for intakes of aerosols of 1-, 3-, 5-, or 10-

micrometer AMAD. Figure 1 lists the 23 organs and tissues for which ICRP-72 dose 

coefficients are provided in FIIDOS. The ICRP-72 dose coefficients represent a 

significant departure from those based on ICRP-30 and earlier publications in several 

respects, as outlined below (Leggett, 2003). 

Dosimetric Quantities 

ICRP-60 introduces a new dosimetric quantity, the equivalent dose (HT), which is the 

absorbed dose (energy absorbed per unit mass) averaged over a tissue or organ and 

weighted by the radiation quality that is of interest. The weighting factor is the radiation 

weighting factor (wR) and is selected for the type and energy of the radiation incident on 

the body, or, in the case of sources within the body, emitted by the source. In ICRP-30, 

the weighting factor was applied to the absorbed dose at a point and called the quality 

factor (Q). The weighted absorbed dose was called the dose equivalent (H). 

26
Resuspension Factors from

Reactor Safety Study and Anspaugh Model .

1.E-9

1.E-8

1.E-7

1.E-6

1.E-5

1.E-4

0 1000 2000 3000 4000 5000 6000 7000

Time (Days)

Reactor Safety Study

Anspaugh Model

Resuspension Factors from

Reactor Safety Study and Anspaugh Model .

1.E-9

1.E-8

1.E-7

1.E-6

1.E-5

1.E-4

0 1000 2000 3000 4000 5000 6000 7000

Time (Days)

Reactor Safety Study

Anspaugh Model

Figure 4. Comparison of time-dependent resuspension models. 

27
Subsidiary dosimetric quantity: The committed equivalent dose, HT(τ), is the time 

integral of the equivalent dose rate, where τ is the integration time in years following the 

intake. When τ is not specified, the implied value for adults is 50 years. 

Under ICRP-60, the effective dose (E) is the equivalent dose weighted by the tissue 

weighting factor, which represents the relative contribution of that organ or tissue to the 

total detriment due to stochastic effects resulting from uniform irradiation of the whole 

body. The effective dose replaces effective dose equivalent in ICRP-26 and -30. ICRP60 provides a modified and expanded set of tissue weighting factors as compared to 

ICRP-30. In most cases, effective dose conversion factors are relatively insensitive to 

changes in the tissue weighting factors. 

Subsidiary dosimetric quantity: The committed effective dose, E(τ), is the time integral 

of the effective dose rate, where τ is the integration time in years following the intake. 

When τ is not specified, the implied value for adults is 50 years.

Respiratory Tract Model 

The updated human respiratory tract model (ICRP-66) addresses age, gender, breathing 

rate, and other factors (particle sizes) in total and regional deposition of inhaled material 

in the respiratory tract. For a reference adult male, the ICRP-66 model predicts lower 

total deposition in the respiratory tract and lower deposition in the lower lungs than does 

the Task Group Lung Model (TGLM) used in ICRP-30 for most particle sizes. 

The ICRP-66 model predicts much different rates of absorption from the respiratory tract 

to blood. The updated model addresses the heterogeneous distribution of radiosensitive 

cells within the respiratory tract. In contrast, the TGLM assumes that the total activity in 

the lungs is uniformly distributed in the total blood-filled lungs with a mass of 1000 g. 

The differences in the biokinetic and dosimetric properties of the updated ICRP-66 model 

and the TGLM lead to substantially different estimates of lung dose in many cases. 

Gastrointestinal Absorption Fractions (f1) 

For the reference, adult male, substantial changes in f1 values have been made for some 

forms of cobalt, tellurium, lanthanides, and actinide elements, including uranium. Doses 

to systemic tissues change nearly in proportion to f1 in most cases (except when doses to 

tissues result mainly from penetrating radiations originating in the intestinal contents). 

Some systemic models used in ICRP-68 feature feedback from systemic tissues back to 

gastrointestinal contents. 

Systemic Biokinetic Models 

The updated models provide age-specific biokinetics for 31 elements. The models for 

some elements are more detailed and physiologically realistic than the corresponding 

models in ICRP-30. 

In ICRP-30, decay chain members produced in the body generally were assigned the 

biokinetic model of the parent radionuclide; this is referred to as “shared kinetics” of 

28
decay chains. The updated models retain “shared kinetics” for many decay chains. If the 

parent is an isotope of lead, radium, thorium, or uranium, then a radionuclide (other than 

a noble gas) formed either in soft tissue or on bone surfaces is assumed to have 

“independent kinetics,” and a radionuclide formed in the bone volume is assigned the 

biokinetics of the parent. 

Comparisons were made between maximum dose ICRP-72 inhalation DCFs with ICRP30 based factors (1- and 20-micrometer AMAD aerosols) and ICRP-72 with ICRP-30 for 

ingestion (all in rem per curie intake) for a five organs of interest. A representative highyield oceanic shot was selected (CASTLE BRAVO). Times after detonation range from 

H+1 to H+8760 hours. Comparisons are depicted in Figures 5 through 7. 

The two sets of ingestion and inhalation dose conversion factors used in FIIDOS for 

current dose calculations are given in Appendix A, Tables A-1 and A-2. 

CASTLE BRAVO Ratio (inhalation): ICRP-72 max to 

ICRP-30 (1 micron AMAD) 

0.1

1

10

149244896168336730146029208760

Time after detonation (h+hour)

Ratio

lli wall

r marrow

Bone surf

testes

thyroid

Figure 5. The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ 

dose from inhalation of 1-micrometer AMAD particles for selected organs. 

29
CASTLE BRAVO Ratio (inhalation): ICRP-72 max to 

ICRP-30 (20 micron AMAD) 

0.1

1

10

149244896168336730146029208760

Time after detonation (h+hour)

Ratio

lli wall

r marrow

Bone surf

testes

thyroid

Figure 6. The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ 

dose from inhalation of 20-micrometer AMAD particles for selected organs. 

Figure 7. The ratio of the ICRP-72 maximum organ dose to the ICRP-30 organ 

dose from ingestion for selected organs. 

30
Tables A-1 and A-2 provide the ingestion and inhalation dose conversion factors from 

ICRP-72 (ICRP, 1996) which are based on ICRP-60 and the lung and systemic biokinetic 

models based thereon (ICRP, 1991; 1994a; 1994b). 

2.2.5 Relative Radionuclide Inventory 

The relative radionuclide inventory is the amount of each radionuclide (Ci) present in a 

model sample of nuclear debris or fallout (based on 1014 fissions) at a specified time. 

This inventory includes fission products, activation products, and actinide elements. The 

inventory appears in the dose calculation equation, Equation 2.20, as the parameter Ai. 

The relative radionuclide inventory is calculated in the ORIGEN2-SAIC code. The 

initial inventory is constructed based on user-supplied data on fission yield, activation 

product production, and actinide element production. After decay, the inventory can be 

modified by removing gaseous fission products and by adjusting specific radionuclide 

concentrations to reflect fission product fractionation effects. The techniques used to 

construct and to modify the relative radionuclide inventory are described below. 

Fission Products 

FIIDOS obtains a decayed fission product inventory by a mixing of initial fission 

products from U-235, U-238, and Pu-239 by fast or 14-MeV neutrons. The mixture of 

the initial six inventories is decayed by the isotope generation and depletion code 

ORIGEN2-SAIC. The inventories are based on 1014 fissions with an instantaneous (i.e., 1 

msec) irradiation time to avoid computer underflow problems. This code is a slightly 

modified version of the ORIGEN2 code with modifications made by SAIC to use fission 

product data provided by England (1993a and 1993b), and ENDF/B-VI decay and 

gamma-ray spectral information. Information for actinides and activation products is 

provided as user input to the ORIGEN2-SAIC code. Nearly 1600 isotopes are calculated, 

i.e. 688, 129, and 781 activation products, actinides, and fission products, respectively. 

The decay of this mixed inventory is calculated through 40 standard decay times. These 

standard decay times range from 0.001 seconds to 317 years in three time steps per 

decade. The decay inventory and spectra at any specific time of interest are calculated by 

one additional decay from the nearest standard decay time. When the inventory output is 

requested the activity of 148 fission product radionuclides are listed (see Table 3). These 

radionuclides were determined to be the important fission product radionuclides in terms 

of dose to internal organs. 

The user must provide the nuclear detonation yield. ORIGEN2-SAIC starts with an 

inventory produced by mixing the six fissionable material/neutron energy inventories. 

FIIDOS requires six yields in kilotons (kT) in order to combine the six fission product 

inventories as described above. The original version of FIIDOS had only one option; i.e. 

it required the user to give the yield for all six. This information may not be available, 

especially for the fission yields that were produced directly from 14-MeV neutrons. 

31
Information about the fusion yield of the weapon is more likely to be available. Thus in 

FIIDOS2, FIIDOS3, and FIIDOS4, an additional option for specifying the total yields by 

fissile fuel isotope is provided. For this option, the total yield, each fissile isotope yield 

and the fusion yield are required. The six yield fractions are determined by solving a 

balance equation involving the amounts of energy released from fast fission, 14-MeV 

fission, and fusion. Information from calculations on a homogeneous sphere of fissile 

material is used to estimate some of the parameters in the balance equation to provide a 

reasonable approximation for dividing the fission yields between fast and 14-MeV types. 

The equations are encoded in the FISFRC.FOR subroutine and are too lengthy for 

inclusion here, but the results are illustrated in Figure 8. The main observation is that a 

small amount of fusion can produce a large increase in 14-MeV fission and this can result 

in an inventory change. An additional observation is that as the fusion fraction of the 

yield gets larger than 50%, a constant ratio between the fast and 14-MeV proportions 

develops, which is independent of the fusion fraction. These results are based on 

simplified balance equations and should be viewed as a non-rigorous method for 

determining the six fission yields. This option is recommended when detailed weapon 

yield information is not available. 

FIIDOS determines the complete relative radionuclide inventory, which includes all 

fission product radionuclides present in nuclear debris or fallout at the exposure time and 

the measurement time. 

Activation Products 

ORIGEN2-SAIC calculates the decayed inventory for 17 activation products and their 

daughters (see Table 4). These radionuclides were selected because of their possible 

importance to internal organ doses. Data on the amount of each activation product 

radionuclide (Ci kT-1) initially produced by the nuclear weapon are input by the user 

(from LLNL, ca. 1970). FIIDOS calculates the amount of each activation product 

radionuclide present at either the exposure time or the measurement time. The inventory 

is normalized to 1014 fissions to produce a relative radionuclide inventory of activation 

products. 

32
Figure 8. Fission fraction results from subroutine FISFRC.

33
Table 3. Fission product radionuclides and standard decay times* used in FIIDOS. 

 

Se-79 Y-92 Mo-105 Sb-129 Cs-134m Pr-144 

Br-82 Sr-93 Tc-105 Te-l29 I-135 Pr-144m 

Br-83 Y-93 Ru-105 Te-129m Xe-135 Ce-145 

Kr-83m Zr-93 Rh-105 I-129 Xe-135m Pr-145 

Br-84 Nb-93m Rh-105m Sn-130 Cs-135 Ce-146 

Br-85 Y-94 Ru-105 Sb-130m Cs-136 Pr-146 

Kr-85 Y-95 Rh-105 I-130 Xe-l37 Ce-147 

Kr-85m Zr-95 Pd-107 Sb-131 Cs-137 Pr-147 

Rb-86 Nb-95 Rh-109 Te-l31 Ba-137m Nd-147 

Kr-87 Y-96 Pd-109 Te-131m Xe-138 Pm-147 

Rb-87 Zr-97 Ag-109m I-131 Cs-138 Pr-148 

Kr-88 Nb-97 Ag-110m Xe-131m Cs-139 Pm-148 

Rb-88 Nb-97m Ag-111 Sb-132 Ba-139 Pm-148m 

Kr-89 Nb-98m Cd-113m Sb-132m Cs-140 Pm-149 

Rb-89 Mo-99 Cd-115m Te-132 Ba-140 Pm-151 

Sr-89 Tc-99 Sn-123 I-132 La-140 Sm-151 

Rb-90 Tc-99m Sb-124 Sb-133 Ba-141 Eu-152 

Rb-90m Mo-10l Sn-125 Te-133 La-141 Sm-153 

Sr-90 Tc-101 Sb-125 Te-133m Ce-141 Eu-154 

Y-90 Mo-102 Te-125m I-133 Ba-142 Eu-155 

Rb-91 Tc-102 Sn-126 Xe-133 La-142 Eu-156 

Sr-91 Tc-103 Sb-126 Xe-133m La-143 Tb-160 

Y-91 Ru-103 Sb-127 Te-134 Ce-143 Ho-166m 

Y-91m Rh-103m Te-127 I-134 Pr-143 

Sr-92 Tc-104 Te-127m Cs-134 Ce-144 

Standard Decay Times (seconds) 

0.001 0.00215 0.00464 0.01 0.0215 0.0464 

0.1 0.215 0.464 1. 2.15 4.64 

10 21.5 46.4 100. 215 464 

1.00 × 103 2.15 × 103 4.64 × 103 1.00 × 104 2.15 × 104 4.64 × 104

1.00 × 105 2.15 × 105 4.64 × 105 1.00 × 106 2.15 × 106 4.64 × 106

1.00 × 107 2.15 × 107 4.64 × 107 1.00 × 108 2.15 × 108 4.64 × 108

1.00 × 109 2.15 × 109 4.64 × 109 1.00 × 1010

1 hour = 3600 sec 1 day = 86400 sec 1month = 2.59 × 106 7 sec 1 year = 3.15 × 10 sec 

* The FIIDOS database uses these 40 specific decay times for calculation of radionuclide 

inventories and spectra. Values for other decay times are obtained by one additional decay 

calculation from the nearest time. 

34
Actinides 

ORIGEN2-SAIC calculates the decayed inventory for 18 actinide radionuclides (see 

Table 5). These radionuclides are produced in a nuclear detonation or are remnant from 

the nuclear device. Data on the amount of each actinide radionuclide (Ci per kT) 

immediately after detonation are input by the user from radio-chemistry data (LLNL, ca. 

1970). FIIDOS calculates the amount of each actinide radionuclide present at the 

exposure time and the measurement time. The inventory is normalized to 1014 fissions to 

produce a relative radionuclide inventory of actinides. 

Table 4. Activation product radionuclides. 

 Be- 7 Co- 58 W-187 

 Na-24 Co- 60 W-188 

 Mn-54 Cu- 64 Au-198 

 Fe-55 Cu- 67 Au-199 

 Fe-59 W-181 Pb-203 

 Co-57 W-185 

Table 5. Actinide product radionuclides. 

 Th-229 U-237 Pu-238 

 Th-230 U-238 Pu-239 

 Th-234 U-240 Pu-240 

 U-233 Np-237 Pu-241 

 U-234 Np-239 Am-241 

 U-235 Np-240 Cm-242 

Table 6. Gaseous fission product radionuclides. 

 Kr-83 m Kr -89 Xe-135 m 

 Kr-85 Xe-131 m Xe-137 

 Kr-85 m Xe-133 Xe-138 

 Kr-87 Xe-133 m 

 Kr-88 Xe-135 

35
Inventory Modifications 

The fallout field produced by a nuclear weapon does not contain some of the fission 

products, such as noble gases, and the relative abundance of a specific radionuclide in the 

fallout field is not necessarily the same as that calculated by basic fission product buildup 

and depletion codes. FIIDOS provides a simple capability for the user to modify the 

fission product inventory to reflect these observations. 

One form of fission product inventory modification involves the removal of the 

radionuclides of the gaseous fission products krypton and xenon (see Table 6). If this 

option is selected, FIIDOS automatically modifies the relative radionuclide inventory to 

give zero amounts for the gaseous fission products. FIIDOS also maintains a record of 

the amount of each gaseous fission product radionuclide deleted from the inventory, in 

order to adjust the gamma-ray emission spectrum (discussed in Section 2.2.6.3). 

The second form of fission product inventory modification involves the adjustment of 

specific radionuclide inventories to reflect the effects of fission product fractionation. To 

implement this inventory modification option, the user must input a specific fractionation 

factor and gamma-ray emission data for each radionuclide affected. In FIIDOS, this 

factor is used as a multiplier to increase or decrease the amount of the radionuclide in the 

relative radionuclide inventory. FIIDOS maintains a record of the amount of each 

radionuclide removed from the inventory, so that the gamma-ray emission spectrum can 

be adjusted. 

2.2.6 Radiological Contamination Scaling Factor 

The parameter SF in Equation 2.20 is the radiological contamination scaling factor. The 

scaling factor is not a user-supplied input to FIIDOS. The factor is calculated within 

FIIDOS, and the units depend on the specified input options. 

For those options in which the level of contamination is specified in terms of activity (Ci) 

or activity concentration (Ci m-3 or Ci m-2), the scaling factor is calculated by: 

SF = Aing × (A )

 -1

T (2.33) 

SF = Ainh × (A )

 -1

T (2.34) 

SF = AC × (A )

 -1

T or (2.35) 

SF = SC × (A )

 -1

T (2.36) 

where: 

A = gross ingestion activity intake (Ci), ing

A = gross inhalation activity intake (Ci), inh

AC = gross airborne activity concentration (Ci m-3), 

-2 SC = gross surface activity concentration (Ci m ), 

36
and 

14 AT = total activity of relative radionuclide inventory (Ci per 10 fissions). 

14 14 The factor SF thus has units of 10 fissions, 10 fissions m-3 14 or 10 fissions m-2, 

depending on the option selected. 

For those options in which the level of contamination is specified in terms of radiation 

intensity (R hr-1), the scaling factor is calculated by: 

SF = Ica × (∑EST × ψ )

-1 (2.37) ca

SF = Ics × (∑EST × ψcs)

 -1 (2.38) 

SF = Is × (∑EST × ψs)

 -1 (2.39) 

where: 

 = radiation intensity aloft inside debris cloud (R hr-1 I ), ca

-1 Ics = radiation intensity at surface inside debris cloud (R hr ), 

Is = radiation intensity above contaminated surface (R hr-1), 

 = rate of emission of gamma rays of energy E from relative 

radionuclide inventory (γ hr

ST

-1 14 per 10 fissions), and 

ψca, ψcs, ψs = energy-dependent factors relating radiation intensity 

to a unit gamma ray volume, or surface, emission rate (R hr-1

per γ hr-1

 m-3 -1 or R hr per γ hr-1 m

-2), for the selected 

exposure situation. 

14 The factor SF has units of (10 fissions m-3 14 ) or (10 fissions m-2), depending on the 

option selected. 

The following sections discuss the quantities used in the calculation of the scaling factor 

SF. The user-supplied radiological measurement quantities are addressed in Section 

2.2.6.1. The approach used in FIIDOS to determine the total activity of the relative 

radionuclide inventory, AT, is described in Section 2.2.6.2. Section 2.2.6.3 addresses the 

FIIDOS procedures used to calculate the gamma-ray emission spectrum, ST. The methods 

used to calculate the gamma-ray exposure factors, ψca, ψcs, ψs are contained in FIIDOS 

are explained in Section 2.2.6.4. 

37
2.2.6.1 Radiological Measurement Quantities 

There are two basic types of radiological measurement quantities that are input by the 

user: gross (or isotope specific) activity or radiation intensity. 

A gross activity radiological measurement quantity may be an ingestion activity intake 

(Ci), an inhalation activity intake (Ci), an airborne activity concentration (Ci m-3), or a 

surface activity concentration (Ci m-2). When a gross activity quantity is used, the usersupplied input must include the measured value and the time after burst at which the 

measurement was made. An option in FIIDOS allows the user to input the activity of a 

one specific isotope of the complete inventory. The corresponding gross activity is then 

determined for input into FIIDOS. 

The other basic type of radiological measurement accommodated by FIIDOS is radiation 

intensity. When this type of radiological measurement is used, the user-supplied input 

data must include the measured value, the time at which the measurement was made, and 

identification parameters denoting the characteristics of the measurement device and the 

geometry of the measurement situation. 

In FIIDOS, two types of gamma-ray radiation measurement devices are considered: a 

non-specific RADIAC meter and a radiation film badge. For the RADIAC meter, it is 

assumed that the measured radiation intensity will be reported in terms of the intensity in 

air (R hr-1) or a free-in-air, tissue dose rate (rad hr-1). The film badge is assumed to use 

DuPont Type 502 film shielded by a lead-tin laminate. The reported film badge dose rate 

(rem hr-1) can be for either free-in-air or in-situ irradiation conditions, and should be an 

average value based on the total film badge dose recorded for the period of exposure to 

airborne contaminants. 

In FIIDOS, three geometric arrangements of the radiation intensity measurement 

situation are considered: the radiation measuring device may be above a contaminated 

surface, aloft inside a nuclear debris cloud, or at a near-surface position inside a nuclear 

debris cloud. More specific information on these geometries is provided in Section 

2.2.6.4. 

2.2.6.2 Total Activity of Relative Radionuclide Inventory 

The relative radionuclide inventory, and the procedures used in FIIDOS to construct the 

inventory, are discussed in Section 2.2.5. It is important to recognize that for the scaling 

factor calculation, the relative radionuclide inventory must be referenced to the time at 

which the radiological measurement was performed. Note that it may be necessary for 

FIIDOS to determine the relative radionuclide inventory at the radiological measurement 

time for use in the determination of the gamma-ray emission spectrum. As is discussed 

in Section 2.2.6.3, radionuclide-specific information is utilized where the gamma-ray 

emission spectrum requires modification to reflect activation products, actinide elements, 

or fractionated fission products. 

38
2.2.6.3 Gamma-ray Emission Spectrum 

The gamma-ray emission spectrum is the gamma-ray emission rate from a model sample 

of nuclear debris or fallout based on 1014 fissions. Since the gamma-ray emission 

spectrum is used in the calculation of a scaling factor keyed to a radiation intensity 

measurement, the spectrum is determined for the time at which the radiological 

measurement was performed. The spectrum is given in terms of an 18-energy group 

structure that spans a gamma-ray energy range from 0.010 MeV to 11.0 MeV. 

The gamma-ray emission spectrum is constructed when FIIDOS calls the ORIGEN2-

SAIC code. It includes the gamma rays from fission products, activation products, and 

actinide elements. If the FIIDOS user desires, the gamma-ray emission spectrum is 

modified to reflect fission product inventory adjustments due to gaseous fission product 

removal or fission product fractionation effects. The techniques used to construct the 

gamma-ray emission spectrum are described below. 

Fission Product Gamma Rays 

FIIDOS calls the ORIGEN2-SAIC code which calculates the gamma-ray emission 

spectra for fission products produced by the fission of U-235, U-238, and Pu-239 by fast 

and 14-MeV neutrons. The spectra are based on 1014 fissions with an instantaneous (i.e., 

1 msec) irradiation time. 

The spectral contribution from each fissionable material-neutron energy set is determined 

using the fission fraction of each set as was done for the relative radionuclide inventory. 

This spectral contribution is determined for the specified measurement time. The 

individual spectral contributions from 781 isotopes are summed within the ORIGEN2-

SAIC code to obtain the total gamma-ray emission spectrum from the fission products. 

Activation Product Gamma Rays 

ORIGEN2-SAIC calculates the gamma-ray emission data for any of 688 activation 

product radionuclides of which 17 are currently used in calculating organ dose in FIIDOS 

(see Table 4). The data are presented in the form of gamma rays per disintegration in the 

18-energy group structure. 

39
Actinide Element Gamma Rays 

In the same manner as described for the activation products, FIIDOS obtains, for the 

radionuclides given in Table 5, the gamma-ray emission spectrum contributed by the 

actinide elements. ORIGEN2-SAIC calculates the gamma-ray emission data for any of 

129 actinides, of which 18 are currently used in calculating organ dose in FIIDOS. 

Spectrum Modifications 

As is the case with the relative radionuclide inventory construction described in Section 

2.2.5, FIIDOS provides the capability to modify the gamma-ray emission spectrum to 

reflect the effects of gaseous fission product removal or fission product radionuclide 

fractionation. 

Based on prior calculations of the relative radionuclide inventory at the measurement 

time, information is available on the amount (Ci per 1014 fissions) of each gaseous fission 

product radionuclide and fractionated fission product radionuclide removed from the 

relative radionuclide inventory. 

Gamma-ray emission data, in the form of gamma rays per disintegration in the 18-energy 

group structure, are available in FIIDOS for specific gaseous fission product 

radionuclides (see Table 6). However, similar data for fractionated fission product 

radionuclides is not currently accessed in FIIDOS, but must be provided as user-supplied 

input in conjunction with the user-supplied radionuclide fractionation factors discussed in 

Section 2.2.5. 

By considering the amount of each radionuclide removed from the relative radionuclide 

inventory and the gamma-ray emission data for the radionuclide, FIIDOS determines the 

necessary gamma-ray emission spectrum modifications. 

The isotope fractionation method in FIIDOS is the same as in the original version of 

FIIDOS. However, because the complete inventory and gamma spectrum are being 

generated at all 40 time steps and can be accessed at any measurement time, future 

modifications are possible so as to use ORIGEN2-SAIC to fractionate the inventory. 

Gamma-ray Energy Group Structure 

At this point, it should be noted that the 18-energy group structure used for the gammaray emission spectrum does not exactly match the energy group structure that is used for 

the gamma-ray exposure factor discussed in Section 2.2.6.4. Since the FIIDOS 

methodology uses the product of the gamma-ray emission spectrum and the gamma-ray 

exposure factor, the energy group structure of the emission spectrum is modified to make 

the two energy group structures compatible. 

As seen in Table 7, the first 15 gamma-ray spectrum energy groups from ORIGEN match 

40
the last 15 exposure factor energy groups from radiation transport cross section of DLC31 (Bartine, 1977); however, the 16th gamma-ray spectrum energy group (4.0 - 6.0 MeV) 

encompasses both the 5th th (5.0 - 6.0 MeV) and the 6 (4.0 - 5.0 MeV) exposure factor 

energy groups. To accommodate this mismatch, the 16th gamma-ray spectrum energy 

group is subdivided into two groups with 55% of the gamma ray emission rate assigned 

to a 4.0 - 5.0 MeV energy group and 45% of the emission rate assigned to a 5.0 - 6.0 

MeV energy group. This 55% - 45% gamma ray emission rate allocation results in a 50% 

- 50% energy emission rate allocation to each of the two groups. Table 7 also shows that 

the energy group structures mismatch for the last two gamma-ray spectrum energy 

groups and the first four exposure factor energy groups. However, these mismatches are 

not important, since the nuclear debris or fallout does not emit any high energy gamma 

rays associated with the 17th th and 18 gamma-ray spectrum energy groups. 

2.2.6.4 Gamma-ray Exposure Factor 

The gamma-ray exposure factor (R hr-1, rad hr-1, rem hr-1 per γ sec-1

 m

-2 -1

 or γ sec m-3) is 

the exposure rate resulting from a unit gamma-ray surface, or volume, emission rate. The 

factor is in terms of a 21-energy group structure that spans a gamma-ray energy range 

from 0.01 MeV to 14.0 MeV. The gamma-ray exposure factor is dependent upon the 

characteristics of the radiation measurement device and the geometry of the radiation 

measurement situation. 

The radiation measurement devices considered include a non-specific radical meter that 

measures either intensity in air (R hr-1) or tissue dose rate (rad hr-1), and a radiation film 

badge that provides a dose rate (rem hr-1) value based on a measured dose and exposure 

duration. The gamma-ray response functions for these devices are shown in Table 8. For 

air, the conversion from gamma-ray fluence (γ sec

-1) to radiation intensity (R hr-1) is 

based on the ICRU recommendations in NBS Handbook 85 (NBS, 1964), restructured to 

a 21-energy group structure. Tissue is as represented by elements of a man-phantom 

described by Snyder (1974). The film badge response is for DuPont Type 502 film 

shielded by a lead-tin laminate, with the approximation of normally incident radiation 

(DNA, 1979a). 

The radiation measurement situations considered include radiation intensity above a 

contaminated surface, radiation intensity aloft inside a debris cloud, and radiation 

intensity at the surface inside a debris cloud. The methodology used to calculate the 

gamma-ray exposure factor for each of these measurement situations is described below. 

41
Table 7. Gamma-ray energy group structures.

 ORIGEN2 DLC-31 

Group Energy Range (MeV) Group Energy Range (MeV)

1 0.010-0.020 21 0.010-0.020 

2 0.020-0.030 20 0.020-0.030 

3 0.030-0.045 19 0.030-0.045 

4 0.045-0.070 18 0.045-0.070 

5 0.070-0.100 17 0.070-0.100 

6 0.100-0.150 16 0.100-0.150 

7 0.150-0.300 15 0.150-0.300 

8 0.300-0.450 14 0.300-0.450 

9 0.450-0.700 13 0.450-0.700 

10 0.700-1.000 12 0.700-1.000 

11 1.000-1.500 11 1.000-1.500 

12 1.500-2.000 10 1.500-2.000 

13 2.000-2.500 9 2.000-2.500 

14 2.500-3.000 8 2.500-3.000 

15 3.000-4.000 7 3.000-4.000 

16 4.000-6.000 6 4.000-5.000 

17 6.000-8.000 5 5.000-6.000 

18 8.000-11.00 4 6.000-7.000 

 3 7.000-8.000 

 2 8.000-10.000 

 1 10.000-14.000 

42
Table 8. Gamma-ray response functions. 

Energy Range (MeV) Tissue(1) Air(2) Film Badge(3) 

(rad per γ cm

-2) (R per γ cm-2) (rem per γ cm-2)

-10 -10 0.010 - 0.020 4.378 × 10 4.320 × 10 0.000 

-10 -10 0.020 - 0.030 1.359 × 10 1.340 × 10 0.000 

-11 -11 -14 0.030 - 0.045 6.166 × 10 5.850 × 10 7.908 × 10

-11 -11 -12 0.045 - 0.070 3.615 × 10 3.580 × 10 3.310 × 10

-11 -11 -11 0.070 - 0.100 3.766 × 10 3.690 × 10 2.284 × 10 

-11 -11 -11 0.100 - 0.150 5.352 × 10 5.560 × 10 3.919 × 10

-10 -10 -11 0.150 - 0.300 1.085 × 10 1.130 × 10 9.827 × 10

-10 -10 -10 0.300 - 0.450 1.931 × 10 2.010 × 10 1.821 × 10

-10 -10 -10 0.450 - 0.700 2.979 × 10 3.110 × 10 2.850 × 10

-10 -10 -10 0.700 - 1.000 4.262 × 10 4.410 × 10 4.111 × 10

-10 -10 -10 1.000 - 1.500 5.839 × 10 6.020 × 10 5.887 × 10

-10 -10 -10 1.500 - 2.000 7.498 × 10 7.750 × 10 7.826 × 10

-10 -10 -10 2.000 - 2.500 8.933 × 10 9.280 × 10 9.317 × 10

-9 -9 -9 2.500 - 3.000 1.023 × 10 1.050 × 10 1.065 × 10

-9 -9 -9 3.000 - 4.000 1.202 × 10 1.240 × 10 1.253 × 10

-9 -9 -9 4.000 - 5.000 1.423 × 10 1.470 × 10 1.488 × 10

-9 -9 -9 5.000 - 6.000 1.630 × 10 1.690 × 10 1.709 × 10

-9 -9 -9 6.000 - 7.000 1.829 × 10 1.920 × 10 1.942 × 10

-9 -9 -9 7.000 - 8.000 2.028 × 10 2.100 × 10 2.114 × 10

-9 -9 -9 8.000 - 10.000 2.338 × 10 2.440 × 10 2.458 × 10

-9 -9 -9 10.000 - 14.000 2.949 × 10 3.060 × 10 3.088 × 10

(1) MIRD (Snyder) Phantom (Snyder, 1974). 

(2) ICRU recommended values restructured to 21-energy group structure (NBS, 1964). 

(3) DuPont Type 502 film shielding by a tin-lead laminate (DNA, 1979a). 

Radiation Intensity Above a Contaminated Surface 

The source term for this gamma-ray exposure factor calculation is a soil slab of infinite 

lateral dimensions, having a thickness of 1 meter. The soil is represented by Area 7 

Nevada Test Site soil, described in Table 9 (DNA, 1979b). The radioactive material 

within the soil slab is modeled as two planar sources of equal source strength, one at a 

depth of 0.25 cm and the other at a depth of 0.75 cm. This depth distribution is not meant 

to indicate the actual distribution of radioactivity in the soil, but is simply a mechanism 

used to account for the shielding effect of ground roughness. As shown in Figure 9 

(Glasstone, 1977), this modeling gives a ground roughness factor that compares 

favorably with the value of 0.7, commonly mentioned in the fallout literature. The 

43
gamma-ray exposure factor for the RADIAC meter is given for a free-in-air, unshielded 

condition. The meter is assumed to be located at a height of one meter above the 

contaminated surface. 

The gamma-ray exposure factor for the film badge is given for both free-in-air and in-situ 

conditions. In the free-in-air condition, no consideration is given to the partial shielding 

of the film badge by the human body. For the in-situ conditions, the human body is 

represented by a man phantom model, and the film badge is taken to be a point on the 

chest of the model, see Figure 10 (Kaul, 1977). The shielding effectiveness of the body 

depends upon the geometric characterization of the irradiation as affected by the 

orientation of the body and the characteristics of the radiation. The calculated 

distribution of a representative fallout field radiation environment is shown in Figure 11. 

A badged individual passing through the field, walking erect, would thus be exposed 

primarily in his polar midplane to azimuthally isotropic radiation. On the other hand, an 

individual assuming random orientations while in the field, perhaps by reason of some 

assigned task, would be exposed in a more generally isotropic fashion. Therefore, 

FIIDOS includes separate film badge exposure factors for these two situations, calculated 

on the basis of azimuthally isotropic, polar midplane exposure in the case of a standing 

individual and on the basis of isotropic exposure for a man assuming various random 

orientations while in the fallout field. The body provides more effective shielding of the 

film badge for conditions of isotropic exposure than that in the midplane. Therefore, the 

film badge gamma-ray exposure factors for in-situ (isotropic) irradiation are less than the 

factors for in-situ (midplane) irradiation. Leaving aside the differences between isotropic 

or midplane irradiation, the ratio of in-situ dose to free-in-air dose ranges from 0.5 for 

low energy gamma rays to 0.9 for high energy gamma rays; for a typical fallout radiation 

gamma-ray spectrum, the ratio is approximately 0.7. Thus, the overall efficiency in 

transmission of gamma-ray emissions from fallout to a in-situ film badge, considering 

both body shielding and ground roughness, is approximately 0.5. 

44
Table 9. Elemental composition of Nevada Test Site* soil. 

 

Element Weight Percent Element Weight Percent

H(organic) 0.50 P 0.02 

H(water) 0.66 S 0.03 

C 0.90 Cl 0.08 

N 0.01 K 1.92 

O 50.85 Ca 6.72 

Na 0.79 Ti 0.13 

Mg 2.04 Mn 0.071 

Al 7.61 Fe 1.5 

Si 25.03 Other 1.14 

 * As represented by Area 7 (DNA, 1979b). 

Figure 9. Equivalent ground roughness for soil source. 

45
Approximate Film Badge Location

(0.09 cm from surface of chest,

20 cm down from top of torso,

and 10 cm from midline)

Figure 10. Man phantom model. 

46
Incident radiation

Basis

• Air exposure at 1 meter above surface

• Unfractionated U-235 fission products

• Two hour decay

Fraction of total intensity

0.05

0.10

0.15

0.20

0.25

0.30

Horizontal plane

@ 1 meter above ground

__ __ __ __ __ __

Incident radiation

Basis

• Air exposure at 1 meter above surface

• Unfractionated U-235 fission products

• Two hour decay

Fraction of total intensity

0.05

0.10

0.15

0.20

0.25

0.30

Horizontal plane

@ 1 meter above ground

__ __ __ __ __ __

Figure 11. Angular contribution of fallout intensity. 

The radiation transport calculations of the gamma-ray exposure factors were performed 

using the code ANISN (Engle, 1973). The calculations were performed for the 21-

energy group structure shown earlier in Table 7. The atmosphere was modeled as lowhumidity air at the NTS elevation based on meteorological data typical of Operation 

TEAPOT (NDL, 1965). That the film badge response uses the approximation of 

normally incident radiation principally affects the small exposure factors at low energies 

(which contribute minimally to dose from a fallout field). The comparison among film 

badge orientations of the exposure factors at such energies is not meaningful. 

Table 10 provides the gamma-ray exposure factor for radiation intensity above a contaminated surface. 

47
Radiation Intensity Aloft Inside Debris Cloud 

This gamma-ray exposure factor is calculated using an adaptation of the method given in 

Meteorology and Atomic Energy (Slade, 1968). It is assumed that the debris cloud is 

effectively infinite in extent; i.e. of uniform contamination density throughout the range 

of gamma-ray radiation. The gamma-ray exposure factor given in Table 11 is for a 

radical meter that measures intensity in air (R hr-1), unshielded, within a debris cloud. 

Radiation Intensity at Surface Inside Debris Cloud 

This gamma-ray exposure factor is determined using the same procedures cited above for 

radiation intensity inside a debris cloud, except that the bottom half of the cloud is 

assumed to be replaced by the ground. Accordingly, the gamma-ray exposure factor for 

the radiation intensity below the cloud is one-half of the exposure factor inside the cloud. 

2.3 LIMITATIONS OF TECHNICAL APPROACH 

FIIDOS is designed to provide a tool for calculating the radiation dose to various body 

organs that would result from the ingestion or inhalation of nuclear weapon fallout. 

While FIIDOS is intended for use in the assessment of radiation exposure of military 

personnel from atmospheric nuclear detonations, its calculation flexibility facilitates 

additional applications. The technical approach adopted for FIIDOS is adequate for the 

purposes of its intended application; however, there are limitations of the technical 

approach that should be identified to avoid a misuse of FIIDOS or a misunderstanding of 

FIIDOS results. The limitations encompass both the methodology and the data used in 

FIIDOS. 

Three aspects of the methodology impose limitations on the application of FIIDOS. All 

three relate to the use of a radiological measurement to characterize a radiological 

environment. First, it must be recognized that the radiological measurement quantifies 

the radioactive contamination at a specific location. The radiological environment that 

FIIDOS calculates is referenced to this same location. FIIDOS does not provide a 

mechanism for translating a radiological measurement at one location to another location. 

Second, when a radiological measurement at one time is used to determine the 

radiological environment at a different time, the only effect that FIIDOS considers is 

radioactive decay. Decontamination and other effects that alter the distribution of the 

radioactive material, such as wind and rain, are not included in the FIIDOS methodology. 

Third, the association of the radiological hazard with the radiological measurement is 

valid only as long as the fallout debris emits sufficient gamma-ray radiation to give 

meaningful measurements. This condition exists in a fresh fallout field and continues for 

several years; however, after some time, the fallout radiation level will become 

indistinguishable from the prevailing background radiation level. At these late times, the 

fallout material could still contain some radionuclides that contribute significantly to an 

48
internal dose, even though the gamma-ray radiation emission rate from the fallout 

material is low. 

Table 10. Gamma-ray exposure factor for surface contamination. 

Gamma-ray Exposure Factor (units as measured per γ hr-1 cm-2)

Film Badge (Sn-Pb Shielded Type 502)

Energy 

Range 

Tissue 

Free-In-Air

Air 

Free-In-Air Free-In-Air

In-Situ 

(Midplane) 

In-Situ 

(Isotropic) 

Group (MeV) (rad hr-1) (R hr-1) (rem hr-1) (rem hr-1) (rem hr-1)

1 10.0-14.0 5.75 × 10-9 5.96 × 10-9 5.99 × 10-9 5.41 × 10-9 5.05 × 10-9

2 8.0-10.0 4.57 × 10-9 4.77 × 10-9 4.78 × 10-9 3.93 × 10-9 3.88 × 10-9

3 7.0-8.0 3.97 × 10-9 4.11 × 10-9 4.11 × 10-9 4.08 × 10-9 3.63 × 10-9

4 6.0-7.0 3.57 × 10-9 3.74 × 10-9 3.76 × 10-9 3.27 × 10-9 3.23 × 10-9

5 5.0-6.0 3.17 × 10-9 3.29 × 10-9 3.30 × 10-9 2.77 × 10-9 2.65 × 10-9

6 4.0-5.0 2.75 × 10-9 2.84 × 10-9 2.85 × 10-9 2.12 × 10-9 2.27 × 10-9

7 3.0-4.0 2.30 × 10-9 2.37 × 10-9 2.37 × 10-9 2.07 × 10-9 1.91 × 10-9

8 2.5-3.0 1.93 × 10-9 1.98 × 10-9 1.98 × 10-9 1.65 × 10-9 1.62 × 10-9

9 2.0-2.5 1.66 × 10-9 1.73 × 10-9 1.71 × 10-9 1.58 × 10-9 1.40 × 10-9

10 1.5-2.0 1.38 × 10-9 1.42 × 10-9 1.41 × 10-9 1.17 × 10-9 1.10 × 10-9

11 1.0-1.5 1.06 × 10-9 1.09 × 10-9 1.04 × 10-9 8.91 × 10-10 8.31 × 10-10

12 0.7-1.0 7.66 × 10-10 7.93 × 10-10 7.20 × 10-10 5.64 × 10-10 5.36 × 10-10

13 .45-.70 5.46 × 10-10 5.68 × 10-10 5.01 × 10-10 4.21 × 10-10 4.04 × 10-10

14 .30-.45 3.69 × 10-10 3.83 × 10-10 3.21 × 10-10 2.63 × 10-10 2.61 × 10-10

15 .15-.30 2.22 × 10-10 2.29 × 10-10 1.80 × 10-10 1.54 × 10-10 1.48 × 10-10

16 .10-.15 1.12 × 10-10 1.14 × 10-10 6.65 × 10-11 6.32 × 10-11 5.88 × 10-11

17 .07-.10 7.52 × 10-11 7.37 × 10-11 3.07 × 10-11 2.91 × 10-11 2.57 × 10-11

18 .045-.070 5.43 × 10-11 5.33 × 10-11 3.94 × 10-12 3.58 × 10-12 3.14 × 10-12

19 .030-.045 4.10 × 10-11 3.90 × 10-11 4.75 × 10-14 2.96 × 10-14 3.23 × 10-14

20 .020-.030 2.64 × 10-11 2.61 × 10-11 0 0 0 

21 .010-.020 9.94 × 10-12 9.80 × 10-12 0 0 0 

49
Table 11. Gamma-ray exposure factor for airborne contamination. 

 Free Air 

 Gamma-ray Energy Range Gamma-ray Exposure Factor

 Group (MeV) (R hr-1 per γ hr-1 m-3)

1 10.0-14.0 1.69 × 10-10

2 8.0-10.0 1.27 × 10-10

3 7.0-8.0 1.06 × 10-10

4 6.0-7.0 9.14 × 10-11

5 5.0-6.0 7.73 × 10-11

6 4.0-5.0 6.33 × 10-11

7 3.0-4.0 4.92 × 10-11

8 2.5-3.0 3.87 × 10-11

9 2.0-2.5 3.16 × 10-11

10 1.5-2.0 2.46 × 10-11

11 1.0-1.5 1.76 × 10-11

12 0.7-1.0 1.20 × 10-11

13 0.45-0.70 8.09 × 10-12

14 0.30-0.45 7.38 × 10-12

15 0.15-0.30 3.12 × 10-12

16 0.10-0.15 1.76 × 10-12

17 0.07-0.10 1.20 × 10-12

18 0.045-0.070 8.16 × 10-13

19 0.030-0.045 5.34 × 10-13

20 0.020-0.030 3.52 × 10-13

21 0.010-0.020 2.11 × 10-13

50
Limitations on the accuracy of FIIDOS-calculated organ doses arise from data internal to 

FIIDOS and user-supplied input data. One major limitation of the original FIIDOS code 

was that the ORIGEN2 database lacked many early gamma rays, especially before 5 

minutes. The ORIGEN2-SAIC calculated gamma-ray spectra are very accurate, even to 

early times, as was demonstrated by the excellent agreement with measurements and 

other calculations (Roberts, 1996). 

The ORIGEN2-SAIC code calculates up to 1600 total isotopes in the inventory. FIIDOS 

currently uses only 148 of the 781 fission product radionuclides available from 

ORIGEN2-SAIC for determining internal dose. Most of the other isotopes make a 

negligible contribution to internal dose because they decay before the earliest fallout 

deposition times. 

Dose conversion factors for short-lived radionuclides are low values, especially for 

organs outside the organ of uptake. Most radionuclides lacking dose conversion factors 

have half-lives of a few minutes or less. In this early period, distribution of radionuclides 

to other organs is limited. The shorter-lived radionuclides included in Appendix A, 

Tables A-1 and A-2 clearly demonstrate these effects. 

The upper limit of the organ dose at early times has been crudely estimated by assuming 

the radionuclides lacking dose conversion factors in FIIDOS have a dose conversion 

factor similar to the rest of the inventory. The potential upper limit of the organ dose was 

then 41 percent more if inhaled at 3 minutes, 7 percent more at 9 minutes, and 4 percent 

more at 30 minutes than obtained by FIIDOS. 

The original version of FIIDOS was based on ORIGEN2 calculations with a very 

incomplete gamma-ray spectra database from only 180 isotopes. With FIIDOS, the timedependent gamma-ray emission spectrum of the weapon debris is determined from 

spectra calculated by ORIGEN2-SAIC. The ORIGEN2-SAIC database contains spectral 

information on 781 fission-product radionuclides. 

The 148 fission products radionuclides in the FIIDOS inventory include most fissionproduct nuclides of biological significance beyond the first minutes of decay. The 

FIIDOS code can easily be expanded to include dose from the other isotopes calculated 

by ORIGEN2-SAIC to accommodate more dose coefficients. 

The choice of 18 actinides appears to introduce some problems when in much degraded 

fallout fields. The daughters and granddaughters of these 18 isotopes can contribute 

doses comparable to the parent’s dose. Because the daughters are not included in the 

FIIDOS inventory, their dose will be unaccounted. 

51
SECTION 3 

 COMPUTER PROGRAM 

3.1 INTRODUCTION 

The computer program FIIDOS is written in FORTRAN primarily for operation on an 

IBM-compatible PC running Windows (95-XP), but could easily be recompiled for use 

on a UNIX workstation or an Apple Macintosh computer. A typical FIIDOS problem 

has a running time of about 1 second, with more complicated problems being completed 

in less than 5 seconds. 

FIIDOS consists of a main program, eighteen subroutines and the code ORIGEN2-SAIC 

with its subroutines. FIIDOS uses a data library that has several files containing 

problem-independent data. User input provides problem-dependent data and program 

control instructions. Program output occurs in sequential fashion from the main program 

and selected subroutines. 

The equations and operations of the computer code FIIDOS are discussed in Section 3.2. 

The main program and subroutines, data library, user input, and program output for 

FIIDOS are discussed in Sections 3.3, 3.4, 3.5, and 3.6, respectively. FORTRAN listing 

of the main program and subroutines is provided in Appendix B. 

3.2 EQUATIONS AND OPERATIONS 

The equations used in FIIDOS for calculating the committed organ dose resulting from 

the intake of a radionuclide are computerized versions of Equations 2.20 through 2.27 

given in Section 2. The computer equations and their parameters are given in Figure 12. 

Figure 13 illustrates, in a simplified manner, the concept of the computer code FIIDOS. 

The relationship of the FIIDOS data library and processing to the user-supplied inputs is 

shown. 

The actual sequence of operations used by the computer code FIIDOS is shown in Figure 

14. Each element of the flow diagram is numbered to facilitate subsequent discussion of 

the program. 

As seen in Figure 14, the first five elements of the flow diagram are concerned with the 

input data handling and some preliminary calculations. The procedure to calculate the 

radiological contamination scaling factor is reflected by elements 6 through 11. The path 

followed from element 6 to 11 depends upon whether the radiological measurement is of 

gross activity or radiation intensity, with or without modifications to the gamma-ray 

emission spectrum to reflect activation products, actinide elements, or fractionated fission 

products. The procedure to calculate the relative radionuclide inventory at the time of 

exposure is reflected in element 12. The calculation of the organ dose occurs at element 

13. At that point, the program flow branches. If integrated (chronic) doses are to be 

52
calculated, a loop is entered (elements 15 to 18) which calculates the relative radionuclide 

inventory at each standard time after the start of the exposure and up to the end of the 

exposure period. The resulting dose increments from exposure to those inventories are 

summed to produce a total dose. The integrated exposure branch is rejoined by the acute 

exposure branch at element 19 and, if requested, the intermediate results are written to the 

output file. If the calculation is complete (no additional exposures), then the program 

ends and the final output is written. Otherwise, the program flow returns to element 6 as 

many times as required. 

3.3 MAIN PROGRAM AND SUBROUTINES 

FIIDOS consists of a main program, eighteen subroutines and the code ORIGEN2-SAIC. 

Figure 15 shows the basic organization and hierarchy of FIIDOS. The main program 

controls the execution of FIIDOS. The actual problem calculations are performed by the 

subroutines. Each routine is briefly described below. 

Program MAIN is the control module for FIIDOS. The basic flow of program MAIN is 

shown in Figure 14. As seen in the figure, program MAIN consists primarily of 

decisions for branching and calls for subroutines. Program variables appearing in the 

diagram are discussed in Section 3.5 as follows: ITRM--Item 6; and ITPM--Item 2. 

Subroutine INPUT obtains the input data provided by the FIIDOS user. A discussion of 

the user input data is given in Section 3.5. 

Subroutine FISFRC converts the weapon yield data provided by the user in units of 

kilotons into the relative number of fissions for each fissionable material-neutron energy 

set. The fissionable materials considered include U-235, U-238, and Pu-239; the neutron 

energies considered include fast neutrons and 14-MeV neutrons. 

Subroutine ORGSRC prepares the input for the ORIGEN2-SAIC code. 

Subroutine RRI calculates the relative radionuclide inventory of a mixture of 

radionuclides at a specified time of concern, which can be either the measurement time or 

the exposure time. Subroutine RRI itself is a control module; as shown in Figure 15, 

subroutine RRI has five subordinate modules that perform the inventory-related 

calculations. 

Subroutine GFPI accepts the relative radionuclide inventory of fission products 

calculated by ORIGEN2-SAIC. 

Subroutine KRXERI determines the amount of each krypton and xenon radionuclide 

removed from the relative radionuclide inventory of fission products, if required. 

53
D(I,J) = DUR × BR × AKFAC × DCF(I,J) × AFP(I) × SF × 106

 (3.1) 

with, 

SF = ACTMES × (ACTOT)

-1 (3.2) 

or 

SF = RIMES × (∑E SPEC × GREF)

 -1 (3.3) 

where: 

D(I,J) = dose commitment (rem) to organ J from radionuclide I, 

DUR = duration of exposure (hr), 

BR = breathing rate (m3

 hr-1), 

AKFAC = airborne activity-surface activity ratio (Ci m-3 per Ci m-2), or 

resuspension factor (m-1), 

DCF(I,J) = dose conversion factor (rem μCi-1) for the dose to organ J resulting 

from the ingestion or inhalation of radionuclide I, and 

AFP(I) = amount of radionuclide I (Ci per 1014 fissions) in the relative 

radionuclide inventory of the nuclear debris (note that AFP pertains to 

fission products. 

Similar parameters are defined for activation products and actinide elements), 

SF = radiological contamination scaling factor (1014 fissions, 1014 fissions m-2, 

or 1014 fissions m-3), 

ACTMES = measured gross activity intake (Ci), surface concentration (Ci m-2) 

or airborne concentration (Ci m-3), 

ACTTOT = total activity of relative radionuclide inventory (Ci per 1014

fissions), 

RIMES = measured radiation intensity (R hr-1) above contaminated surface, at 

surface inside debris cloud, or aloft inside debris cloud, 

SPEC = rate of emission of gamma-rays of energy E from relative radionuclide 

inventory (γ hr-1 per 1014 fissions), and 

GREF = energy-dependent factor of energy E, relating radiation intensity 

(R hr-1) to gamma-ray emission rate from contaminated surface 

(γ hr-1

 m

-2) or debris cloud (γ hr-1

 m-3). 

Figure 12. Dose equations for computer calculations. 

54
Radionuclide Inventory

and Spectrum for

Each Fission Type

(Also for Actinides & 

Activation Products)

calculated with -ORIGEN

Concept of FIIDOS

Surface 

Concentration

(at exposure time)

Specific Gamma Radiation

Emission Spectrum

(at measurement time)

Weapon & Fallout

Information

Specific Radionuclide

Inventor

(at measurement time)

Radiologica

Measurements

Committed Organ Dose

Equivalent Dose

Resuspension

Facto

Exposur

Duratio

Breathin

Rat

Dose Conversion Factors

(inhalation & ingestion)

Gamma 

Exposure Factors

Specifi

Detector Rate

Bioassay 

Concentration in Urine

Intake Excretion Functions

Jone

(inhalation & ingestion)

Normalization

Facto

Activity Intake

FIIDO

Components which were modified are shaded

Figure 13. Concept of FIIDOS. 

55
1. Start of program MAIN. 

2. Subroutine INPUT reads the input data provided by 

the user. 

3. Subroutine FISFRC converts the weapon yield in KT 

into relative number of fissions for each fissionable 

material-neutron energy set. 

4. Subroutine ORGSRC converts user input into 

ORIGEN2-SAIC input. 

5. Subroutine ORIGEN2-SAIC combines inventories and 

decays them to times of interest. 

6. Connector shows point in MAIN where problem is 

reentered for multiple measurement/exposure pairs. 

7. Subroutine RRI calculates the relative radionuclide 

inventory at the time of measurement for the purposes 

of 1) modifying the relative gamma emission spectrum 

and 2) providing the necessary inventory information 

to calculate the scaling factor. 

8. Decision for branching based on whether radiological 

measurement is gross activity or radiation intensity. 

9. Subroutine RGES calculates the relative gamma 

emission spectrum used to generate the scaling factor 

(only for intensity-based measurements). 

10. Connector shows point where branches rejoin the 

program flow. 

11. Subroutine SFCALC calculates the scaling factor 

based on the measured radiological quantity. 

12. Subroutine RRI calculates the relative radionuclide 

inventory at the time of exposure. 

13. Subroutine DOSE calculates the inhalation and 

ingestion dose to organs and the Pu-239 excretion. 

14. Decision for branching based on integrated (chronic) 

versus acute exposures. 

15. Connector shows reentry point in program flow for 

integrated exposures. 

16. Subroutine RRI calculates the relative radionuclide 

inventory for each intermediate time of exposure and 

at the end of the exposure. 

17. Subroutine DOSE calculates each increment of 

internal dose and Pu-239 excretion for integrated 

exposures. 

18. Decision for branching based on completion of the 

integrated dose calculation. 

19. Connector shows point where the acute and integrated 

exposure branches rejoin after the total dose is 

calculated for a single measurement/exposure pair. 

20. Subroutine OUTPUTF prints the intermediate results 

of each measurement/exposure pair (if requested). 

21. Decision for branching based on completion of 

calculations of dose for all measurement/exposure 

pairs. 

22. Subroutine OUTPUTF prints the final total internal 

doses and the total Pu-239 excretions from all 

exposures. 

23. End of program. 

CALL INPUT

CALL FISFRC

NO

CALL 

ORGSRC

1

2

3

4

5

6

7

8

13

CALL RRI

YES

CALL 

ORIGEN2-SAIC

12

14

START

ITRM>3 

CALL RGES

CALL 

SFCALC

CALL RRI

CALL DOSE

ITPM=2 

NO

YES

CALL RRI

CALL DOSE

DONE NO

YES

CALL OUTPUTF

DONE 

YES

NO

CALL OUTPUTF

END

9

10

11

15

16

17

18

19

20

21

22

23

Figure 14. Relationship of principal subroutines. 

56
MAIN

INPUT

FISFRC

ORGSRC

RRI

RGES

DOSE

OUTPUT

GFPG

KRXERG

ACTPG

GFPI

KRXERI

ACTPI

ACTINI

ACTING FRACI

FRACG

MAIN

INPUT

FISFRC

ORGSRC

RRI

RGES

SFCALC

DOSE

OUTPUTF

GFPG

ACTPG

GFPI

KRXERI

ACTPI

ACTINI

ACTING FRACI

FRACG

ORIGEN2-SAIC

Figure 15. Organization and hierarchy of FIIDOS. 

57
Subroutine ACTPI accepts the relative radionuclide inventory of activation products 

calculated by ORIGEN2-SAIC, if required. 

Subroutine ACTINI accepts the relative radionuclide inventory of actinide elements 

products calculated by ORIGEN2-SAIC, if required. 

Subroutine FRACI is used to calculate the change in the relative radionuclide inventory 

of fission products resulting from fractionation, if required. This calculation uses 

radionuclide-specific fractionation factors provided by the user and radionuclide 

inventory data produced by subroutine GFPI. 

Subroutine RGES calculates the relative gamma-ray emission spectrum of a mixture of 

radionuclides at the measurement time, if required. Subroutine RGES itself is primarily a 

control module; as shown in Figure 15, subroutine RGES has five subordinate modules 

that perform the spectrum-related calculations. 

Subroutine GFPG accepts the relative gamma-ray emission spectrum from the fission 

product radionuclides, calculated by ORIGEN2-SAIC, considering the contribution from 

each fissionable material-neutron energy set. 

Subroutine KRXERG determines the relative gamma-ray emission spectrum contributed 

by the krypton and xenon radionuclides removed from the fission product inventory, if 

required. This calculation uses gamma-ray emission spectral data contained in a data file 

and radionuclide inventory data produced by subroutine KRXERI. 

Subroutine ACTPG accepts the relative gamma-ray emission spectrum contributed by the 

activation products, calculated by ORIGEN2-SAIC, if required. 

Subroutine ACTING accepts the relative gamma-ray emission spectrum contributed by 

the actinide elements calculated by ORIGEN2-SAIC, if required. 

Subroutine FRACG is used to calculate the change in the relative gamma-ray emission 

spectrum of fission products resulting from fractionation, if required. This calculation 

uses gamma-ray emission spectral data provided by the user and radionuclide inventory 

data produced by subroutine FRACI. 

Subroutine SFCALC calculates the radiological contamination scaling factor based on the 

radiological measurement data provided by the user. As appropriate, this scaling factor is 

the intake, airborne concentration, or surface concentration of the radioactive material. 

Subroutine DOSE calculates the radiation dose to each organ contributed by each 

radionuclide and performs the plutonium excretion calculations, if requested. 

Subroutine OUTPUTF provides the calculated doses and other elements of calculation 

data. A discussion of the program output is in Section 3.6. 

58
Subroutine ORIGEN2-SAIC is called by the main routine to calculate inventory and 

spectra at times of interest. More information on this code is available (Croff, 1980; 

Roberts, 1996). 

3.4 DATA LIBRARY 

FIIDOS makes extensive use of files stored in a data library to provide problemindependent input data. Table 12 identifies the FIIDOS data library files. FIIDOS causes 

ORIGEN2-SAIC to calculate the decay inventory and spectra at 40 basic times after 

detonation. The 40 times are given in Table 13. 

The gamma-ray emission spectra are calculated for 18 energy groups by ORIGEN2-

SAIC. The gamma-ray release rate is expressed in terms of gamma-rays per second and 

is based on 1014 fissions. Table 14 provides the 18 gamma-ray energy groups. The files 

KRXE.GAM, contain gamma-ray emission spectra for krypton and xenon radionuclides. 

The spectra are expressed in gamma rays per disintegration and are provided in the 18-

energy group structure given above. 

The files GREF.SUR, GREF.INC, and GREF.BLC contain the gamma-ray exposure 

factor for radiation intensity above a contaminated surface, inside a debris cloud, and at 

the surface below a debris cloud, respectively. In the file GREF.SUR the factors are 

given in units of rad hr-1, R hr-1, or rem hr-1 per γ hr-1

 cm

-2 and factors are provided for 

several detector-orientation combinations. In the files GREF.INC and GREF.BLC the 

factors are given in units of R hr-1 per γ hr-1

 cm

-2 and factors are provided for a single 

detector-orientation combination. The factors are represented in the 21-energy group 

structure given in Table 15. 

The files INH.DCF and ING.DCF contain the ingestion and inhalation dose conversion 

factors. The factors are given in units of rem μCi-1. 

3.5 INPUT DESCRIPTION 

The user-supplied, problem-dependent input data required by the computer code FIIDOS 

is identified in Table 16. A discussion of this input data, keyed to the entries in Table 16, 

is provided below. 

3.6 OUTPUT DESCRIPTION 

The computer code FIIDOS has two basic types of output: standard and optional. 

Standard output, which provides the basic dose results of a FIIDOS calculation, occurs 

automatically and is not under any form of user control. Optional output, which provides 

supplemental information on the details of the FIIDOS calculations, is permitted or 

suppressed by user-specified control parameters. 

59
Table 12. FIIDOS data library. 

FIIDOS data files 

Unit Number File Name File Contents

 1 fiidos.out FIIDOS output 

 2 inh.dcf Inhalation Dose Conversion Factors (ICRP-72) 

 2 ing.dcf Ingestion Dose Conversion Factors (ICRP-72) 

 2 input.dat FIIDOS input file 

 2 krxe.gam Gamma-ray Emission Spectrum for Krypton and Xenon 

Radionuclides 

 2 gref.sur Gamma-ray Exposure Factor above Contaminated Surface 

 2 gref.inc Gamma-ray Exposure Factor Aloft inside Debris Cloud 

 2 gref.blc Gamma-ray Exposure Factor at Surface inside Debris Cloud 

 2 tape5.inp ORIGEN2-SAIC input file created by subroutine orgsrc.ftn 

3 orgsrc.dat Initial 1 msec fission product inventory for U-235, U-238, 

Pu-239; fast & 14 MeV 

2 & 3 frac.gam Gamma-ray Emission Spectrum for Fractionated Fission 

Products (user supplied) 

ORIGEN2-SAIC data files 

Unit Number File Name File Contents

 3 tape3.inp (not used) substitute library cards 

 4 tape4.inp (not used) 

 5 tape5.inp ORIGEN2-SAIC input file 

 6 tape6.out ORIGEN2-SAIC output file 

 7 tape7.out (not used) punch output 

 9 tape9.inp decay library 

 10 tape10.inp gamma-ray library 

 11 tape11.out alternative output file 

 12 tape12.out table of contents for tape6.out 

 13 tape13.out (not used)table of contents for tape11.out 

 15 tape15.out debugging file 

 16 tape16.out info on variable actinide cross sections 

 50 tape50.out copy of tape5.inp 

60
Table 13. The 40 basic time intervals that ORIGEN2-SAIC used when 

performing the decay calculations. 

Interval Seconds Seconds Hours Days Years

1 1.00 × 10-3

2 2.15 × 10-3

3 4.64 × 10-3

4 1.00 × 10-2

5 2.15 × 10-2

6 4.64 × 10-2 0.05

7 1.00 × 10-1 0.10

8 2.15 × 10-1 0.22

9 4.64 × 10-1 0.46

10 1.00 × 100 1.00

11 2.15 × 100 2.15

12 4.64 × 100 4.64

13 1.00 × 101 10.00

14 2.15 × 101 21.54

15 4.64 × 101 46.42

16 1.00 × 109 100.00

17 2.15 × 109 215.40 0.06

18 4.64 × 109 464.20 0.13

19 1.00 × 109 1000.0 0.28

20 2.15 × 109 0.60

21 4.64 × 109 1.29 0.05

22 1.00 × 109 2.78 0.12

23 2.15 × 109 5.98 0.25

24 4.64 × 109 12.89 0.54

25 1.00 × 109 27.78 1.16

26 2.15 × 109 2.49

27 4.64 × 109 5.37

28 1.00 × 109 11.57

29 2.15 × 109 24.93 0.07

30 4.64 × 109 53.73 0.15

31 1.00 × 109 115.7 0.32

32 2.15 × 109 249.3 0.68

33 4.64 × 109 537.2 1.47

34 1.00 × 109 3.17

35 2.15 × 109 6.83

36 4.64 × 109 14.72

37 1.00 × 109 31.71

38 2.15 × 109 68.30

39 4.64 × 109 147.2

40 1.00 × 1010 317.1

61
Table 14. Eighteen energy groups for gamma-ray spectra with their midpoint 

energies noted. 

Group Emid(MeV) Group Emid(MeV) Group Emid(MeV)

1 0.010 7 0.225 13 2.25 

2 0.025 8 0.375 14 2.75 

3 0.0375 9 0.575 15 3.50 

4 0.0575 10 0.850 16 5.00 

5 0.0850 11 1.25 17 7.00 

6 0.125 12 1.75 18 9.50 

Table 15. Twenty one energy groups for gamma-ray exposure factors spectra with 

their midpoint energies noted. 

Group Emid(MeV) Group Emid(MeV) Group Emid(MeV)

1 14.0 8 3.0 15 0.3 

2 10.0 9 2.5 16 0.15 

3 8.0 10 2.0 17 0.1 

4 7.0 11 1.5 18 0.07 

5 6.0 12 1.0 19 0.045 

6 5.0 13 0.7 20 0.03 

7 4.0 14 0.45 21 0.02 

62
Table 16. Input data required by FIIDOS. 

1. Title 

2. Index for Type of Problem 

3. First Index for Output Control 

4. Second Index for Output Control 

5. Third Index for Output Control 

6. Fourth Index for Output Control 

7. Fifth Index for Output Control 

8. Number of Measurements 

9. Types of Radiological Measurements 

10. Times at which Radiological Measurements are Performed 

11. Measured Radiation Intensities 

12. Types of Radiation Intensity Measurement Devices 

13. Measured Gross Activities 

14. Number of Exposure Incidents 

15. Times at which the Exposures Occurred 

16. Measurement Correspondences of Exposures 

17. Durations of the Exposures 

18. Breathing Rates During the Exposures 

19. Ratios of Airborne to Surface Activity during the Exposures 

20. Types of Dose Conversion Factors for Exposures 

21. Fissile Yields for Fission Products 

22. Index for Activation Products 

23. Activation Product Yields 

24. Index for Actinides 

25. Actinide Yields 

26. Index for Krypton and Xenon 

27. Index for Fractionation of Fission Products 

28. Number of Fission Product Radionuclides to be Modified by Fractionation 

29. Identification Numbers of Fractionated Fission Products 

30. Remaining Fractions of Fission Product Inventory 

31. Gamma-ray Emission Spectrum for Fractionated Fission Products 

32. Index for Plutonium Excretion 

33. Number of Times to Calculate Pu-239 Excretion 

34. User Specified Times for Pu-239 Urine Excretion 

63
Table 16. Input data required by FIIDOS (Continued). 

(1) Item: Title 

 Name: TITLE(I) 

 Remarks: Title of problem selected by user. 

(2) Item: Index for Type of Problem 

 Name: ITPM 

 Remarks: The index parameter ITPM may have the integer value of 1 or 2. 

 

The following scheme is used: 

 Value Type of Problem 

 1 Short (Acute) Exposures (up to 100 measurement plus exposure 

times) 

 2 Long Duration (Integrated) Exposures (up to 33 long duration 

integrations) 

(3) Item: First Index for Output Control 

 Name: IOUT1 

 Remarks: The index parameter IOUT1 may have the integer value of 0 or 1. If 

IOUT1 = 0, this output option is not used. If IOUT1 = 1, either the 

relative gamma-ray emission spectrum at the time of measurement 

or the measured activity of radiological material, and the 

radiological contamination scaling factor are provided as code 

output. 

(4) Item: Second Index for Output Control 

 Name: IOUT2 

 Remarks: The index parameter IOUT2 may have the integer value of 0 or 1. If 

IOUT2 = 0, this output option is not used. If IOUT2 = 1, the relative 

radionuclide inventories for fission products, activation products, 

and actinide elements, at the time of exposure, are provided as code 

output. Suppressed for ITPM=2. 

(5) Item: Third Index for Output Control 

 Name: IOUT3 

 Remarks: The index parameter IOUT3 may have the integer value of 0 or 1. If 

IOUT3 = 0, this output option is not used. If IOUT3 = 1, the dose to 

each organ from each radionuclide is provided as code output. 

Suppressed for ITPM=2. 

64
Table 16. Input data required by FIIDOS (Continued). 

(6) Item: Fourth Index for Output Control 

 Name: IOUT4 

 Remarks: The index parameter IOUT4 may have the integer value of 0 or 1. If 

OUT4 = 0, only the total dose from all exposures is printed in the 

output file. If IOUT4 = 1, the intermediate doses corresponding to 

each exposure are printed. If IOUT4 = 0, output for IOUT1, IOUT2, 

and IOUT3 is suppressed. 

(7) Item: Fifth Index for Output Control 

 Name: IOUT5 

 Remarks: The index parameter IOUT5 may have the integer value of 0 or 1. If 

IOUT5 = 0, this output option is not used. If IOUT5 = 1, a summary 

dose table is create in a separate file (FIIDOST.OUT) with dose 

contributions by exposure as well as by source (alpha emitters and 

beta plus gamma emitters). This option is ideal for creating dose 

lookup tables to be imported into spreadsheet programs. 

(8) Item: Number of Radiological Measurements 

 Name: NMEAS 

 Remarks: For ITPM = 1, the parameter NMEAS may have an integer value 

between 1 and 99, with the additional requirement that NMEAS + 

NEXP ≤ 100. For ITPM = 2, NMEAS may have an integer value 

between 1 and 33. FIIDOS will ignore measurements that do not 

have corresponding exposures. 

*** Data items 9, 10, 11, 12, and 13 are entered in sequence for each measurement *** 

(9) Item: Types of Radiological Measurements 

 Name: XITRM (NMEAS entries required) 

 Remarks: The index parameter XITRM(I) may have the integer value of 1, 2, 

3, 4, 5, or 6. 

The following scheme is used: 

 Value Type of Radiological Measurement 

 1 Radiation Intensity - Above Contam. Surface 

 2 Radiation Intensity - Inside Debris Cloud 

 3 Radiation Intensity - Below Debris Cloud 

 4 Gross Activity - Airborne Concentration 

 5 Gross Activity - Surface Concentration 

 6 Gross Activity - Ingestion or Inhalation Intake (if XRIMES(I) ≠ 0; 

indicates Specific Activity Intake) 

65
Table 16. Input data required by FIIDOS (Continued).

(10) Item: Times at which Radiological Measurements are Performed 

 Name: XTMEAS (NMEAS entries required) 

 Remarks: This time is referenced to the time of the nuclear explosion and is 

given in units of hours. 

(11) Item: Measured Radiation Intensities 

 Name: XRIMES (NMEAS entries required) 

 Remarks: If corresponding XITRM = 1, enter the radiation measurement in 

rad hr-1, R hr-1 -1 , or rem hr . If XITRM = 2 or 3, enter the radiation 

intensity (R/hr). If XITRM = 4, or 5, enter a zero. If XITRM = 6, 

enter a zero for gross activity intake, or enter FIIDOS isotope # for 

specific activity intake for that isotope). 

(12) Item: Types of Radiation Intensity Measurement Devices 

 Name: XITMI (NMEAS entries required) 

 Remarks: If corresponding XITRM = 1, enter the integer value of 1, 2, 3, 4, or 

5. 

The following scheme is used: 

 Value Type of Measurement Device 

 1 Tissue, Free-In-Air 

 2 Air, Free-In-Air 

 3 Film Badge, Free-In-Air 

 4 Film Badge, In-Situ (Midplane) 

 5 Film Badge, In-Situ (Isotropic) 

 If XITRM = 2 or 3, enter 2. 

 If XITRM = 4, 5, or 6, enter zero. 

(13) Item: Measured Gross Activities 

 Name: ACTMES (NMEAS entries required) 

 Remarks: If corresponding XITRM = 1, 2, or 3, enter a zero. If XITRM = 4, 5, 

or 6, enter the measured gross activity in units of Ci-m 3, Ci m-2

, or 

Ci, as appropriate. 

(14) Item: Number of Exposure Incidents 

 Name: NEXP 

 Remarks: If ITPM = 1, up to 99 exposure incidents can be calculated, with the 

additional requirement that NMEAS + NEXP 100. If ITPM = 2, up 

to 33 exposure incidents can be entered. 

66
Table 16. Input data required by FIIDOS (Continued).

*** Data items 15, 16, 17, 18, 19 and 20 are entered in sequence for each exposure *** 

(15) Item: Times at which Exposures Occurred 

 Name: XTEXP (NEXP entries required) 

 Remarks: This time is referenced to the time of the nuclear explosion and is 

given in units of hours. 

(16) Item: Measurement Correspondences of Exposures 

 Name: XCMEAS (NEXP entries required) 

 Remarks: This index determines the measurement time corresponding to the 

exposure. 

 The following scheme is used: 

 Value Types of Measurement Correspondence 

 1 Nearest measurement time after exposure 

 0 Nearest measurement time prior to exposure 

th -# Exposure corresponds to # measurement 

(17) Item: Durations of Exposures 

 Name: XDUR (NEXP entries required) 

 Remarks: This duration is given in units of hours. If corresponding XITRM = 

6, enter 10. 

(18) Item: Breathing Rates during Exposures 

 Name: XBR (NEXP entries required) 

 Remarks: The breathing rate is given in units of m3

 hr-1. If corresponding 

XITRM = 6, enter the value 1.0. 

(19) Item: Ratios of Airborne to Surface Activity during Exposures 

 Name: XKFAC (NEXP entries required) 

-1 Remarks: If corresponding XITRM = 1 or 5, enter the ratio in units of m . If 

XITRM = 2, 3, 4, or 6, enter the value 1.0. 

(20) Item: Types of Dose Conversion Factor during Exposures 

 Name: ITDCF (NEXP entries required) 

 Remarks: The index parameter ITDCF may have the integer value of 1 or 2. 

 The following scheme is used. 

 Value Dose Conversion Factor 

 1 Inhalation (currently ICRP-72) 

 2 Ingestion (currently ICRP-72) 

 

Table 16. Input data required by FIIDOS (Continued).

67
(21) Item: Fissile Yields from Fissionable Material-Neutron Energy Set 

 Name: YKT (6 entries required) 

 Remarks: Enter the weapon yield in kilotons from one of the two options. 

 I FIIDOS option 1 FIIDOS option 2

 Fission/Fusion Yields Fission by Neutron Energy 

 1 -1 U-235, Fast Neutron 

 2 Total Yield U-235, 14-MeV Neutron 

 3 Total U-235 Yield U-238, Fast Neutron 

 4 Total U-238 Yield U-238, 14-MeV Neutron 

 5 Total Pu-239 Yield Pu-239, Fast Neutron 

 6 Total Fusion yield (for yield balance) Pu-239, 14-MeV Neutron 

(22) Item: Index for Activation Products 

 Name: IACTP 

 Remarks: The index parameter IACTP may have the integer value of 0 or 1. If 

IACTP = 0, activation products are not considered. If IACTP = 1, 

activation products are considered. 

(23) Item: Activation Product Production 

 Name: ACTPP (20 entries required if IACTP=1) 

 Remarks: If IACTP = 0, this data is not required. If IACTP = 1, enter the 

production data, in units of Ci kT-1, for 20 specific radionuclides in 

the following order. 

 (1) Be-7 (2) Na-24 (3) Mn-54 (4) Fe-55 

 (5) Fe-59 (6) Co-57 (7) Co-58 (8) Co-60 

 (9) Cu-64 (10) Cu-67 (11) W-181 (12) W-185 

 (13) W-187 (14) W-188 (15) Au-198 (16) Au-199 

 (17) Pb-203 (18) Not used (19) Not used (20) Not used 

(24) Item: Index for Actinides 

 Name: IACTIN 

 Remarks: The index parameter IACTIN may have the integer value of 0 or 1. 

If IACTIN = 0, actinide elements are not considered. If IACTIN = 

1, actinide elements are considered. 

68
Table 16. Input data required by FIIDOS (Continued).

(25) Item: Actinide Production 

 Name: ACTINP (20 entries required if IACTP=1) 

 Remarks: If IACTIN = 0, this data is not required. If IACTIN = 1, enter the 

production data, in units of Ci kT-1, for 20 specific radionuclides in 

the following order: 

 (1) Th-229 (2) Th-230 (3) Th-234 (4) U-233 

 (5) U-234 (6) U-235 (7) U-237 (8) U-238 

 (9) U-240 (10) Np-237 (11) Np-239 (12) Np-240 

 (13) Pu-238 (14) Pu-239 (15) Pu-240 (16) Pu-241 

 (17) Am-241 (18) Cm-242 (19) Not used (20) Not used 

(26) Item: Index for Krypton and Xenon 

 Name: IKRXER 

Remarks: The index parameter IKRXER may have the integer value of 0 or 1. 

If IKRXER=0, the fission product inventory is not modified. If 

IKRXER = 1, krypton and xenon radionuclides are removed from 

the fission product inventory. 

(27) Item: Index for Fractionation of Fission Products 

 Name: IFRAC 

 Remarks: The index parameter IFRAC may have the integer value of 0 or 1. If 

IFRAC = 0, the fission product inventory is not modified. If IFRAC 

= 1, the fission product inventory is modified to reflect fractionation 

effects. 

(28) Item: Number of Fission Product Radionuclides to be Modified by 

Fractionation 

 Name: NFRAC 

 Remarks: If IFRAC = 0, this entry is not required. If IFRAC = 1, enter the 

number of radionuclides to be considered. 

***Data Items 29, 30, and 31 are entered in sequence for each radionuclide*** 

(29) Item: Identification Numbers of Fractionated Fission Products 

 Name: IDFRAC (NFRAC entries required if IFRAC=1) 

 Remarks: If IFRAC = 0, this data is not required. If IFRAC = 1, enter the 

identification number for each fractionated fission product using the 

identification numbers given below. 

69
Table 16. Input data required by FIIDOS (Continued).

(1) SE-79 (2) BR-82 (3) BR-83 (4) KR-83M (5) BR-84 

(6) BR-85 (7) KR-85 (8) KR-85M (9) RB-86 (10) KR-87 

(11) RB-87 (12) KR-88 (13) RB-88 (14) KR-89 (15) RB-89 

(16) SR-89 (17) RB-90 (18) RB-90M (19) SR-90 (20) Y-90 

(21) RB-91 (22) SR-91 (23) Y-91 (24) Y-91M (25) SR-92 

(26) Y-92 (27) SR-93 (28) Y-93 (29) ZR-93 (30) NB-93M 

(31) Y-94 (32) Y-95 (33) ZR-95 (34) NB-95 (35) Y-96 

(36) ZR-97 (37) NB-97 (38) NB-97M (39) NB-98M (40) MO-99 

(41) TC-99 (42) TC-99M (43) MD-101 (44) TC-101 (45) MO-102 

(46) TC-102 (47) TC-103 (48) RU-103 (49) RH-103M (50) TC-104 

(51) MO-105 (52) TC-106 (53) RU-105 (54) RH-105 (55) RH-105M 

(56) RU-106 (57) RH-106 (58) PD-107 (59) RH-109 (60) PD-109 

(61) AG-109M(62) AG-110M(63) AG-111 (64) CD-113M (65) CD-115M 

(66) SN-123 (67) SB-124 (68) SN-125 (69) SB-125 (70) TE-125M 

(71) SN-126 (72) SB-126 (73) SB-127 (74) TE-127 (75) TE-127M 

(76) SB-129 (77) TE-129 (78) TE-129M (79) I-129 (80) SN-130 

(81) SB-130M (82) I-130 (83) SB-131 (84) TE-131 (85) TE-131M 

(86) I-131 (87) XE-131M (88) SB-132 (89) SB-132M (90) TE-132 

(91) I-132 (92) SB-133 (93) TE-133 (94) TE-133M (95) I-133 

(96) XE-133 (97) XE-133M (98) TE-134 (99) I-134 (100) CS-134 

(101) CS-134M (102) I-135 (103) XE-135 (104) XE-135M (105) CS-135 

(106) CS-136 (107) XE-137 (108) CS-137 (109) BA-137M (110) XE-138 

(111) CS-138 (112) CS-139 (113) BA-139 (114) CS-140 (115) BA-140 

(116) LA-140 (117) BA-141 (118) LA-141 (119) CE-141 (120) BA-142 

(121) LA-142 (122) LA-143 (123) CE-143 (124) PR-143 (125) CE-144 

(126) PR-144 (127) PR-144M (128) CE-145 (129) PR-145 (130) CE-146 

(131) PR-146 (132) CE-147 (133) PR-147 (134) ND-147 (135) PM-147 

(136) PR-148 (137) PM-148 (138) PM-148M (139) PM-149 (140) PM-151 

(141) SM-151 (142) EU-152 (143) SM-153 (144) EU-154 (145) EU-155 

(146) EU-156 (147) TB-160 (148) HO-166M (149) NOT USED (150) NOT USED 

(30) Item: Remaining Fractions of Fission Product Inventory 

 Name: FFRAC (NFRAC entries required if IFRAC=1) 

 Remarks: If IFRAC = 0, this data is not required. If IFRAC = 1, enter the 

fraction of the basic fission product inventory that is present in the 

fractionated fallout material which corresponds to each identified 

fission product. 

70
Table 16. Input data required by FIIDOS (Concluded).

(31) Item: Gamma-ray Emission Spectrum for Fractionated Fission Products 

 Name: GAMMA (18 entries for each NFRAC fission products, required if 

IFRAC = 1) 

 Remarks: If IFRAC = 0, this data is not required. If IFRAC = 1, enter the 

gamma-ray emission spectrum in units of γ sec-1 Ci-1 in the 

ORIGEN2 18-energy group structure which corresponds to each 

identified fission product. 

(32) Item: Index for Plutonium Excretion 

 Name: IPLUT 

 Remarks: The index parameter IPLUT may have the integer value of 0 or 1. If 

IPLUT = 0, the plutonium excretion calculations are not included in 

the program output. If IPLUT = 1, plutonium excretion calculation 

is done for each exposure, with all times normalized to the shot time. 

(33) Item: Number of Times to Calculate Pu-239 Excretion 

 Name: NPLUT 

 Remarks: The maximum value for NPLUT is 10. This data is not required if 

IPLUT = 0. 

(34) Item: User Specified Times for Pu-239 Excretion 

 Name: TYRS (NPLUT entries required if IPLUT=1) 

 Remarks: FIIDOS normalizes all excretions to the shot time so that excretions 

from multiple exposures may be added for a total excretion value 

from all exposures. This data is not required if IPLUT = 0. 

71
72

Standard FIIDOS output includes the user-supplied input data and the total calculated 

organ doses. The input data produced include the data given in Table 16. The calculated 

doses for each organ include the doses from fission products, activation products, and 

actinide elements and the total dose from all radionuclides. If specified in the input file, 

the Pu-239 urine excretion amounts are included in the output for the specified times. 

Optional FIIDOS outputs include five separate options under user control: 

• first option provides details on the radiological contamination 

scaling factor, including, as appropriate, either the relative 

gamma-ray emission spectrum at the time of measurement or the 

measured activity of radiological material; 

• second option produces a listing of the relative radiological 

inventories for fission products, activation products, and actinide 

elements, at the time of exposure; 

• third option produces a listing of the dose to each organ from 

each radionuclide; 

• fourth option indicates whether the intermediate results from 

multiple exposure will be produced; and, 

• fifth option produces a secondary output file in tabular format 

with all the intermediate and total doses, convenient for 

importing into a spreadsheet application for further processing.

If no intermediate results are requested, the output from the first three options is 

suppressed. 

The collective output provided by FIIDOS when all four options pertaining to the main 

output file are exercised is shown in Figure 16. The example problem is illustrated in 

Figure 16 is a 15-minute inhalation exposure to depleted fallout 4 hours after the 

detonation. This fallout scenario is characterized by a radiation intensity of 10 R hr-1 at 

H+1 hour. The weapon yield is 10 kT, all from U-235 fast fission. No activation 

products or actinides are considered. The fallout is considered to be depleted of the 

fission gases krypton and xenon, but no other fractionation effects are considered. The 

secondary file output from this run is not reproduced herein.
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM ONE  --------------------------------------------------------------------------------  itpm problem type single/integrated 1/2 1  iout1 print spectrum no/yes 0/1 1  iout2 print inventory no/yes 0/1 1  iout3 print dose inventory no/yes 0/1 1  iout4 print intermediate doses no/yes 0/1 1  iout5 print dose tables no/yes 0/1 1  nmeas number of measurement calculations 1  itrm rad measurement indices 1  tmeas time of rad measurements 1.00  rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 10.0  itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 2  actmes activity measurement (itrm=4-6) 0.00  nexp number of exposure calculations 1  texp exposed @ h+(hr) 4.00  icmeas rad exposure to measurement indices (re-sorted) 1  dur duration (hr) 0.250  br breathing rate (m**3/hr) 1.20  kfac resuspension factors (m**-1) 1.000E-05  itdcf dose conversion factor set index 1/2 1  iactp activation products no/yes 0/1 0  iactin actinides no/yes 0/1 0  ikrxer noble gases removed no/yes 0/1 1  ifrac fractionation no/yes 0/1 0  iplut plutonium bioassay no/yes 0/1 1  nplut number of entries for plutonium bioassay 3  tyrs times after shot for Pu conc in urine 50.0 55.0 60.0  fiidos output  time of measurement 1.00 hours  spec(j)-relative gamma emission spectrum at time of measurement  (gamma/hr per 10**14 fissions)  group # fission product activation product actinides total noble gases fractionated  1 4.140E+11 0.00 0.00 4.140E+11 1.260E+11 0.00  2 1.444E+12 0.00 0.00 1.444E+12 3.149E+10 0.00  3 1.096E+12 0.00 0.00 1.096E+12 3.453E+10 0.00  4 7.883E+10 0.00 0.00 7.883E+10 5.261E+08 0.00  5 7.442E+11 0.00 0.00 7.442E+11 2.103E+08 0.00  6 1.790E+12 0.00 0.00 1.790E+12 2.686E+09 0.00  7 4.983E+12 0.00 0.00 4.983E+12 7.058E+11 0.00  8 6.026E+12 0.00 0.00 6.026E+12 7.673E+11 0.00  9 8.902E+12 0.00 0.00 8.902E+12 1.444E+11 0.00 Figure 16. FIIDOS output - all options. 

73
 10 1.320E+13 0.00 0.00 1.320E+13 2.120E+11 0.00 

 11 9.872E+12 0.00 0.00 9.872E+12 1.021E+11 0.00  12 2.386E+12 0.00 0.00 2.386E+12 2.961E+11 0.00  13 1.840E+12 0.00 0.00 1.840E+12 6.322E+11 0.00  14 9.412E+11 0.00 0.00 9.412E+11 1.060E+11 0.00  15 3.465E+11 0.00 0.00 3.465E+11 3.973E+09 0.00  16 4.501E+09 0.00 0.00 4.501E+09 7.963E+05 0.00  17 5.65 0.00 0.00 5.65 0.00 0.00  18 0.00 0.00 0.00 0.00 0.00 0.00  sf scaling factor(10**14 fissions [per m**2, m**3]) 2.54  inventory of 150 fission products, 20 activation products, 20 actinides (ci/10**14 fissions)  1 2 3 4 5 6 7 8 9 10  0 1.541E-12 2.429E-08 4.277E-04 0.00 6.631E-05 6.437E-27 0.00 0.00 1.082E-09 0.00  10 2.724E-17 0.00 2.697E-03 0.00 2.019E-06 1.902E-05 8.465E-20 1.498E-18 1.151E-07 5.839 20 0.00 2.357E-03 4.521E-06 1.425E-03 4.043E-03 3.582E-03 4.910E-11 2.493E-03 5.629E-13 5.736 30 1.545E-05 2.599E-08 2.182E-05 6.677E-08 0.00 1.588E-03 1.503E-03 1.507E-03 2.669E-06 4.352 40 1.951E-13 1.435E-04 1.271E-06 1.273E-05 4.907E-08 4.946E-08 0.00 1.795E-05 1.696E-05 4.234 50 0.00 1.632E-11 7.627E-04 7.446E-05 2.172E-04 3.118E-07 3.118E-07 2.536E-14 0.00 2.590 60 2.590E-05 1.668E-13 1.208E-06 8.930E-12 5.693E-09 2.340E-09 1.151E-11 1.526E-07 1.035E-08 4.545 70 5.087E-13 2.456E-09 1.507E-05 2.847E-06 2.488E-09 4.143E-04 4.019E-04 1.248E-06 8.066E-15 1.752 80 0.00 3.657E-08 2.825E-05 2.553E-04 7.629E-05 7.388E-05 0.00 5.924E-19 3.320E-27 2.983 90 2.405E-04 3.688E-30 2.152E-04 9.516E-04 1.475E-03 0.00 0.00 8.914E-04 4.685E-03 1.356 100 2.012E-08 3.235E-03 0.00 0.00 1.029E-13 2.441E-07 0.00 1.250E-07 1.180E-07 0.00  110 6.272E-04 3.606E-09 3.704E-03 0.00 1.011E-04 6.867E-06 1.140E-05 4.208E-03 1.835E-05 2.460 120 3.458E-03 1.003E-06 8.401E-04 6.766E-06 4.031E-06 4.025E-06 5.648E-08 4.559E-25 2.094E-03 3.084 130 8.768E-05 0.00 2.565E-07 4.171E-05 4.610E-09 5.690E-33 1.301E-11 4.658E-12 7.830E-05 6.924 140 2.353E-10 7.886E-17 1.711E-05 9.328E-14 5.155E-09 7.433E-08 2.476E-13 2.434E-19 0.00 0.00  0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00  10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00  0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00  10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00  acttot total activity(curies/10**14 fissions) 5.214E-02  dose commitment in rem from each radionuclide  iso # adrenals bone surf brain breast st wall si wall uli wall lli wall kidneys live 1 6.518E-15 6.518E-15 6.518E-15 6.518E-15 7.822E-15 9.125E-15 2.303E-14 5.649E-14 2.216E-13 9.56 2 1.781E-10 1.713E-10 1.439E-10 1.439E-10 2.466E-10 1.850E-10 2.329E-10 2.877E-10 1.507E-10 1.64 3 4.825E-08 4.825E-08 4.825E-08 4.825E-08 1.206E-06 6.514E-08 7.840E-08 5.910E-08 4.825E-08 4.82 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 8.977E-09 9.351E-09 9.351E-09 7.855E-09 3.553E-07 1.309E-08 1.010E-08 7.668E-09 8.416E-09 8.22 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 3.357E-11 1.221E-10 3.357E-11 3.052E-11 3.662E-11 3.357E-11 4.578E-11 7.019E-11 3.357E-11 3.35 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 4.303E-19 1.690E-18 4.303E-19 4.303E-19 4.533E-19 4.303E-19 6.147E-19 9.988E-19 4.303E-19 4.30 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 1.749E-07 1.977E-07 1.825E-07 1.673E-07 8.366E-06 3.575E-07 2.053E-07 1.673E-07 1.749E-07 1.67Figure 16. FIIDOS output - all options (Continued).

74
 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 15 1.367E-10 2.050E-10 1.480E-10 1.196E-10 3.075E-09 1.765E-10 1.423E-10 1.310E-10 1.253E-10 1.19 16 1.234E-07 3.755E-06 1.234E-07 1.234E-07 1.931E-07 2.414E-07 1.180E-06 3.165E-06 1.234E-07 1.23 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 19 2.532E-09 1.558E-06 2.532E-09 2.532E-09 2.662E-09 2.792E-09 8.766E-09 2.500E-08 2.532E-09 2.53 20 8.399E-15 2.470E-13 8.399E-15 8.399E-15 7.081E-11 1.647E-10 9.058E-10 2.141E-09 8.399E-15 2.47 21 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 22 2.459E-06 1.196E-05 2.459E-06 1.861E-06 1.263E-05 1.861E-05 5.516E-05 5.849E-05 2.526E-06 2.26 23 6.120E-10 8.032E-09 2.040E-10 6.629E-10 3.825E-08 9.562E-08 5.737E-07 1.657E-06 3.442E-10 8.15 24 5.628E-08 4.422E-08 3.939E-08 3.618E-08 6.432E-07 3.055E-07 3.939E-07 3.899E-07 5.628E-08 4.82 25 2.394E-06 1.368E-05 2.394E-06 1.938E-06 1.368E-05 2.508E-05 7.525E-05 5.359E-05 2.508E-06 2.28 26 2.223E-07 2.021E-07 1.515E-07 1.616E-07 5.455E-05 7.577E-05 1.313E-04 6.466E-05 2.627E-07 2.32 27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 28 1.195E-07 1.336E-07 7.735E-08 9.141E-08 3.516E-05 6.961E-05 2.180E-04 2.391E-04 1.477E-07 1.47 29 2.381E-16 7.938E-12 3.334E-16 1.175E-16 1.905E-16 4.763E-16 2.381E-15 6.985E-15 9.366E-17 7.93 30 1.618E-20 8.735E-20 7.602E-21 1.618E-20 3.559E-20 6.955E-20 3.882E-19 1.132E-18 1.181E-19 1.60 31 4.357E-10 3.791E-10 3.878E-10 3.355E-10 6.971E-08 1.786E-08 4.357E-09 5.228E-10 3.834E-10 3.31 32 3.885E-13 3.079E-13 3.005E-13 3.592E-13 5.498E-11 8.063E-12 1.393E-12 4.618E-13 2.492E-13 3.00 33 9.231E-07 8.001E-06 2.339E-07 7.385E-07 4.739E-07 4.862E-07 9.847E-07 2.154E-06 4.246E-07 6.15 34 1.036E-09 5.272E-10 1.036E-10 1.092E-09 6.402E-10 7.155E-10 1.525E-09 3.201E-09 4.142E-10 9.22 35 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 36 2.195E-06 3.808E-06 1.389E-06 1.702E-06 2.240E-05 5.824E-05 2.105E-04 3.001E-04 2.509E-06 2.41 37 1.017E-07 8.053E-08 6.782E-08 6.782E-08 5.510E-06 4.111E-06 3.137E-06 6.782E-07 1.060E-07 8.90 38 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 39 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 40 2.823E-07 3.068E-07 8.837E-08 2.577E-07 2.577E-06 6.382E-06 3.068E-05 7.119E-05 3.437E-07 3.92 41 5.336E-17 5.336E-17 5.336E-17 5.336E-17 3.081E-15 6.602E-16 4.181E-15 1.210E-14 5.336E-17 7.15 42 7.687E-09 1.376E-08 4.855E-09 4.855E-09 6.473E-08 8.496E-08 1.699E-07 1.173E-07 9.709E-09 8.49 43 4.302E-11 3.944E-11 3.944E-11 3.227E-11 3.191E-09 8.605E-10 2.366E-10 3.944E-11 3.585E-11 3.22 44 9.694E-11 1.005E-10 8.976E-11 7.181E-11 1.185E-08 2.262E-09 4.668E-10 7.540E-11 8.258E-11 7.54 45 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 47 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 48 2.025E-07 8.607E-08 1.823E-08 2.025E-07 1.316E-07 1.772E-07 5.569E-07 1.468E-06 7.088E-08 1.67 49 1.004E-12 2.344E-12 6.218E-13 9.566E-13 4.066E-09 2.487E-09 1.435E-09 2.248E-10 8.131E-13 1.48 50 2.150E-10 1.911E-10 1.911E-10 1.672E-10 1.791E-08 4.180E-09 1.146E-09 2.030E-10 1.911E-10 1.67 51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 52 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 53 1.914E-07 1.850E-07 1.248E-07 1.355E-07 4.087E-06 6.238E-06 1.355E-05 1.140E-05 2.366E-07 2.06 54 1.092E-08 1.113E-08 6.090E-09 9.030E-09 1.659E-07 3.780E-07 1.638E-06 3.150E-06 1.050E-08 1.11 55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 56 9.671E-09 4.748E-09 2.198E-09 9.671E-09 1.143E-08 1.846E-08 9.671E-08 2.901E-07 4.132E-09 8.08 57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 58 2.074E-20 3.075E-19 2.074E-20 2.074E-20 3.647E-18 9.296E-18 5.506E-17 1.645E-16 1.359E-17 7.15 59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 60 1.680E-10 6.208E-10 7.303E-11 1.461E-10 1.388E-07 2.921E-07 1.022E-06 1.388E-06 2.337E-09 1.31 61 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 62 4.185E-14 1.693E-14 3.433E-15 4.468E-14 2.304E-14 9.405E-15 1.505E-14 2.445E-14 1.552E-14 3.85 63 2.181E-10 1.601E-10 8.178E-11 2.113E-10 5.793E-09 1.431E-08 8.178E-08 2.147E-07 1.431E-10 1.90 64 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.540E-13 6.044E-13 9.066E-13 1.587E-12 8.562E-11 1.48

 65 1.429E-11 1.268E-11 1.188E-11 1.349E-11 6.101E-11 1.268E-10 6.903E-10 1.926E-09 1.766E-09 3.21

Figure 16. FIIDOS output - all options (Continued).

75
 66 7.920E-12 1.584E-10 7.260E-12 7.920E-12 2.244E-11 4.620E-11 2.574E-10 7.260E-10 7.260E-12 7.92

 67 4.546E-13 6.170E-13 7.469E-14 4.546E-13 3.182E-13 3.897E-13 1.266E-12 3.150E-12 2.013E-13 4.22 68 3.961E-10 2.755E-09 1.507E-10 3.788E-10 1.894E-09 4.305E-09 2.368E-08 6.457E-08 2.497E-10 3.40 69 3.504E-10 2.540E-09 8.468E-11 2.920E-10 2.015E-10 1.752E-10 3.796E-10 8.468E-10 1.606E-10 4.08 70 6.153E-15 7.563E-13 2.564E-15 6.410E-15 1.038E-14 2.051E-14 1.013E-13 2.820E-13 3.077E-14 6.66 71 1.148E-13 4.017E-13 5.452E-14 9.039E-14 6.887E-14 6.887E-14 1.420E-13 3.156E-13 6.600E-14 8.75 72 5.471E-11 4.848E-11 1.108E-11 5.333E-11 5.125E-11 9.696E-11 2.424E-10 5.402E-10 2.701E-11 4.98 73 3.399E-08 5.949E-08 1.275E-08 3.187E-08 1.062E-07 2.635E-07 1.232E-06 3.272E-06 2.507E-08 4.07 74 8.831E-11 2.087E-10 8.831E-11 8.831E-11 7.225E-09 1.284E-08 3.934E-08 4.094E-08 2.729E-10 9.63 75 4.280E-12 7.016E-10 3.157E-12 4.069E-12 7.016E-12 1.473E-11 1.123E-10 3.789E-10 5.262E-11 4.06 76 1.869E-07 2.453E-07 1.285E-07 1.402E-07 3.271E-06 6.075E-06 1.285E-05 8.178E-06 2.220E-07 2.10 77 4.987E-09 5.780E-09 4.307E-09 4.194E-09 1.473E-06 1.043E-06 7.140E-07 1.360E-07 5.894E-09 4.76 78 3.485E-09 1.197E-07 2.218E-09 3.238E-09 9.856E-09 2.358E-08 1.408E-07 3.872E-07 3.379E-08 3.16 79 1.365E-17 4.549E-17 1.592E-17 1.251E-17 1.638E-17 1.365E-17 2.502E-17 4.549E-17 1.319E-17 1.34 80 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 81 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 82 3.610E-11 5.879E-11 6.498E-11 3.300E-11 1.341E-10 3.919E-11 4.229E-11 5.054E-11 3.300E-11 3.40 83 2.310E-09 2.231E-09 1.832E-09 1.673E-09 1.115E-07 5.019E-08 2.470E-08 1.195E-08 2.071E-09 1.83 84 5.617E-09 5.401E-09 4.104E-09 4.248E-09 6.265E-07 2.016E-07 7.921E-08 5.905E-08 4.753E-09 4.53 85 1.786E-07 3.442E-07 9.466E-08 1.506E-07 6.239E-07 1.377E-06 4.518E-06 8.175E-06 2.367E-07 1.80 86 5.209E-08 1.438E-07 1.688E-07 6.667E-08 1.500E-07 4.792E-08 6.459E-08 1.063E-07 4.584E-08 5.00 87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 88 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 90 2.019E-06 3.197E-06 8.413E-07 1.935E-06 3.197E-06 9.254E-06 3.449E-05 7.908E-05 1.767E-06 1.93 91 1.085E-07 1.289E-07 1.289E-07 8.819E-08 8.819E-07 1.221E-07 1.221E-07 1.153E-07 1.018E-07 9.49 92 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 93 4.855E-09 4.734E-09 4.370E-09 3.823E-09 3.095E-07 7.890E-08 1.092E-07 1.578E-07 4.309E-09 4.06 94 2.093E-07 1.825E-07 1.530E-07 1.476E-07 5.904E-06 3.757E-06 4.294E-06 3.757E-06 2.147E-07 1.82 95 8.737E-07 1.290E-06 1.415E-06 8.321E-07 4.992E-06 9.569E-07 1.248E-06 1.581E-06 8.321E-07 8.32 96 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 97 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 98 1.810E-07 1.609E-07 1.257E-07 1.232E-07 4.022E-06 3.268E-06 2.765E-06 6.536E-07 2.011E-07 1.65 99 1.083E-06 1.176E-06 1.176E-06 8.324E-07 1.321E-05 1.216E-06 1.150E-06 9.513E-07 9.778E-07 9.24 100 3.824E-12 3.671E-12 2.868E-12 2.638E-12 3.441E-12 3.824E-12 3.709E-12 4.206E-12 3.594E-12 3.63 101 2.043E-12 2.270E-12 1.816E-12 1.646E-12 1.362E-11 2.270E-12 2.440E-12 2.270E-12 1.930E-12 1.98 102 1.916E-06 2.646E-06 2.829E-06 1.734E-06 1.004E-05 2.099E-06 2.372E-06 2.464E-06 1.825E-06 1.82 103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 104 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 105 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.756E-15 2.698E-15 2.901E-15 3.772E-15 2.698E-15 2.69 106 1.101E-08 1.101E-08 8.259E-09 7.571E-09 1.032E-08 1.101E-08 1.101E-08 1.170E-08 1.032E-08 1.03 107 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 108 2.397E-08 2.326E-08 2.009E-08 1.903E-08 2.256E-08 2.397E-08 2.432E-08 2.820E-08 2.291E-08 2.29 109 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 110 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 111 1.026E-07 1.079E-07 1.079E-07 8.668E-08 2.123E-06 1.362E-07 1.114E-07 8.491E-08 9.552E-08 9.19 112 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 113 2.298E-07 1.567E-06 2.298E-07 2.194E-07 1.358E-05 1.024E-05 2.507E-05 5.746E-06 2.298E-07 2.29 114 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 115 8.269E-07 7.698E-06 5.417E-07 3.421E-07 7.698E-07 1.939E-06 1.140E-05 3.707E-05 7.128E-07 4.84 116 2.711E-08 2.517E-08 1.143E-08 2.130E-08 8.908E-08 2.130E-07 6.778E-07 1.297E-06 2.517E-08 7.35

 117 5.142E-10 2.475E-09 5.142E-10 4.178E-10 2.057E-08 1.028E-08 3.214E-08 1.543E-08 5.142E-10 4.82

Figure 16. FIIDOS output - all options (Continued).

76
 118 2.136E-07 1.543E-06 1.543E-07 1.780E-07 4.035E-05 5.815E-05 1.056E-04 6.171E-05 1.899E-07 2.61

 119 3.157E-08 5.175E-08 2.018E-09 3.053E-08 5.692E-08 1.294E-07 6.727E-07 1.915E-06 9.832E-09 4.14 120 1.318E-12 2.845E-12 1.318E-12 9.020E-13 2.290E-11 1.388E-11 3.122E-11 8.327E-12 1.457E-12 1.24 121 1.073E-06 9.266E-07 7.803E-07 7.705E-07 2.828E-05 2.341E-05 2.243E-05 6.242E-06 1.170E-06 1.26 122 7.636E-12 1.386E-11 5.657E-12 6.222E-12 2.461E-09 5.939E-10 5.374E-10 9.051E-10 7.071E-12 5.37 123 3.317E-07 4.265E-07 1.398E-07 3.080E-07 5.449E-06 1.279E-05 5.449E-05 1.114E-04 3.317E-07 4.26 124 2.862E-12 4.389E-10 2.862E-12 2.862E-12 2.862E-08 7.060E-08 4.198E-07 1.164E-06 7.441E-10 3.62 125 3.069E-08 2.274E-07 9.094E-09 3.069E-08 7.844E-08 1.933E-07 1.137E-06 3.410E-06 1.478E-08 6.59 126 2.951E-12 2.497E-12 2.724E-12 2.384E-12 1.135E-08 2.611E-09 4.881E-10 2.611E-11 2.497E-12 2.27 127 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 128 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 129 1.063E-08 1.299E-08 7.086E-09 8.267E-09 1.594E-05 2.716E-05 6.495E-05 5.019E-05 2.008E-08 2.59 130 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 132 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 133 4.413E-12 4.702E-12 3.907E-12 3.328E-12 4.051E-10 7.958E-11 2.894E-11 3.617E-11 3.473E-12 3.40 134 4.940E-08 1.153E-07 5.763E-09 5.058E-08 1.882E-07 4.470E-07 2.352E-06 6.234E-06 2.000E-08 7.29 135 8.971E-15 6.370E-10 3.510E-15 8.451E-15 4.290E-12 1.066E-11 6.500E-11 1.950E-10 5.070E-15 1.69 136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 137 2.861E-14 1.834E-14 6.969E-15 2.971E-14 1.540E-13 3.668E-13 1.834E-12 4.768E-12 1.761E-14 2.97 138 2.233E-13 1.077E-13 1.839E-14 2.365E-13 1.314E-13 1.445E-13 3.416E-13 7.751E-13 8.276E-14 1.97 139 1.745E-09 2.871E-09 6.183E-10 1.590E-09 3.754E-07 8.833E-07 4.637E-06 1.016E-05 1.435E-09 5.74 140 2.734E-08 3.515E-08 1.289E-08 2.343E-08 3.320E-07 7.616E-07 3.124E-06 5.468E-06 2.929E-08 3.12 141 3.251E-15 7.299E-10 1.393E-15 1.128E-15 6.370E-14 1.593E-13 9.953E-13 2.986E-12 1.725E-15 1.92 142 1.067E-16 4.225E-16 2.024E-17 2.891E-17 3.781E-17 4.003E-17 5.115E-17 3.336E-17 7.116E-17 6.00 143 2.653E-09 3.666E-08 9.166E-10 2.171E-09 6.271E-08 1.495E-07 7.236E-07 1.495E-06 2.123E-09 4.05 144 1.105E-13 1.079E-12 2.105E-14 3.157E-14 3.946E-14 4.209E-14 5.525E-14 4.472E-14 7.629E-14 8.94 145 2.762E-10 1.745E-08 4.071E-11 6.107E-11 9.305E-11 1.003E-10 1.745E-10 2.617E-10 2.036E-10 5.38 146 1.027E-09 2.935E-09 1.824E-10 8.594E-10 1.069E-09 2.033E-09 7.546E-09 1.908E-08 1.488E-09 3.98 147 1.187E-14 9.777E-14 2.095E-15 8.380E-15 6.076E-15 7.682E-15 1.955E-14 4.679E-14 9.777E-15 3.77 148 1.030E-18 4.942E-18 1.647E-19 2.197E-19 5.079E-19 3.501E-19 4.324E-19 2.540E-19 6.452E-19 4.18 149 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 150 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

Figure 16. FIIDOS output - all options (Continued).

77
 20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 iso # muscle ovaries pancreas r marrow skin spleen testes thymus thyroid uter 1 6.518E-15 1.217E-14 3.389E-14 6.518E-15 6.518E-15 3.780E-14 1.955E-14 6.518E-15 6.518E-15 6.51 2 1.576E-10 1.918E-10 1.850E-10 1.644E-10 1.028E-10 1.644E-10 1.302E-10 2.055E-10 1.713E-10 1.78 3 4.825E-08 4.825E-08 4.945E-08 4.825E-08 4.825E-08 4.825E-08 4.825E-08 4.825E-08 4.825E-08 4.82 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 9.538E-09 7.668E-09 1.365E-08 8.977E-09 7.294E-09 1.066E-08 6.546E-09 1.085E-08 9.912E-09 7.66 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 3.357E-11 3.357E-11 3.357E-11 6.103E-11 3.052E-11 3.357E-11 3.357E-11 3.357E-11 3.357E-11 3.35 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 4.303E-19 4.303E-19 4.303E-19 8.452E-19 4.303E-19 4.303E-19 4.303E-19 4.303E-19 4.303E-19 4.30 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 1.825E-07 1.673E-07 2.130E-07 1.825E-07 1.673E-07 1.901E-07 1.597E-07 1.977E-07 1.901E-07 1.67 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 15 1.480E-10 1.082E-10 2.221E-10 1.594E-10 1.082E-10 1.708E-10 9.110E-11 1.822E-10 1.594E-10 1.08 16 1.234E-07 1.234E-07 1.234E-07 3.004E-06 1.234E-07 1.234E-07 1.234E-07 1.234E-07 1.234E-07 1.23 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 19 2.532E-09 2.532E-09 2.532E-09 6.818E-07 2.532E-09 2.532E-09 2.532E-09 2.532E-09 2.532E-09 2.53 20 8.399E-15 8.564E-15 8.399E-15 2.470E-13 8.399E-15 8.399E-15 8.399E-15 8.399E-15 8.399E-15 8.39 21 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 22 2.658E-06 4.785E-06 2.658E-06 1.130E-05 1.927E-06 2.326E-06 1.927E-06 2.592E-06 2.526E-06 3.52 23 3.697E-10 3.442E-10 4.972E-10 8.159E-09 2.677E-10 5.100E-10 1.785E-10 7.394E-10 3.570E-10 2.42 24 5.628E-08 1.045E-07 1.407E-07 6.030E-08 2.492E-08 9.245E-08 5.226E-09 6.432E-08 4.422E-08 8.44 25 2.622E-06 3.877E-06 2.850E-06 9.236E-06 2.052E-06 2.508E-06 1.938E-06 2.736E-06 2.508E-06 3.30 26 2.627E-07 8.385E-07 4.041E-07 2.930E-07 1.212E-07 2.829E-07 5.556E-08 2.627E-07 1.717E-07 5.45 27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 28 1.547E-07 6.117E-07 1.758E-07 1.899E-07 6.891E-08 1.336E-07 4.992E-08 1.477E-07 9.141E-08 3.30 29 2.064E-16 7.303E-17 5.398E-17 6.350E-13 1.746E-16 6.985E-17 3.651E-17 1.048E-16 5.874E-17 3.81Figure 16. FIIDOS output - all options (Continued).

78
 30 3.235E-20 9.220E-21 9.058E-21 3.235E-20 8.249E-21 1.779E-20 7.441E-21 9.705E-21 7.602E-21 7.60

 31 4.793E-10 4.313E-10 1.176E-09 4.183E-10 2.266E-10 7.843E-10 3.137E-11 6.100E-10 4.270E-10 3.66 32 3.592E-13 2.052E-13 7.330E-13 3.225E-13 1.759E-13 5.278E-13 2.199E-14 5.791E-13 3.592E-13 1.68 33 4.246E-07 4.431E-07 6.154E-07 1.477E-06 2.400E-07 5.723E-07 1.046E-07 8.616E-07 3.939E-07 2.64 34 4.896E-10 6.779E-10 7.720E-10 6.402E-10 2.448E-10 7.532E-10 7.532E-11 1.262E-09 4.331E-10 3.20 35 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 36 2.733E-06 1.075E-05 2.777E-06 4.928E-06 1.299E-06 2.240E-06 1.210E-06 2.598E-06 1.658E-06 5.37 37 1.060E-07 2.331E-07 2.331E-07 1.102E-07 4.663E-08 1.568E-07 1.272E-08 1.144E-07 7.630E-08 1.78 38 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 39 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 40 2.455E-07 1.043E-06 2.700E-07 3.314E-07 1.056E-07 2.455E-07 1.068E-07 3.437E-07 1.473E-07 4.90 41 5.336E-17 5.336E-17 5.336E-17 5.336E-17 5.336E-17 5.336E-17 5.336E-17 5.336E-17 1.375E-15 5.33 42 9.709E-09 3.398E-08 1.416E-08 1.092E-08 3.641E-09 1.011E-08 2.508E-09 9.305E-09 3.236E-08 2.18 43 4.661E-11 3.944E-11 1.183E-10 3.944E-11 2.187E-11 7.888E-11 2.653E-12 6.095E-11 4.302E-11 3.40 44 1.077E-10 7.899E-11 2.513E-10 9.335E-11 5.027E-11 1.687E-10 1.508E-11 1.293E-10 5.386E-10 6.82 45 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 47 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 48 9.113E-08 1.215E-07 1.519E-07 1.164E-07 4.506E-08 1.418E-07 1.519E-08 2.430E-07 8.101E-08 5.56 49 4.400E-12 7.175E-12 5.261E-12 1.052E-12 8.131E-13 1.913E-12 5.740E-13 8.131E-13 6.218E-13 2.72 50 2.269E-10 2.030E-10 5.374E-10 2.030E-10 1.182E-10 3.702E-10 3.344E-11 2.985E-10 1.051E-09 1.79 51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 52 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 53 2.366E-07 8.173E-07 3.441E-07 2.796E-07 9.894E-08 2.366E-07 5.592E-08 2.151E-07 1.463E-07 4.94 54 1.197E-08 4.410E-08 1.239E-08 1.449E-08 6.090E-09 1.071E-08 6.300E-09 1.239E-08 7.560E-09 2.31 55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 56 4.836E-09 2.901E-09 7.297E-09 5.803E-09 3.253E-09 7.034E-09 1.934E-09 1.143E-08 4.748E-09 2.37 57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 58 2.074E-20 2.074E-20 2.074E-20 1.144E-19 2.074E-20 2.074E-20 2.074E-20 2.074E-20 2.074E-20 2.07 59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 60 4.090E-10 2.191E-09 2.629E-10 3.067E-10 9.494E-11 1.972E-10 7.011E-11 1.753E-10 8.764E-11 5.25 61 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 62 1.834E-14 7.995E-15 3.057E-14 2.304E-14 9.876E-15 3.010E-14 1.129E-15 5.173E-14 1.740E-14 4.28 63 1.636E-10 4.430E-10 1.976E-10 1.976E-10 9.881E-11 1.806E-10 8.859E-11 2.556E-10 1.261E-10 2.28 64 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.289E-13 5.28 65 1.268E-11 1.332E-11 1.365E-11 1.300E-11 1.220E-11 1.365E-11 1.188E-11 1.397E-11 1.252E-11 1.25 66 7.260E-12 7.260E-12 7.920E-12 5.676E-11 7.260E-12 7.920E-12 7.260E-12 7.920E-12 7.260E-12 7.26 67 2.241E-13 2.858E-13 3.572E-13 3.897E-13 1.266E-13 3.247E-13 5.196E-14 5.521E-13 2.111E-13 1.49 68 2.712E-10 6.027E-10 3.229E-10 1.765E-09 1.722E-10 3.100E-10 1.335E-10 4.305E-10 2.239E-10 3.18 69 1.752E-10 1.489E-10 2.599E-10 4.964E-10 1.022E-10 2.365E-10 6.132E-11 3.504E-10 1.606E-10 1.05 70 4.999E-15 7.179E-15 3.718E-15 6.538E-14 2.436E-15 4.999E-15 1.923E-15 5.384E-15 3.974E-14 2.69 71 6.743E-14 5.882E-14 8.752E-14 2.009E-13 4.591E-14 8.034E-14 3.587E-14 1.076E-13 6.600E-14 4.87 72 3.117E-11 8.311E-11 4.294E-11 4.848E-11 1.524E-11 4.017E-11 1.039E-11 6.372E-11 2.493E-11 4.01 73 2.889E-08 1.062E-07 3.272E-08 6.374E-08 1.445E-08 2.847E-08 1.360E-08 3.909E-08 1.955E-08 5.09 74 9.633E-11 1.204E-10 9.633E-11 2.007E-10 8.831E-11 9.633E-11 8.831E-11 9.633E-11 3.372E-10 1.04 75 3.718E-12 3.999E-12 3.578E-12 1.894E-10 3.017E-12 3.718E-12 2.806E-12 3.929E-12 7.016E-11 3.08 76 2.220E-07 7.126E-07 3.154E-07 2.921E-07 1.086E-07 2.337E-07 6.542E-08 2.220E-07 1.519E-07 4.55 77 5.440E-09 8.387E-09 8.500E-09 5.667E-09 3.854E-09 6.460E-09 3.060E-09 5.327E-09 5.667E-09 6.91 78 2.781E-09 3.450E-09 3.027E-09 5.280E-08 2.253E-09 2.992E-09 2.077E-09 3.450E-09 4.576E-08 2.53 79 3.412E-17 1.410E-17 1.365E-17 1.570E-17 1.570E-17 1.342E-17 1.274E-17 1.934E-17 2.275E-13 1.38 80 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 81 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

Figure 16. FIIDOS output - all options (Continued).

79
 82 6.188E-11 4.229E-11 4.641E-11 5.260E-11 3.610E-11 3.816E-11 3.300E-11 7.323E-11 1.857E-08 5.67

 83 2.390E-09 3.187E-09 5.497E-09 2.310E-09 1.195E-09 3.744E-09 3.983E-10 2.948E-09 4.939E-08 2.54 84 5.617E-09 7.201E-09 1.224E-08 5.329E-09 2.808E-09 8.641E-09 1.224E-09 6.985E-09 4.897E-07 5.68 85 1.893E-07 7.100E-07 2.001E-07 2.582E-07 9.036E-08 1.721E-07 8.606E-08 2.130E-07 7.745E-06 3.44 86 1.458E-07 5.000E-08 5.625E-08 1.146E-07 7.709E-08 5.209E-08 3.959E-08 1.771E-07 4.375E-04 5.83 87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 88 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 90 1.851E-06 6.562E-06 1.935E-06 2.356E-06 9.254E-07 1.767E-06 1.010E-06 2.356E-06 5.384E-05 3.19 91 1.357E-07 1.085E-07 1.560E-07 1.221E-07 8.819E-08 1.221E-07 8.819E-08 1.560E-07 1.289E-05 1.35 92 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 93 5.644E-09 9.103E-09 1.032E-08 5.401E-09 2.731E-09 7.283E-09 1.153E-09 6.676E-09 3.277E-07 5.46 94 2.281E-07 4.831E-07 4.562E-07 2.308E-07 1.074E-07 3.221E-07 4.831E-08 2.496E-07 6.709E-06 3.48 95 1.331E-06 9.569E-07 9.985E-07 1.165E-06 9.153E-07 8.737E-07 7.905E-07 1.498E-06 1.706E-03 1.16 96 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 97 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 98 1.986E-07 4.525E-07 4.022E-07 2.061E-07 9.302E-08 2.765E-07 4.022E-08 2.087E-07 8.799E-07 3.52 99 1.229E-06 9.513E-07 1.718E-06 1.110E-06 7.928E-07 1.321E-06 7.267E-07 1.453E-06 4.757E-05 1.07 100 3.212E-12 3.824E-12 3.824E-12 3.441E-12 2.409E-12 3.594E-12 3.212E-12 3.441E-12 3.441E-12 4.20 101 1.930E-12 2.043E-12 2.157E-12 1.873E-12 1.589E-12 1.986E-12 1.816E-12 1.986E-12 1.930E-12 2.04 102 2.737E-06 2.099E-06 2.464E-06 2.372E-06 1.825E-06 2.099E-06 1.734E-06 3.285E-06 7.482E-04 2.64 103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 104 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 105 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.698E-15 2.69 106 8.948E-09 1.101E-08 1.170E-08 9.636E-09 6.607E-09 1.032E-08 8.948E-09 1.032E-08 1.032E-08 1.17 107 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 108 2.150E-08 2.432E-08 2.432E-08 2.220E-08 1.833E-08 2.291E-08 2.150E-08 2.220E-08 2.220E-08 2.46 109 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 110 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 111 1.097E-07 8.491E-08 1.592E-07 1.026E-07 8.137E-08 1.274E-07 7.076E-08 1.291E-07 1.167E-07 8.49 112 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 113 2.298E-07 2.612E-07 2.507E-07 1.567E-06 2.194E-07 2.403E-07 2.194E-07 2.298E-07 2.298E-07 2.50 114 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 115 6.273E-07 1.910E-06 6.273E-07 5.417E-06 3.707E-07 4.847E-07 3.992E-07 4.562E-07 4.562E-07 9.69 116 2.517E-08 1.046E-07 2.905E-08 3.486E-08 1.239E-08 2.324E-08 1.104E-08 2.905E-08 1.569E-08 5.03 117 5.464E-10 6.106E-10 8.035E-10 2.314E-09 4.178E-10 6.428E-10 3.535E-10 6.106E-10 5.464E-10 5.46 118 1.899E-07 3.086E-07 2.255E-07 4.391E-07 1.543E-07 2.018E-07 1.305E-07 2.018E-07 1.662E-07 2.37 119 1.449E-08 2.225E-08 2.329E-08 1.915E-08 6.210E-09 2.277E-08 1.915E-09 3.829E-08 1.138E-08 1.03 120 1.596E-12 2.706E-12 2.220E-12 3.053E-12 9.020E-13 1.596E-12 6.869E-13 1.665E-12 1.388E-12 2.01 121 1.170E-06 2.536E-06 2.146E-06 1.170E-06 5.754E-07 1.561E-06 2.341E-07 1.268E-06 8.875E-07 1.95 122 7.919E-12 1.980E-11 1.046E-11 1.301E-11 4.808E-12 8.202E-12 4.242E-12 8.485E-12 6.222E-12 1.10 123 4.028E-07 1.895E-06 4.028E-07 4.976E-07 1.493E-07 3.317E-07 1.493E-07 4.028E-07 1.967E-07 8.53 124 2.862E-12 2.862E-12 2.862E-12 4.389E-10 2.862E-12 2.862E-12 2.862E-12 2.862E-12 2.862E-12 2.86 125 1.705E-08 1.069E-08 2.387E-08 1.364E-07 1.250E-08 2.387E-08 7.957E-09 3.524E-08 1.591E-08 9.32 126 3.178E-12 2.611E-12 7.606E-12 2.724E-12 1.589E-12 5.108E-12 2.951E-13 4.200E-12 2.951E-12 2.27 127 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 128 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 129 1.358E-08 4.960E-08 1.771E-08 1.712E-08 6.495E-09 1.299E-08 3.897E-09 1.299E-08 8.267E-09 2.89 130 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 132 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 133 4.919E-12 3.617E-12 1.158E-11 4.051E-12 2.170E-12 7.958E-12 2.387E-13 6.222E-12 4.341E-12 2.89

Figure 16. FIIDOS output - all options (Continued).

80
 134 2.823E-08 8.586E-08 3.881E-08 4.117E-08 1.129E-08 3.764E-08 6.939E-09 6.116E-08 2.000E-08 3.64

 135 5.590E-15 3.770E-15 7.540E-15 5.070E-11 4.290E-15 7.020E-15 3.380E-15 9.751E-15 5.070E-15 3.64 136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 137 2.091E-14 7.336E-14 2.457E-14 2.751E-14 9.903E-15 2.311E-14 7.336E-15 3.594E-14 1.394E-14 3.37 138 1.012E-13 1.274E-13 1.708E-13 1.314E-13 5.124E-14 1.576E-13 1.314E-14 2.759E-13 9.196E-14 5.91 139 1.700E-09 7.508E-09 1.855E-09 3.312E-09 6.846E-10 1.590E-09 7.067E-10 2.076E-09 9.717E-10 3.53 140 3.320E-08 1.543E-07 3.515E-08 4.101E-08 1.269E-08 2.929E-08 1.289E-08 3.320E-08 1.718E-08 7.42 141 1.593E-15 1.128E-15 1.858E-15 5.773E-11 1.194E-15 1.062E-15 9.290E-16 1.128E-15 9.953E-16 9.29 142 3.113E-17 3.113E-17 8.006E-17 1.557E-16 1.957E-17 2.891E-17 8.228E-18 2.891E-17 1.846E-17 2.22 143 2.798E-09 1.351E-08 2.991E-09 1.399E-08 1.013E-09 2.316E-09 1.013E-09 2.846E-09 1.254E-09 5.78 144 3.157E-14 3.157E-14 8.155E-14 2.394E-13 2.052E-14 3.157E-14 8.682E-15 3.157E-14 1.973E-14 2.39 145 7.124E-11 7.124E-11 2.181E-10 1.454E-09 3.344E-11 6.688E-11 1.221E-11 7.270E-11 3.780E-11 4.79 146 5.031E-10 1.132E-09 7.965E-10 1.425E-09 2.725E-10 6.708E-10 1.342E-10 9.852E-10 3.983E-10 5.24 147 4.679E-15 5.517E-15 8.380E-15 2.025E-14 2.654E-15 6.355E-15 9.777E-16 9.079E-15 3.911E-15 3.07 148 2.608E-19 2.608E-19 5.560E-18 1.030E-18 1.579E-19 4.324E-19 6.658E-20 2.334E-19 1.441E-19 1.92 149 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 150 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 4 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 5 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 7 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 8 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 9 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 11 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

Figure 16. FIIDOS output - all options (Continued).

81
 16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0

 17 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 total dose commitments in rem for intake at time = 4.00 hours  with duration time = 0.250 hours  fission products activation products actinides(g+b) actinides(a) total  adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05  bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05  brain 1.655E-05 0.00 0.00 0.00 1.655E-05  breast 1.577E-05 0.00 0.00 0.00 1.577E-05  st wall 3.192E-04 0.00 0.00 0.00 3.192E-04  si wall 4.332E-04 0.00 0.00 0.00 4.332E-04  uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03  lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03  kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05  liver 2.182E-05 0.00 0.00 0.00 2.182E-05  et region 3.062E-03 0.00 0.00 0.00 3.062E-03  lung 1.066E-03 0.00 0.00 0.00 1.066E-03  muscle 2.120E-05 0.00 0.00 0.00 2.120E-05  ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05  pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05  r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05  skin 1.308E-05 0.00 0.00 0.00 1.308E-05  spleen 1.977E-05 0.00 0.00 0.00 1.977E-05  testes 1.176E-05 0.00 0.00 0.00 1.176E-05  thymus 2.342E-05 0.00 0.00 0.00 2.342E-05  thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03  uterus 2.950E-05 0.00 0.00 0.00 2.950E-05  ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04  eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04  radionuclides contributing > 1% to effective dose equivalent  nuclide rem percent  sr-91 1.861E-05 3.5  sr-92 2.052E-05 3.9  y-92 2.930E-05 5.6  y-93 4.289E-05 8.1  zr-97 6.272E-05 11.9  mo-99 1.596E-05 3.0  ru-105 5.592E-06 1.1  i-131 2.292E-05 4.3  te-132 2.524E-05 4.8  i-133 8.737E-05 16.6  i-134 1.031E-05 2.0  i-135 4.197E-05 8.0 Figure 16. FIIDOS output - all options (Continued).

82
83

 ba-139 5.746E-06 1.1  la-141 2.730E-05 5.2  la-142 1.463E-05 2.8  ce-143 2.606E-05 4.9  ce-144 6.025E-06 1.1  pr-145 1.535E-05 2.9  pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02  time after shot (yrs) 50. 55. 60.  conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0  total of all measurements and exposures  total dose commitments in rem for all intakes by DCF set  Doses from Specified DCF File  DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006  fission products activation products actinides(g+b) actinides(a) total  adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05  bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05  brain 1.655E-05 0.00 0.00 0.00 1.655E-05  breast 1.577E-05 0.00 0.00 0.00 1.577E-05  st wall 3.192E-04 0.00 0.00 0.00 3.192E-04  si wall 4.332E-04 0.00 0.00 0.00 4.332E-04  uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03  lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03  kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05  liver 2.182E-05 0.00 0.00 0.00 2.182E-05  et region 3.062E-03 0.00 0.00 0.00 3.062E-03  lung 1.066E-03 0.00 0.00 0.00 1.066E-03  muscle 2.120E-05 0.00 0.00 0.00 2.120E-05  ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05  pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05  r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05  skin 1.308E-05 0.00 0.00 0.00 1.308E-05  spleen 1.977E-05 0.00 0.00 0.00 1.977E-05  testes 1.176E-05 0.00 0.00 0.00 1.176E-05  thymus 2.342E-05 0.00 0.00 0.00 2.342E-05  thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03  uterus 2.950E-05 0.00 0.00 0.00 2.950E-05  ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04  eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 Figure 16. FIIDOS output - all options (Concluded).  pu239 fraction in urine from all exposures  time after shot (yrs) 50. 55. 60.  conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0  end 
SECTION 4 

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87
A-1

APPENDIX A 

DOSE FACTORS
Table A-1. Ingestion dose conversion factors 

based on ICRP-72. 

Ingestion Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Se-79 3.58E-03 3.58E-03 3.58E-03 3.58E-03 3.81E-03 3.70E-03 5.27E-03 8.52E-03 1.20E-01 5.15E-02 3.58E-03 3.58E-03

Br-82 1.81E-03 1.67E-03 1.22E-03 1.13E-03 3.09E-03 2.09E-03 2.68E-03 3.40E-03 1.71E-03 1.69E-03 1.51E-03 1.45E-03

Br-83 2.71E-05 2.70E-05 2.68E-05 2.69E-05 1.12E-03 5.40E-05 6.53E-05 4.11E-05 2.71E-05 2.70E-05 2.69E-05 2.69E-05

Kr-83m 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 0.00E+00

Br-84 3.51E-05 2.15E-05 1.64E-05 2.11E-05 2.53E-03 8.75E-05 5.52E-05 2.72E-05 3.39E-05 2.73E-05 1.81E-05 2.43E-05

Br-85 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 0.00E+00

Kr-85 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 0.00E+00

Kr-85m 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 0.00E+00

Rb-86 8.20E-03 3.06E-02 8.04E-03 7.94E-03 1.09E-02 8.24E-03 1.16E-02 1.81E-02 8.13E-03 8.10E-03 8.09E-03 8.05E-03

Kr-87 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 0.00E+00

Rb-87 4.28E-03 1.70E-02 4.28E-03 4.28E-03 4.75E-03 4.29E-03 6.14E-03 9.74E-03 4.28E-03 4.28E-03 4.28E-03 4.28E-03

Kr-88 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 0.00E+00

Rb-88 1.24E-05 9.95E-06 8.01E-06 9.19E-06 2.71E-03 7.24E-05 2.43E-05 1.06E-05 1.21E-05 1.05E-05 8.30E-06 9.90E-06

Kr-89 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 0.00E+00

Rb-89 2.05E-05 1.77E-05 6.85E-06 1.04E-05 1.34E-03 4.49E-05 2.68E-05 1.62E-05 1.93E-05 1.44E-05 7.62E-06 1.26E-05

Sr-89 7.25E-04 2.21E-02 7.25E-04 7.25E-04 3.21E-03 5.07E-03 2.88E-02 8.20E-02 7.25E-04 7.25E-04 7.25E-04 7.25E-04

Rb-90 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 0.00E+00

Rb-90m 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 0.00E+00

Sr-90 2.46E-03 1.51E+00 2.46E-03 2.46E-03 3.33E-03 4.20E-03 2.16E-02 8.10E-02 2.46E-03 2.46E-03 2.46E-03 2.46E-03

Y-90 4.77E-08 1.38E-06 4.77E-08 4.77E-08 3.95E-03 9.46E-03 5.01E-02 1.17E-01 4.77E-08 1.35E-06 4.77E-08 4.77E-08

Rb-91 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 0.00E+00

Sr-91 1.59E-04 5.24E-04 6.90E-05 7.91E-05 3.16E-03 4.78E-03 1.39E-02 1.47E-02 2.28E-04 1.81E-04 7.39E-05 9.52E-05

Y-91 1.28E-06 2.32E-05 4.49E-07 6.39E-07 2.57E-03 6.42E-03 3.86E-02 1.12E-01 2.26E-06 2.28E-05 4.81E-07 7.20E-07

Y-91m 1.07E-05 3.79E-06 5.25E-08 2.39E-06 1.83E-04 8.64E-05 1.05E-04 8.99E-05 1.38E-05 8.38E-06 2.48E-07 3.77E-06

Sr-92 9.60E-05 2.60E-04 3.68E-05 4.90E-05 1.95E-03 3.82E-03 1.14E-02 8.06E-03 1.32E-04 1.02E-04 3.96E-05 5.75E-05

Y-92 1.30E-05 7.74E-06 1.06E-07 3.02E-06 5.26E-03 7.34E-03 1.23E-02 6.33E-03 2.30E-05 1.59E-05 4.51E-07 4.48E-06

Sr-93 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 0.00E+00

Y-93 8.61E-06 7.75E-06 9.74E-08 1.95E-06 4.74E-03 9.29E-03 2.93E-02 3.24E-02 1.75E-05 1.24E-05 3.59E-07 2.82E-06

Zr-93 5.22E-06 1.95E-01 7.87E-06 2.69E-06 8.51E-05 2.10E-04 1.26E-03 3.70E-03 2.13E-06 1.83E-06 1.35E-06 2.82E-06

Nb-93m 1.38E-05 1.39E-04 1.37E-05 1.34E-05 1.38E-04 3.24E-04 1.88E-03 5.48E-03 2.12E-04 2.45E-04 1.35E-05 1.37E-05

Y-94 1.01E-05 2.69E-06 8.43E-08 2.66E-06 2.37E-03 6.03E-04 1.46E-04 1.72E-05 1.08E-05 6.37E-06 3.29E-07 3.99E-06

Y-95 4.11E-06 1.10E-06 6.20E-08 1.31E-06 1.39E-03 2.09E-04 3.30E-05 7.48E-06 4.39E-06 2.60E-06 1.98E-07 1.79E-06

Zr-95 4.97E-04 8.33E-03 1.98E-04 1.38E-04 1.42E-03 3.98E-03 1.15E-02 2.90E-02 6.14E-04 4.01E-04 1.57E-04 2.24E-04

Nb-95 2.75E-04 3.51E-04 4.34E-05 7.15E-05 1.05E-03 3.07E-03 6.79E-03 1.49E-02 5.81E-04 5.32E-04 4.79E-05 1.09E-04

Y-96 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 0.00E+00

Zr-97 1.94E-04 2.34E-04 8.71E-06 4.46E-05 4.51E-03 1.20E-02 4.52E-02 6.57E-02 4.10E-04 2.95E-04 1.40E-05 6.42E-05

Nb-97 1.71E-05 6.95E-06 1.54E-07 3.87E-06 1.44E-03 1.05E-03 7.99E-04 1.76E-04 2.39E-05 1.50E-05 4.93E-07 6.00E-06

Nb-97m 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 0.00E+00

Nb-98m 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 0.00E+00

Mo-99 1.25E-03 3.78E-03 8.95E-04 8.98E-04 2.75E-03 1.10E-03 1.55E-03 2.14E-03 1.15E-02 1.03E-02 9.36E-04 1.02E-03

Tc-99 1.43E-04 1.43E-04 1.43E-04 1.43E-04 8.01E-03 6.84E-04 5.06E-03 1.46E-02 1.43E-04 1.91E-04 1.43E-04 1.43E-04

Tc-99m 1.45E-05 1.93E-05 4.53E-06 4.87E-06 2.06E-04 1.42E-04 2.87E-04 1.99E-04 2.04E-05 1.61E-05 5.40E-06 7.70E-06

Mo-101 1.65E-05 8.25E-06 5.10E-06 7.71E-06 1.20E-03 3.97E-05 2.29E-05 1.03E-05 1.75E-05 1.32E-05 5.74E-06 9.70E-06

Tc-101 2.73E-06 9.21E-07 1.19E-07 6.70E-07 5.55E-04 9.99E-05 2.05E-05 2.94E-06 2.86E-06 1.67E-06 1.60E-07 1.07E-06

Mo-102 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 0.00E+00

Tc-102 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 0.00E+00

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Se-79 3.58E-03 6.75E-03 1.85E-02 3.58E-03 3.58E-03 2.06E-02 1.06E-02 3.58E-03 3.58E-03 3.58E-03 4.11E-03 1.07E-02

Br-82 1.47E-03 2.14E-03 2.09E-03 1.59E-03 1.03E-03 1.79E-03 1.45E-03 1.53E-03 1.51E-03 1.99E-03 1.99E-03 2.02E-03

Br-83 2.69E-05 2.70E-05 2.76E-05 2.69E-05 2.68E-05 2.73E-05 2.69E-05 2.69E-05 2.69E-05 2.70E-05 3.09E-05 1.62E-04

Kr-83m 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 0.00E+00

Br-84 2.38E-05 2.53E-05 8.57E-05 2.32E-05 1.86E-05 5.93E-05 1.79E-05 2.15E-05 1.81E-05 2.47E-05 2.06E-05 3.26E-04

Br-85 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 0.00E+00

Kr-85 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 0.00E+00

Kr-85m 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 0.00E+00

Rb-86 8.06E-03 8.19E-03 8.17E-03 1.56E-02 7.93E-03 8.11E-03 8.04E-03 8.06E-03 8.09E-03 8.17E-03 1.07E-02 1.05E-02

Kr-87 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 0.00E+00

Rb-87 4.28E-03 4.28E-03 4.28E-03 8.47E-03 4.28E-03 4.28E-03 4.28E-03 4.28E-03 4.28E-03 4.28E-03 5.75E-03 5.45E-03

Kr-88 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 0.00E+00

Rb-88 9.76E-06 9.92E-06 2.51E-05 9.83E-06 8.63E-06 1.86E-05 8.28E-06 9.14E-06 8.30E-06 9.76E-06 8.83E-06 3.35E-04

Kr-89 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 0.00E+00

Rb-89 1.21E-05 1.24E-05 5.89E-05 1.40E-05 8.78E-06 3.91E-05 7.61E-06 1.01E-05 7.62E-06 1.20E-05 1.00E-05 1.73E-04

Sr-89 7.25E-04 7.25E-04 7.25E-04 1.77E-02 7.25E-04 7.25E-04 7.25E-04 7.25E-04 7.25E-04 7.25E-04 2.49E-03 9.49E-03

Rb-90 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 0.00E+00

Rb-90m 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 0.00E+00

Sr-90 2.46E-03 2.46E-03 2.46E-03 6.63E-01 2.46E-03 2.46E-03 2.46E-03 2.46E-03 2.46E-03 2.46E-03 5.49E-03 1.02E-01

Y-90 4.79E-08 5.28E-08 4.78E-08 1.38E-06 4.77E-08 4.77E-08 4.77E-08 4.77E-08 4.77E-08 4.78E-08 2.24E-07 9.94E-03

Rb-91 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 0.00E+00

Sr-91 1.68E-04 8.07E-04 2.55E-04 5.81E-04 9.79E-05 1.93E-04 1.25E-04 8.21E-05 7.39E-05 4.69E-04 6.92E-04 2.40E-03

Y-91 2.02E-06 1.38E-05 2.06E-06 2.44E-05 1.06E-06 1.71E-06 1.75E-06 5.88E-07 4.81E-07 6.25E-06 4.68E-06 8.75E-03

Y-91m 6.55E-06 2.99E-05 3.65E-05 8.35E-06 2.50E-06 2.32E-05 1.45E-06 1.72E-06 2.48E-07 2.35E-05 7.28E-06 4.27E-05

Sr-92 8.77E-05 3.46E-04 1.90E-04 2.39E-04 5.53E-05 1.37E-04 5.72E-05 4.76E-05 3.96E-05 2.42E-04 4.60E-04 1.58E-03

Y-92 1.26E-05 8.16E-05 3.36E-05 1.78E-05 4.97E-06 2.22E-05 5.16E-06 2.18E-06 4.51E-07 5.25E-05 2.04E-05 1.83E-03

Sr-93 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 0.00E+00

Y-93 1.11E-05 8.15E-05 1.90E-05 1.64E-05 4.35E-06 1.34E-05 6.39E-06 1.43E-06 3.59E-07 4.42E-05 2.32E-05 4.27E-03

Zr-93 4.91E-06 1.65E-06 1.25E-06 1.57E-02 3.95E-06 1.61E-06 8.61E-07 2.38E-06 1.35E-06 9.10E-07 4.23E-06 4.12E-03

Nb-93m 1.39E-05 2.32E-05 1.37E-05 5.36E-05 1.33E-05 1.36E-05 1.35E-05 1.35E-05 1.35E-05 1.37E-05 1.78E-05 4.60E-04

Y-94 4.86E-06 1.42E-05 3.63E-05 5.22E-06 2.08E-06 2.27E-05 9.32E-07 2.00E-06 3.29E-07 1.20E-05 3.76E-06 3.01E-04

Y-95 1.97E-06 4.45E-06 1.59E-05 1.97E-06 9.11E-07 9.90E-06 3.96E-07 1.00E-06 1.98E-07 3.71E-06 1.38E-06 1.71E-04

Zr-95 5.06E-04 3.25E-03 5.47E-04 1.78E-03 2.34E-04 4.15E-04 3.87E-04 1.61E-04 1.57E-04 1.50E-03 1.06E-03 3.56E-03

Nb-95 3.91E-04 3.04E-03 4.35E-04 6.45E-04 1.59E-04 3.30E-04 3.31E-04 6.92E-05 4.79E-05 1.37E-03 9.66E-04 2.17E-03

Y-96 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 0.00E+00

Zr-97 2.95E-04 2.31E-03 3.91E-04 4.90E-04 1.12E-04 2.83E-04 2.05E-04 3.50E-05 1.40E-05 1.14E-03 6.76E-04 7.64E-03

Nb-97 1.17E-05 6.00E-05 5.45E-05 1.55E-05 4.51E-06 3.48E-05 3.10E-06 2.81E-06 4.93E-07 4.55E-05 1.45E-05 2.54E-04

Nb-97m 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 0.00E+00

Nb-98m 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 0.00E+00

Mo-99 9.59E-04 1.02E-03 1.21E-03 2.27E-03 8.71E-04 1.05E-03 9.08E-04 9.53E-04 9.36E-04 1.01E-03 1.60E-03 2.24E-03

Tc-99 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 3.74E-03 1.43E-04 5.93E-04 2.37E-03

Tc-99m 1.30E-05 6.19E-05 3.29E-05 1.62E-05 5.79E-06 2.30E-05 7.61E-06 5.93E-06 1.76E-04 4.14E-05 2.88E-05 8.25E-05

Mo-101 9.35E-06 9.69E-06 4.85E-05 9.14E-06 6.50E-06 3.21E-05 5.68E-06 7.60E-06 5.74E-06 9.28E-06 7.01E-06 1.53E-04

Tc-101 1.26E-06 2.98E-06 1.04E-05 1.29E-06 5.35E-07 6.61E-06 2.45E-07 5.18E-07 4.42E-06 2.57E-06 8.85E-07 6.96E-05

Mo-102 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 0.00E+00

Tc-102 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 0.00E+00

A-2
Table A-1. Ingestion dose conversion factors 

based on ICRP-72. 

Ingestion Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Tc-103 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 0.00E+00

Ru-103 3.78E-04 4.10E-04 2.14E-04 2.18E-04 1.14E-03 2.94E-03 9.53E-03 2.45E-02 5.02E-04 4.17E-04 2.49E-04 2.68E-04

Rh-103m 1.41E-08 2.37E-08 1.23E-08 1.23E-08 9.51E-05 5.86E-05 3.33E-05 5.28E-06 1.70E-08 1.68E-08 1.23E-08 1.52E-08

Tc-104 1.70E-05 5.37E-06 9.07E-07 5.14E-06 2.30E-03 5.03E-04 1.35E-04 2.18E-05 1.84E-05 1.12E-05 1.37E-06 7.32E-06

Mo-105 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 0.00E+00

Tc-105 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 0.00E+00

Ru-105 5.44E-05 3.94E-05 4.81E-06 1.44E-05 1.84E-03 2.75E-03 5.89E-03 4.92E-03 9.61E-05 6.79E-05 6.23E-06 2.03E-05

Rh-105 2.43E-05 3.02E-05 1.05E-05 1.23E-05 7.20E-04 1.62E-03 7.16E-03 1.41E-02 4.06E-05 3.04E-05 1.11E-05 1.41E-05

Rh-105m 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 0.00E+00

Ru-106 5.44E-03 5.44E-03 5.29E-03 5.27E-03 1.16E-02 2.05E-02 9.46E-02 2.66E-01 5.48E-03 5.44E-03 5.35E-03 5.35E-03

Rh-106 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 0.00E+00

Pd-107 3.76E-08 5.46E-07 3.76E-08 3.76E-08 3.96E-05 9.84E-05 5.98E-04 1.75E-03 2.48E-05 1.28E-05 3.76E-08 3.76E-08

Rh-109 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 0.00E+00

Pd-109 8.92E-07 4.70E-06 3.51E-07 4.06E-07 1.79E-03 3.70E-03 1.33E-02 1.73E-02 2.49E-05 1.35E-05 3.54E-07 5.05E-07

Ag-109m 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 0.00E+00

Ag-110m 6.85E-03 3.19E-03 1.27E-03 2.12E-03 6.37E-03 1.29E-02 2.31E-02 4.27E-02 6.05E-03 2.81E-02 1.71E-03 3.65E-03

Ag-111 7.54E-05 7.48E-05 6.35E-05 6.51E-05 1.60E-03 3.68E-03 2.07E-02 5.52E-02 8.10E-05 2.17E-03 6.41E-05 6.77E-05

Cd-113m 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.38E-02 1.49E-02 2.45E-02 4.68E-02 2.09E+00 3.60E-01 1.30E-02 1.30E-02

Cd-115m 6.68E-04 6.25E-04 6.11E-04 6.16E-04 3.24E-03 6.83E-03 3.76E-02 1.07E-01 9.57E-02 1.66E-02 6.13E-04 6.25E-04

Sn-123 1.22E-04 2.54E-03 1.20E-04 1.19E-04 2.35E-03 5.57E-03 3.32E-02 9.67E-02 1.23E-04 1.22E-04 1.20E-04 1.20E-04

Sb-124 1.44E-03 1.01E-02 6.75E-04 6.28E-04 4.03E-03 9.74E-03 3.16E-02 8.08E-02 1.70E-03 2.36E-03 6.92E-04 8.42E-04

Sn-125 1.11E-04 9.26E-04 3.72E-05 4.81E-05 3.79E-03 9.31E-03 5.05E-02 1.37E-01 1.86E-04 1.37E-04 3.86E-05 5.81E-05

Sb-125 1.58E-03 3.36E-02 9.72E-04 7.67E-04 1.83E-03 3.62E-03 9.39E-03 2.30E-02 1.42E-03 2.91E-03 9.58E-04 1.06E-03

Te-125m 2.83E-04 7.32E-02 2.61E-04 2.05E-04 7.37E-04 1.27E-03 5.93E-03 1.64E-02 3.02E-03 2.22E-04 2.15E-04 2.38E-04

Sn-126 3.45E-03 2.00E-02 2.63E-03 1.71E-03 6.00E-03 1.59E-02 5.99E-02 1.63E-01 3.27E-03 2.65E-03 2.30E-03 2.33E-03

Sb-126 1.32E-03 3.92E-03 4.34E-04 4.44E-04 4.46E-03 1.17E-02 2.97E-02 6.74E-02 1.91E-03 1.88E-03 4.55E-04 6.48E-04

Sb-127 2.70E-04 1.10E-03 1.04E-04 1.16E-04 2.14E-03 5.36E-03 2.55E-02 6.69E-02 4.15E-04 5.27E-04 1.08E-04 1.48E-04

Te-127 1.68E-05 3.81E-05 1.63E-05 1.64E-05 9.05E-04 1.30E-03 3.99E-03 4.21E-03 5.09E-05 1.69E-05 1.64E-05 1.65E-05

Te-127m 5.53E-04 1.19E-01 5.31E-04 4.92E-04 9.32E-04 1.58E-03 1.12E-02 3.87E-02 8.50E-03 5.02E-04 5.01E-04 5.15E-04

Sb-129 9.75E-05 1.06E-04 1.22E-05 2.98E-05 2.68E-03 4.83E-03 1.06E-02 6.67E-03 1.65E-04 1.27E-04 1.51E-05 4.04E-05

Te-129 3.38E-06 3.14E-06 1.98E-06 2.25E-06 1.47E-03 9.63E-04 6.60E-04 1.29E-04 4.45E-06 3.17E-06 2.02E-06 2.47E-06

Te-129m 9.34E-04 4.60E-02 8.53E-04 8.10E-04 2.57E-03 5.05E-03 2.98E-02 8.47E-02 1.28E-02 8.56E-04 8.36E-04 8.49E-04

I-129 4.56E-04 1.48E-03 5.28E-04 4.22E-04 7.38E-04 4.67E-04 8.33E-04 1.59E-03 4.47E-04 4.53E-04 5.28E-04 5.69E-04

Sn-130 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 0.00E+00

Sn-130m 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 0.00E+00

I-130 2.78E-04 2.93E-04 2.62E-04 1.87E-04 2.17E-03 3.40E-04 4.34E-04 4.86E-04 2.60E-04 2.42E-04 2.93E-04 2.63E-04

Sb-131 2.37E-05 1.06E-05 1.76E-06 6.87E-06 1.73E-03 7.57E-04 3.44E-04 8.42E-05 2.78E-05 1.68E-05 2.37E-06 1.02E-05

Te-131 5.74E-06 3.19E-06 1.44E-06 1.90E-06 1.22E-03 3.71E-04 1.13E-04 1.80E-05 6.40E-06 4.02E-06 1.56E-06 2.99E-06

Te-131m 4.57E-04 1.86E-03 2.09E-04 2.11E-04 2.49E-03 5.02E-03 1.64E-02 2.93E-02 1.11E-03 4.98E-04 2.32E-04 2.74E-04

I-131 1.87E-04 4.88E-04 5.32E-04 2.18E-04 1.12E-03 2.00E-04 3.28E-04 6.01E-04 1.70E-04 1.81E-04 5.45E-04 3.82E-04

Xe-131m 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 0.00E+00

Sb-132 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 0.00E+00

Sb-132m 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 0.00E+00

Te-132 1.12E-03 4.25E-03 7.18E-04 6.74E-04 2.83E-03 5.70E-03 2.76E-02 7.16E-02 1.84E-03 1.20E-03 8.18E-04 8.37E-04

I-132 1.31E-04 9.51E-05 7.15E-05 7.46E-05 2.34E-03 1.73E-04 1.95E-04 1.40E-04 1.22E-04 1.05E-04 8.28E-05 9.45E-05

Sb-133 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 0.00E+00

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Tc-103 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 0.00E+00

Ru-103 4.43E-04 2.12E-03 4.96E-04 5.95E-04 2.59E-04 4.27E-04 4.21E-04 2.61E-04 2.49E-04 1.10E-03 8.93E-04 2.72E-03

Rh-103m 3.02E-08 1.66E-07 1.19E-07 1.82E-08 1.33E-08 3.45E-08 1.23E-08 1.23E-08 1.23E-08 6.06E-08 3.25E-08 1.41E-05

Tc-104 8.59E-06 2.20E-05 6.19E-05 8.98E-06 4.05E-06 3.91E-05 2.19E-06 4.16E-06 3.32E-05 1.88E-05 6.86E-06 2.96E-04

Mo-105 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 0.00E+00

Tc-105 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 0.00E+00

Ru-105 5.70E-05 3.65E-04 1.32E-04 8.15E-05 2.32E-05 8.90E-05 2.80E-05 1.21E-05 6.23E-06 2.24E-04 1.09E-04 9.79E-04

Rh-105 3.28E-05 1.94E-04 3.96E-05 4.58E-05 1.73E-05 3.19E-05 2.67E-05 1.24E-05 1.11E-05 1.02E-04 8.07E-05 1.36E-03

Rh-105m 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 0.00E+00

Ru-106 5.42E-03 6.21E-03 5.51E-03 5.51E-03 5.28E-03 5.44E-03 5.41E-03 5.36E-03 5.35E-03 5.77E-03 6.45E-03 2.59E-02

Rh-106 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 0.00E+00

Pd-107 3.76E-08 3.76E-08 3.76E-08 2.05E-07 3.76E-08 3.76E-08 3.76E-08 3.76E-08 3.76E-08 3.76E-08 4.50E-07 1.37E-04

Rh-109 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 0.00E+00

Pd-109 2.19E-06 2.76E-05 2.74E-06 2.87E-06 6.53E-07 1.59E-06 8.14E-07 3.84E-07 3.54E-07 6.38E-06 6.41E-06 2.03E-03

Ag-109m 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 0.00E+00

Ag-110m 3.50E-03 1.29E-02 6.73E-03 4.50E-03 1.99E-03 3.46E-03 2.55E-03 2.32E-03 1.71E-03 6.93E-03 5.14E-03 1.03E-02

Ag-111 7.57E-05 1.60E-04 8.08E-05 8.28E-05 6.72E-05 7.42E-05 7.27E-05 6.52E-05 6.41E-05 1.09E-04 9.80E-05 4.65E-03

Cd-113m 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.30E-02 1.31E-02 8.50E-02

Cd-115m 6.29E-04 6.98E-04 6.59E-04 6.39E-04 6.17E-04 6.52E-04 6.19E-04 6.17E-04 6.13E-04 6.53E-04 6.40E-04 1.22E-02

Sn-123 1.23E-04 1.46E-04 1.23E-04 9.21E-04 1.20E-04 1.22E-04 1.22E-04 1.20E-04 1.20E-04 1.31E-04 1.97E-04 7.78E-03

Sb-124 1.41E-03 6.94E-03 1.62E-03 4.45E-03 8.00E-04 1.29E-03 1.18E-03 7.24E-04 6.92E-04 3.45E-03 3.18E-03 9.42E-03

Sn-125 1.61E-04 1.10E-03 1.71E-04 7.77E-04 8.12E-05 1.39E-04 1.36E-04 4.65E-05 3.86E-05 5.05E-04 4.45E-04 1.14E-02

Sb-125 1.15E-03 2.96E-03 1.43E-03 5.51E-03 7.86E-04 1.13E-03 9.48E-04 9.35E-04 9.58E-04 1.84E-03 1.63E-03 4.20E-03

Te-125m 2.43E-04 5.15E-04 2.32E-04 6.25E-03 2.00E-04 2.33E-04 1.94E-04 2.18E-04 3.85E-03 2.51E-04 5.74E-04 3.22E-03

Sn-126 2.99E-03 9.31E-03 3.17E-03 1.04E-02 2.04E-03 2.66E-03 2.46E-03 2.06E-03 2.30E-03 5.22E-03 4.21E-03 1.77E-02

Sb-126 1.58E-03 1.04E-02 1.80E-03 3.39E-03 7.20E-04 1.39E-03 1.33E-03 5.08E-04 4.55E-04 4.93E-03 3.94E-03 9.11E-03

Sb-127 3.46E-04 2.18E-03 3.96E-04 1.10E-03 1.74E-04 3.14E-04 2.95E-04 1.22E-04 1.08E-04 1.06E-03 1.07E-03 6.18E-03

Te-127 1.68E-05 2.01E-05 1.74E-05 3.74E-05 1.65E-05 1.71E-05 1.66E-05 1.64E-05 6.24E-05 1.84E-05 1.23E-04 6.24E-04

Te-127m 5.15E-04 6.20E-04 5.12E-04 3.04E-02 4.91E-04 5.07E-04 4.84E-04 5.01E-04 1.13E-02 5.18E-04 1.32E-03 8.66E-03

Sb-129 9.78E-05 5.85E-04 2.26E-04 1.58E-04 4.37E-05 1.53E-04 4.91E-05 2.59E-05 1.51E-05 3.66E-04 2.16E-04 1.57E-03

Te-129 2.95E-06 7.07E-06 7.12E-06 3.50E-06 2.29E-06 5.10E-06 2.19E-06 2.20E-06 2.77E-06 5.70E-06 1.02E-05 2.33E-04

Te-129m 8.66E-04 1.15E-03 8.91E-04 1.96E-02 8.15E-04 8.67E-04 8.27E-04 8.31E-04 1.70E-02 9.47E-04 2.59E-03 1.10E-02

I-129 1.11E-03 4.74E-04 4.62E-04 5.19E-04 5.24E-04 4.55E-04 4.30E-04 6.36E-04 7.81E+00 4.66E-04 1.59E-03 3.91E-01

Sn-130 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 0.00E+00

Sn-130m 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 0.00E+00

I-130 3.01E-04 3.33E-04 4.51E-04 2.82E-04 1.88E-04 3.46E-04 2.38E-04 3.09E-04 1.32E-01 4.24E-04 3.48E-03 7.27E-03

Sb-131 1.37E-05 4.56E-05 8.17E-05 1.56E-05 6.11E-06 5.19E-05 3.69E-06 6.07E-06 2.61E-03 3.70E-05 1.82E-05 3.82E-04

Te-131 3.83E-06 9.39E-06 1.97E-05 3.93E-06 1.80E-06 1.26E-05 1.06E-06 2.32E-06 3.30E-03 8.00E-06 8.78E-06 3.24E-04

Te-131m 5.18E-04 2.69E-03 6.61E-04 9.84E-04 2.77E-04 5.27E-04 4.13E-04 2.53E-04 6.85E-02 1.41E-03 1.61E-03 7.23E-03

I-131 4.70E-04 1.93E-04 2.26E-04 3.75E-04 2.54E-04 1.98E-04 1.49E-04 5.65E-04 1.60E+00 2.19E-04 2.80E-03 8.05E-02

Xe-131m 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 0.00E+00

Sb-132 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 0.00E+00

Sb-132m 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 0.00E+00

Te-132 1.36E-03 5.96E-03 1.37E-03 1.99E-03 8.06E-04 1.20E-03 1.33E-03 8.55E-04 1.15E-01 3.25E-03 1.25E-02 1.41E-02

I-132 9.90E-05 1.22E-04 2.70E-04 9.76E-05 6.89E-05 1.93E-04 8.70E-05 9.15E-05 1.27E-02 1.44E-04 1.17E-03 1.06E-03

Sb-133 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 0.00E+00

A-3
Table A-1. Ingestion dose conversion factors 

based on ICRP-72. 

Ingestion Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Te-133 7.67E-06 3.47E-06 1.87E-06 2.90E-06 9.00E-04 1.49E-04 3.80E-05 1.55E-05 7.78E-06 5.13E-06 2.10E-06 4.09E-06

Te-133m 5.91E-05 3.01E-05 1.07E-05 2.04E-05 2.49E-03 1.36E-03 1.06E-03 4.17E-04 7.44E-05 4.91E-05 1.27E-05 2.84E-05

I-133 1.59E-04 1.81E-04 1.78E-04 1.34E-04 2.06E-03 2.12E-04 3.55E-04 4.83E-04 1.53E-04 1.49E-04 1.89E-04 1.68E-04

Xe-133 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 0.00E+00

Xe-133m 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 0.00E+00

Te-134 6.50E-05 4.25E-05 2.64E-05 3.20E-05 1.66E-03 4.64E-04 5.79E-04 1.69E-04 6.84E-05 5.44E-05 3.09E-05 4.08E-05

I-134 7.08E-05 3.92E-05 2.63E-05 3.41E-05 2.04E-03 1.03E-04 9.50E-05 5.44E-05 6.52E-05 5.11E-05 3.10E-05 4.39E-05

Cs-134 7.73E-02 7.39E-02 5.71E-02 5.22E-02 6.99E-02 7.71E-02 7.49E-02 8.34E-02 7.24E-02 7.31E-02 6.86E-02 6.51E-02

Cs-134m 2.60E-05 2.72E-05 2.20E-05 2.09E-05 4.27E-04 3.57E-05 4.06E-05 3.31E-05 2.51E-05 2.51E-05 2.40E-05 2.37E-05

I-135 1.65E-04 1.52E-04 1.29E-04 1.14E-04 2.01E-03 2.15E-04 2.81E-04 2.63E-04 1.58E-04 1.45E-04 1.45E-04 1.43E-04

Xe-135 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 0.00E+00

Xe-135m 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 0.00E+00

Cs-135 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.40E-03 7.12E-03 8.03E-03 9.78E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03

Cs-136 1.22E-02 1.20E-02 8.69E-03 7.92E-03 1.20E-02 1.23E-02 1.20E-02 1.36E-02 1.13E-02 1.14E-02 1.06E-02 1.01E-02

Xe-137 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 0.00E+00

Cs-137 5.19E-02 5.09E-02 4.36E-02 4.15E-02 4.96E-02 5.19E-02 5.34E-02 6.19E-02 4.99E-02 5.02E-02 4.84E-02 4.69E-02

Ba-137m 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 0.00E+00

Xe-138 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 0.00E+00

Cs-138 4.52E-05 2.56E-05 1.83E-05 2.46E-05 2.60E-03 9.61E-05 6.60E-05 3.29E-05 4.31E-05 3.38E-05 2.07E-05 2.96E-05

Cs-139 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 0.00E+00

Ba-139 2.62E-06 1.09E-05 1.39E-06 1.60E-06 2.56E-03 1.96E-03 1.66E-03 3.74E-04 3.29E-06 2.54E-06 1.41E-06 1.80E-06

Cs-140 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 0.00E+00

Ba-140 7.70E-04 6.06E-03 3.71E-04 2.78E-04 2.32E-03 6.15E-03 3.15E-02 1.06E-01 8.37E-04 5.53E-04 3.22E-04 3.99E-04

La-140 3.91E-04 4.27E-04 4.59E-06 9.27E-05 4.04E-03 1.02E-02 3.42E-02 6.45E-02 8.33E-04 5.92E-04 1.91E-05 1.31E-04

Ba-141 8.45E-06 1.01E-05 6.90E-07 2.51E-06 1.46E-03 6.48E-04 8.08E-04 4.32E-04 9.27E-06 5.66E-06 8.45E-07 3.63E-06

La-141 2.37E-06 2.13E-06 5.70E-08 6.09E-07 3.46E-03 5.07E-03 9.20E-03 5.28E-03 4.31E-06 3.72E-06 1.29E-07 8.63E-07

Ce-141 2.00E-05 1.83E-04 9.21E-07 2.81E-06 8.25E-04 2.15E-03 1.13E-02 3.20E-02 4.50E-05 8.82E-05 1.07E-06 5.23E-06

Ba-142 1.38E-05 7.01E-06 6.03E-07 3.91E-06 7.50E-04 3.66E-04 3.40E-04 9.20E-05 1.82E-05 1.16E-05 9.91E-07 5.57E-06

La-142 7.07E-05 3.24E-05 9.83E-07 1.97E-05 3.14E-03 2.65E-03 2.58E-03 6.99E-04 1.08E-04 7.00E-05 3.23E-06 2.71E-05

La-143 9.30E-07 7.38E-07 8.93E-09 2.29E-07 1.46E-03 3.20E-04 2.01E-04 3.14E-04 1.39E-06 9.76E-07 3.21E-08 3.42E-07

Ce-143 4.54E-05 8.11E-05 3.36E-07 7.80E-06 2.07E-03 4.94E-03 2.16E-02 4.31E-02 1.04E-04 8.07E-05 1.23E-06 1.26E-05

Pr-143 4.10E-08 6.39E-06 4.10E-08 4.10E-08 1.34E-03 3.32E-03 1.95E-02 5.46E-02 1.05E-05 5.08E-05 4.10E-08 4.10E-08

Ce-144 5.96E-05 1.23E-03 4.26E-05 4.50E-05 4.13E-03 1.38E-02 8.42E-02 2.46E-01 7.29E-05 3.55E-03 4.29E-05 4.81E-05

Pr-144 2.41E-07 6.70E-08 2.87E-09 6.96E-08 1.52E-03 3.56E-04 6.59E-05 3.51E-06 2.66E-07 1.58E-07 9.65E-09 1.00E-07

Pr-144m 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 0.00E+00

Ce-145 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 0.00E+00

Pr-145 9.90E-07 8.55E-07 3.40E-08 2.36E-07 2.60E-03 4.43E-03 1.05E-02 8.18E-03 2.18E-06 1.98E-06 5.88E-08 3.43E-07

Ce-146 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 0.00E+00

Pr-146 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 0.00E+00

Ce-147 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 0.00E+00

Pr-147 6.18E-06 1.86E-06 3.79E-08 1.49E-06 9.35E-04 1.76E-04 5.35E-05 4.74E-05 6.44E-06 3.77E-06 1.58E-07 2.41E-06

Nd-147 3.06E-05 1.22E-04 2.60E-07 4.94E-06 1.32E-03 3.42E-03 1.76E-02 4.75E-02 7.27E-05 8.21E-05 8.00E-07 8.38E-06

Pm-147 1.11E-08 1.61E-03 8.60E-09 8.69E-09 2.64E-04 6.61E-04 4.00E-03 1.17E-02 1.19E-08 4.30E-04 8.54E-09 9.39E-09

Pr-148 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 0.00E+00

Pm-148 1.21E-04 1.57E-04 1.44E-06 2.81E-05 3.61E-03 9.13E-03 4.51E-02 1.15E-01 2.63E-04 2.17E-04 5.75E-06 4.01E-05

Pm-148m 5.12E-04 8.27E-04 9.76E-06 1.03E-04 2.92E-03 8.73E-03 2.16E-02 5.10E-02 1.10E-03 9.12E-04 2.19E-05 1.60E-04

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Te-133 4.59E-06 8.27E-06 2.52E-05 4.52E-06 2.53E-06 1.63E-05 1.94E-06 3.11E-06 3.01E-03 7.61E-06 4.26E-05 2.68E-04

Te-133m 4.18E-05 1.55E-04 1.73E-04 4.95E-05 2.08E-05 1.13E-04 1.76E-05 2.02E-05 1.19E-02 1.23E-04 2.08E-04 1.05E-03

I-133 1.85E-04 1.81E-04 2.10E-04 1.74E-04 1.37E-04 1.79E-04 1.47E-04 1.94E-04 3.04E-01 2.12E-04 4.11E-03 1.58E-02

Xe-133 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 0.00E+00

Xe-133m 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 0.00E+00

Te-134 4.70E-05 9.99E-05 1.52E-04 4.99E-05 3.01E-05 1.05E-04 3.45E-05 3.61E-05 1.94E-03 8.77E-05 3.13E-04 4.00E-04

I-134 4.39E-05 5.11E-05 1.83E-04 4.27E-05 2.95E-05 1.23E-04 3.24E-05 3.78E-05 1.99E-03 5.52E-05 3.05E-04 3.98E-04

Cs-134 6.41E-02 7.97E-02 8.05E-02 6.91E-02 4.80E-02 7.24E-02 6.43E-02 6.90E-02 6.86E-02 8.09E-02 7.49E-02 7.12E-02

Cs-134m 2.33E-05 2.62E-05 2.98E-05 2.38E-05 2.00E-05 2.66E-05 2.30E-05 2.40E-05 2.40E-05 2.63E-05 2.68E-05 7.44E-05

I-135 1.56E-04 1.83E-04 2.71E-04 1.48E-04 1.11E-04 2.09E-04 1.40E-04 1.57E-04 5.92E-02 2.23E-04 2.42E-03 3.46E-03

Xe-135 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 0.00E+00

Xe-135m 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 0.00E+00

Cs-135 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 7.12E-03 8.07E-03 7.40E-03

Cs-136 9.93E-03 1.27E-02 1.28E-02 1.06E-02 7.16E-03 1.14E-02 9.93E-03 1.07E-02 1.06E-02 1.28E-02 1.19E-02 1.14E-02

Xe-137 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 0.00E+00

Cs-137 4.64E-02 5.30E-02 5.33E-02 4.85E-02 3.97E-02 5.00E-02 4.65E-02 4.85E-02 4.84E-02 5.35E-02 5.35E-02 5.02E-02

Ba-137m 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 0.00E+00

Xe-138 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 0.00E+00

Cs-138 2.88E-05 3.09E-05 1.18E-04 2.79E-05 2.13E-05 8.02E-05 2.04E-05 2.54E-05 2.07E-05 3.00E-05 2.41E-05 3.40E-04

Cs-139 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 0.00E+00

Ba-139 2.29E-06 6.46E-06 5.77E-06 1.09E-05 1.66E-06 4.18E-06 1.57E-06 1.54E-06 1.41E-06 5.29E-06 1.53E-05 4.46E-04

Cs-140 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 0.00E+00

Ba-140 7.49E-04 4.19E-03 7.11E-04 4.62E-03 3.97E-04 5.86E-04 6.10E-04 3.26E-04 3.22E-04 1.85E-03 1.66E-03 9.61E-03

La-140 6.43E-04 5.15E-03 7.71E-04 9.70E-04 2.57E-04 5.89E-04 4.81E-04 6.90E-05 1.91E-05 2.39E-03 1.56E-03 7.49E-03

Ba-141 4.45E-06 1.24E-05 3.01E-05 1.07E-05 2.15E-06 1.91E-05 1.30E-06 2.03E-06 8.45E-07 1.03E-05 8.64E-06 2.59E-04

La-141 2.48E-06 1.64E-05 5.81E-06 3.51E-06 1.03E-06 3.94E-06 1.16E-06 4.54E-07 1.29E-07 1.00E-05 4.33E-06 1.32E-03

Ce-141 4.03E-05 3.75E-04 4.23E-05 7.14E-05 1.18E-05 3.28E-05 2.93E-05 2.34E-06 1.07E-06 1.68E-04 1.20E-04 2.63E-03

Ba-142 9.05E-06 3.92E-05 4.38E-05 1.24E-05 4.03E-06 2.81E-05 2.94E-06 3.10E-06 9.91E-07 2.95E-05 1.27E-05 1.31E-04

La-142 5.45E-05 2.84E-04 2.11E-04 7.02E-05 2.33E-05 1.38E-04 1.82E-05 1.48E-05 3.23E-06 2.11E-04 7.31E-05 6.73E-04

La-143 8.87E-07 6.11E-06 3.01E-06 1.22E-06 3.18E-07 1.96E-06 4.64E-07 1.75E-07 3.21E-08 3.03E-06 1.72E-06 2.07E-04

Ce-143 8.30E-05 7.46E-04 1.03E-04 1.28E-04 2.65E-05 7.43E-05 5.67E-05 5.73E-06 1.23E-06 3.34E-04 2.10E-04 4.14E-03

Pr-143 4.10E-08 4.10E-08 4.10E-08 6.39E-06 4.10E-08 4.10E-08 4.10E-08 4.10E-08 4.10E-08 4.10E-08 2.20E-07 4.33E-03

Ce-144 6.82E-05 2.78E-04 7.07E-05 7.14E-04 5.07E-05 6.23E-05 6.12E-05 4.46E-05 4.29E-05 1.40E-04 1.12E-04 1.94E-02

Pr-144 1.20E-07 3.30E-07 9.11E-07 1.26E-07 5.28E-08 5.72E-07 2.35E-08 5.39E-08 9.65E-09 2.80E-07 9.25E-08 1.87E-04

Pr-144m 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 0.00E+00

Ce-145 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 0.00E+00

Pr-145 1.14E-06 8.06E-06 2.40E-06 1.72E-06 4.43E-07 1.60E-06 5.61E-07 1.76E-07 5.88E-08 4.64E-06 2.14E-06 1.46E-03

Ce-146 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 0.00E+00

Pr-146 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 0.00E+00

Ce-147 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 0.00E+00

Pr-147 2.89E-06 7.69E-06 2.46E-05 2.93E-06 1.15E-06 1.52E-05 4.49E-07 1.09E-06 1.58E-07 6.27E-06 2.00E-06 1.21E-04

Nd-147 6.72E-05 6.56E-04 6.79E-05 1.13E-04 2.04E-05 5.15E-05 5.14E-05 3.63E-06 8.00E-07 2.69E-04 1.87E-04 3.98E-03

Pm-147 1.12E-08 3.36E-08 1.21E-08 1.29E-04 9.15E-09 1.05E-08 1.01E-08 8.70E-09 8.54E-09 1.90E-08 9.66E-08 9.67E-04

Pr-148 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 0.00E+00

Pm-148 2.19E-04 1.83E-03 2.37E-04 3.50E-04 8.55E-05 1.84E-04 1.79E-04 2.10E-05 5.75E-06 8.14E-04 5.64E-04 9.92E-03

Pm-148m 9.37E-04 8.07E-03 9.78E-04 1.55E-03 3.39E-04 7.53E-04 8.11E-04 7.93E-05 2.19E-05 3.59E-03 2.51E-03 6.53E-03

A-4
Table A-1. Ingestion dose conversion factors 

based on ICRP-72. 

Ingestion Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S W all SI W all ULI W all LLI Wall Kidneys Liver ET Region Lung

Pm-149 2.09E-06 5.07E-06 4.91E-08 3.71E-07 1.55E-03 3.69E-03 1.89E-02 4.23E-02 4.73E-06 9.42E-06 8.64E-08 5.81E-07

Pm-151 5.12E-05 8.00E-05 2.20E-07 8.53E-06 1.55E-03 3.64E-03 1.45E-02 2.60E-02 1.15E-04 8.08E-05 1.19E-06 1.39E-05

Sm-151 9.15E-09 2.13E-03 4.02E-09 3.19E-09 8.45E-05 2.11E-04 1.28E-03 3.76E-03 5.22E-09 5.68E-04 2.88E-09 7.11E-09

Eu-152 1.19E-03 4.26E-03 1.80E-04 2.64E-04 2.15E-03 5.79E-03 1.56E-02 3.74E-02 1.22E-03 5.86E-03 1.58E-04 5.20E-04

Sm-153 9.58E-06 4.83E-05 4.58E-08 8.87E-07 1.23E-03 2.96E-03 1.41E-02 3.02E-02 2.52E-05 2.22E-05 8.64E-08 2.11E-06

Eu-154 1.10E-03 8.61E-03 1.60E-04 2.48E-04 2.84E-03 7.56E-03 2.57E-02 6.67E-02 1.21E-03 7.15E-03 1.44E-04 4.74E-04

Eu-155 4.90E-05 2.46E-03 5.80E-06 6.93E-06 3.69E-04 1.00E-03 4.58E-03 1.29E-02 6.29E-05 7.81E-04 4.38E-06 2.05E-05

Eu-156 3.00E-04 4.33E-04 4.95E-06 7.26E-05 3.08E-03 8.39E-03 3.26E-02 8.44E-02 6.61E-04 5.07E-04 1.64E-05 1.02E-04

Tb-160 2.88E-04 8.44E-04 9.50E-06 6.37E-05 2.30E-03 6.49E-03 2.23E-02 5.80E-02 6.19E-04 5.59E-04 1.67E-05 9.49E-05

Ho-166m 3.30E-03 1.46E-02 4.64E-04 6.42E-04 3.93E-03 8.62E-03 1.92E-02 4.25E-02 2.79E-03 1.25E-02 4.04E-04 1.34E-03

Be-7 1.49E-05 2.21E-05 2.56E-06 3.26E-06 5.65E-05 1.78E-04 2.65E-04 4.74E-04 2.94E-05 1.91E-05 2.23E-06 5.26E-06

Na-24 1.28E-03 2.01E-03 9.26E-04 8.26E-04 4.41E-03 1.29E-03 1.45E-03 1.56E-03 1.17E-03 1.10E-03 1.03E-03 9.97E-04

Mn-54 1.77E-03 2.62E-03 6.16E-04 5.55E-04 1.62E-03 3.61E-03 5.38E-03 9.04E-03 1.56E-03 3.89E-03 6.05E-04 9.30E-04

Fe-55 3.17E-04 2.21E-03 3.17E-04 3.17E-04 3.42E-04 3.74E-04 6.64E-04 1.33E-03 3.17E-04 2.71E-03 3.17E-04 3.17E-04

Fe-59 3.90E-03 3.96E-03 1.68E-03 1.83E-03 4.11E-03 7.12E-03 1.47E-02 3.09E-02 3.63E-03 1.12E-02 2.02E-03 2.54E-03

Co-57 2.89E-04 4.34E-04 1.70E-04 1.50E-04 4.43E-04 9.05E-04 2.19E-03 5.20E-03 2.97E-04 6.13E-04 1.99E-04 2.18E-04

Co-58 8.58E-04 8.06E-04 3.80E-04 4.01E-04 1.65E-03 3.91E-03 7.27E-03 1.48E-02 1.05E-03 1.48E-03 4.81E-04 5.49E-04

Co-60 9.15E-03 7.61E-03 5.05E-03 5.00E-03 9.51E-03 1.56E-02 2.42E-02 4.31E-02 8.84E-03 1.66E-02 6.33E-03 6.61E-03

Cu-64 6.24E-05 5.69E-05 1.42E-04 4.06E-05 6.44E-04 7.57E-04 2.29E-03 2.79E-03 7.26E-05 1.37E-04 4.38E-05 4.69E-05

Cu-67 2.58E-04 2.95E-04 1.03E-03 2.03E-04 9.66E-04 1.22E-03 4.87E-03 1.07E-02 2.62E-04 8.41E-04 2.24E-04 2.27E-04

W-181 3.74E-05 2.39E-04 1.49E-05 6.70E-06 1.25E-04 3.02E-04 9.78E-04 2.51E-03 2.76E-04 7.93E-05 9.66E-06 1.57E-05

W-185 1.02E-05 5.46E-04 1.02E-05 1.02E-05 5.51E-04 9.56E-04 6.90E-03 2.00E-02 1.47E-03 2.61E-04 1.02E-05 1.02E-05

W-187 9.73E-05 2.53E-04 2.79E-05 3.80E-05 1.68E-03 2.93E-03 1.21E-02 2.01E-02 3.21E-04 1.53E-04 3.14E-05 4.84E-05

W-188 6.09E-05 3.55E-03 4.06E-05 3.64E-05 6.21E-04 1.69E-03 2.55E-02 1.06E-01 9.70E-03 1.72E-03 3.80E-05 4.23E-05

Au-198 1.46E-04 1.75E-04 6.38E-05 7.37E-05 1.82E-03 4.12E-03 1.76E-02 3.96E-02 2.37E-04 1.80E-04 7.01E-05 8.75E-05

Au-199 4.54E-05 7.43E-05 2.66E-05 2.74E-05 7.25E-04 1.62E-03 7.58E-03 1.78E-02 6.73E-05 5.33E-05 2.79E-05 3.14E-05

Pb-203 1.52E-04 3.81E-04 4.82E-05 4.91E-05 5.64E-04 1.27E-03 3.47E-03 6.62E-03 5.52E-04 3.41E-04 5.42E-05 7.67E-05

Th-229 2.80E-01 8.35E+01 2.80E-01 2.79E-01 2.84E-01 2.92E-01 3.55E-01 5.17E-01 1.17E+00 4.04E+00 2.80E-01 2.80E-01

Th-230 5.03E-02 4.54E+01 5.03E-02 5.03E-02 5.44E-02 6.04E-02 1.12E-01 2.30E-01 6.85E-01 5.89E-01 5.03E-02 5.03E-02

Th-234 7.85E-06 1.75E-04 2.41E-06 3.27E-06 3.69E-03 9.44E-03 5.60E-02 1.60E-01 7.01E-05 2.93E-05 2.52E-06 3.86E-06

U-233 1.05E-01 3.10E+00 1.05E-01 1.05E-01 1.09E-01 1.15E-01 1.67E-01 2.85E-01 1.08E+00 4.10E-01 1.05E-01 1.05E-01

U-234 1.02E-01 2.91E+00 1.02E-01 1.02E-01 1.06E-01 1.12E-01 1.63E-01 2.82E-01 1.06E+00 3.98E-01 1.02E-01 1.02E-01

U-235 9.50E-02 2.74E+00 9.49E-02 9.47E-02 9.90E-02 1.05E-01 1.59E-01 2.88E-01 9.83E-01 3.69E-01 9.48E-02 9.48E-02

U-237 3.67E-05 3.89E-04 3.50E-06 6.10E-06 1.01E-03 2.58E-03 1.25E-02 3.23E-02 5.18E-04 5.89E-05 3.67E-06 1.02E-05

U-238 9.08E-02 2.63E+00 9.08E-02 9.08E-02 9.44E-02 9.97E-02 1.46E-01 2.56E-01 9.40E-01 3.54E-01 9.08E-02 9.08E-02

U-240 4.08E-05 1.64E-04 2.14E-06 9.59E-06 3.14E-03 7.38E-03 2.63E-02 3.50E-02 2.78E-04 7.55E-05 3.16E-06 1.37E-05

Np-237 2.66E-02 2.01E+01 2.65E-02 2.64E-02 3.09E-02 3.76E-02 9.34E-02 2.23E-01 7.17E-02 3.20E-01 2.65E-02 2.65E-02

Np-239 3.33E-05 9.50E-05 1.90E-07 4.04E-06 1.28E-03 3.15E-03 1.45E-02 3.22E-02 7.75E-05 5.07E-05 5.28E-07 7.69E-06

Np-240 3.10E-05 1.38E-05 1.81E-07 7.06E-06 1.71E-03 1.13E-03 8.51E-04 1.88E-04 4.28E-05 2.64E-05 7.99E-07 1.11E-05

Pu-238 4.77E-02 2.74E+01 4.77E-02 4.77E-02 5.25E-02 5.96E-02 1.19E-01 2.58E-01 1.18E-01 5.77E+00 4.77E-02 4.77E-02

Pu-239 5.37E-02 3.05E+01 5.37E-02 5.37E-02 5.81E-02 6.47E-02 1.21E-01 2.50E-01 1.25E-01 6.39E+00 5.37E-02 5.37E-02

Pu-240 5.37E-02 3.05E+01 5.37E-02 5.37E-02 5.81E-02 6.48E-02 1.21E-01 2.51E-01 1.25E-01 6.39E+00 5.37E-02 5.37E-02

Pu-241 1.10E-03 6.06E-01 1.10E-03 1.10E-03 1.12E-03 1.16E-03 1.44E-03 2.10E-03 1.84E-03 1.26E-01 1.10E-03 1.10E-03

Am-241 5.67E-02 3.34E+01 5.67E-02 5.67E-02 6.16E-02 6.91E-02 1.31E-01 2.75E-01 1.71E-01 2.05E+00 5.67E-02 5.67E-02

Cm-242 8.53E-04 6.87E-01 8.53E-04 8.53E-04 6.11E-03 1.40E-02 8.01E-02 2.32E-01 1.48E-02 1.91E-01 8.53E-04 8.53E-04

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Pm-149 3.70E-06 3.09E-05 4.37E-06 7.71E-06 1.25E-06 3.30E-06 2.80E-06 2.87E-07 8.64E-08 1.49E-05 1.01E-05 3.68E-03

Pm-151 8.67E-05 7.36E-04 1.13E-04 1.35E-04 2.84E-05 8.24E-05 5.99E-05 6.22E-06 1.19E-06 3.55E-04 2.20E-04 2.71E-03

Sm-151 6.79E-09 5.92E-08 6.07E-09 1.70E-04 3.61E-09 3.22E-09 2.91E-09 3.13E-09 2.88E-09 6.09E-09 8.49E-08 3.63E-04

Eu-152 7.88E-04 4.93E-03 1.22E-03 2.20E-03 3.60E-04 6.52E-04 5.09E-04 2.57E-04 1.58E-04 2.21E-03 1.55E-03 5.06E-03

Sm-153 2.45E-05 2.68E-04 2.77E-05 3.50E-05 5.79E-06 1.93E-05 1.36E-05 5.46E-07 8.64E-08 1.06E-04 6.71E-05 2.75E-03

Eu-154 7.93E-04 5.13E-03 1.17E-03 2.69E-03 3.60E-04 6.59E-04 5.37E-04 2.39E-04 1.44E-04 2.31E-03 1.62E-03 7.56E-03

Eu-155 4.35E-05 3.66E-04 6.25E-05 2.61E-04 1.31E-05 3.34E-05 2.53E-05 7.14E-06 4.38E-06 1.60E-04 1.11E-04 1.20E-03

Eu-156 5.45E-04 4.54E-03 5.68E-04 8.51E-04 2.17E-04 4.50E-04 4.49E-04 5.51E-05 1.64E-05 1.98E-03 1.41E-03 8.13E-03

Tb-160 5.18E-04 4.42E-03 5.42E-04 8.80E-04 1.96E-04 4.15E-04 4.28E-04 4.96E-05 1.67E-05 1.94E-03 1.36E-03 5.95E-03

Ho-166m 1.55E-03 7.98E-03 1.68E-02 4.30E-03 7.25E-04 1.87E-03 8.97E-04 6.36E-04 4.04E-04 3.78E-03 2.62E-03 7.33E-03

Be-7 2.52E-05 2.05E-04 2.58E-05 4.35E-05 9.38E-06 2.04E-05 2.19E-05 3.11E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Na-24 1.02E-03 1.23E-03 1.49E-03 1.47E-03 7.89E-04 1.26E-03 9.59E-04 1.01E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Mn-54 1.05E-03 4.02E-03 1.60E-03 2.29E-03 5.93E-04 9.79E-04 7.42E-04 6.64E-04 2.23E-06 9.31E-05 6.58E-05 1.03E-04

Fe-55 3.17E-04 3.17E-04 3.17E-04 4.19E-03 3.17E-04 9.36E-03 3.17E-04 3.17E-04 1.03E-03 1.21E-03 1.56E-03 1.61E-03

Fe-59 2.59E-03 6.49E-03 3.98E-03 5.80E-03 1.72E-03 7.26E-03 2.20E-03 2.25E-03 6.05E-04 2.12E-03 1.58E-03 2.67E-03

Co-57 2.41E-04 7.50E-04 3.28E-04 2.84E-04 1.52E-04 2.60E-04 2.19E-04 1.95E-04 3.17E-04 3.17E-04 3.17E-04 1.23E-03

Co-58 8.64E-04 4.11E-03 1.08E-03 1.15E-03 4.68E-04 8.50E-04 7.96E-04 5.04E-04 2.02E-03 4.19E-03 3.31E-03 6.62E-03

Co-60 7.12E-03 1.59E-02 9.65E-03 7.99E-03 4.75E-03 7.73E-03 6.73E-03 6.41E-03 1.99E-04 4.88E-04 4.28E-04 7.80E-04

Cu-64 5.91E-05 1.77E-04 1.56E-04 7.09E-05 4.30E-05 6.89E-05 5.15E-05 4.44E-05 4.81E-04 2.15E-03 1.73E-03 2.77E-03

Cu-67 2.38E-04 4.26E-04 8.88E-04 2.59E-04 2.05E-04 2.51E-04 2.27E-04 2.19E-04 6.33E-03 1.13E-02 9.62E-03 1.26E-02

W-181 3.29E-05 2.43E-04 4.79E-05 8.58E-05 1.16E-05 2.43E-04 1.89E-05 8.40E-06 4.38E-05 1.14E-04 8.45E-05 4.50E-04

W-185 1.02E-05 1.04E-05 1.02E-05 1.87E-04 1.02E-05 1.27E-03 1.02E-05 1.02E-05 2.24E-04 3.29E-04 3.25E-04 1.26E-03

W-187 1.27E-04 8.26E-04 1.75E-04 2.03E-04 5.93E-05 2.68E-04 9.97E-05 3.83E-05 9.66E-06 1.05E-04 1.17E-04 2.88E-04

W-188 5.46E-05 1.77E-04 6.24E-05 1.22E-03 4.12E-05 8.36E-03 4.88E-05 3.76E-05 1.02E-05 1.03E-05 3.39E-04 1.64E-03

Au-198 1.99E-04 1.19E-03 2.30E-04 2.82E-04 1.04E-04 1.88E-04 1.73E-04 7.78E-05 3.14E-05 4.20E-04 8.72E-04 2.33E-03

Au-199 5.91E-05 3.12E-04 6.71E-05 7.65E-05 3.44E-05 5.68E-05 4.98E-05 2.90E-05 3.80E-05 9.64E-05 1.21E-03 7.72E-03

Pb-203 1.46E-04 8.64E-04 2.07E-04 2.52E-04 6.59E-05 1.56E-04 1.10E-04 6.01E-05 7.01E-05 6.06E-04 7.15E-04 3.82E-03

Th-229 2.80E-01 7.04E-01 2.80E-01 4.00E+00 2.79E-01 2.80E-01 7.13E-01 2.80E-01 2.79E-05 1.69E-04 2.55E-04 1.63E-03

Th-230 5.03E-02 3.66E-01 5.03E-02 1.56E+00 5.03E-02 5.03E-02 3.73E-01 5.03E-02 5.42E-05 4.48E-04 3.23E-04 9.14E-04

Th-234 1.43E-05 1.22E-04 1.40E-05 1.08E-04 6.22E-06 1.14E-05 1.71E-05 3.03E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-233 1.05E-01 1.06E-01 1.05E-01 3.11E-01 1.05E-01 1.05E-01 1.06E-01 1.05E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-234 1.02E-01 1.02E-01 1.02E-01 3.00E-01 1.02E-01 1.02E-01 1.02E-01 1.02E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-235 9.49E-02 9.56E-02 9.49E-02 2.81E-01 9.47E-02 9.49E-02 9.48E-02 9.48E-02 2.80E-01 2.80E-01 2.80E-01 1.85E+00

U-237 6.72E-05 6.17E-04 7.38E-05 1.37E-04 2.05E-05 5.80E-05 4.75E-05 5.56E-06 5.03E-02 5.03E-02 5.03E-02 7.91E-01

U-238 9.08E-02 9.08E-02 9.08E-02 2.76E-01 9.08E-02 9.08E-02 9.08E-02 9.08E-02 2.52E-06 5.01E-05 3.67E-05 1.26E-02

U-240 5.83E-05 4.58E-04 8.48E-05 1.05E-04 2.21E-05 6.06E-05 3.84E-05 7.52E-06 1.05E-01 1.05E-01 1.05E-01 1.90E-01

Np-237 2.65E-02 2.68E-01 2.65E-02 7.70E-01 2.64E-02 2.65E-02 2.73E-01 2.64E-02 1.02E-01 1.02E-01 1.03E-01 1.83E-01

Np-239 6.16E-05 5.51E-04 7.33E-05 9.59E-05 1.82E-05 5.57E-05 4.30E-05 2.95E-06 9.48E-02 9.51E-02 9.54E-02 1.73E-01

Np-240 2.08E-05 1.04E-04 1.01E-04 2.67E-05 7.92E-06 6.43E-05 5.23E-06 5.09E-06 3.67E-06 2.75E-04 2.44E-04 2.81E-03

Pu-238 4.77E-02 3.59E-01 4.77E-02 1.35E+00 4.77E-02 4.77E-02 3.66E-01 4.77E-02 9.08E-02 9.08E-02 9.11E-02 1.65E-01

Pu-239 5.37E-02 3.99E-01 5.37E-02 1.45E+00 5.37E-02 5.37E-02 4.06E-01 5.37E-02 3.16E-06 2.25E-04 2.47E-04 4.12E-03

Pu-240 5.37E-02 3.99E-01 5.37E-02 1.45E+00 5.37E-02 5.37E-02 4.06E-01 5.37E-02 2.65E-02 2.65E-02 2.65E-02 3.96E-01

Pu-241 1.10E-03 7.96E-03 1.10E-03 2.38E-02 1.10E-03 1.10E-03 8.11E-03 1.10E-03 5.28E-07 2.60E-04 1.74E-04 2.95E-03

Am-241 5.67E-02 6.48E-01 5.67E-02 1.14E+00 5.67E-02 5.67E-02 6.42E-01 5.67E-02 7.99E-07 8.00E-05 2.48E-05 3.04E-04

Cm-242 8.54E-04 1.22E-02 8.53E-04 4.88E-02 8.53E-04 8.53E-04 1.20E-02 8.53E-04 4.77E-02 4.77E-02 4.77E-02 8.44E-01

A-5
 Table A-2. Inhalation dose conversion factors 

based on ICRP-72. 

 Inhalation Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Se-79 5.55E-04 5.55E-04 5.55E-04 5.55E-04 6.66E-04 7.77E-04 1.96E-03 4.81E-03 1.89E-02 8.14E-03 2.11E-02 7.40E-02

Br-82 9.62E-04 9.25E-04 7.77E-04 7.77E-04 1.33E-03 9.99E-04 1.26E-03 1.55E-03 8.14E-04 8.88E-04 5.55E-02 1.07E-02

Br-83 1.48E-05 1.48E-05 1.48E-05 1.48E-05 3.70E-04 2.00E-05 2.41E-05 1.81E-05 1.48E-05 1.48E-05 3.18E-03 1.15E-03

Kr-83m 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 0.00E+00

Br-84 1.78E-05 1.85E-05 1.85E-05 1.55E-05 7.03E-04 2.59E-05 2.00E-05 1.52E-05 1.67E-05 1.63E-05 3.55E-03 4.44E-04

Br-85 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 0.00E+00

Kr-85 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 0.00E+00

Kr-85m 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 0.00E+00

Rb-86 4.07E-03 1.48E-02 4.07E-03 3.70E-03 4.44E-03 4.07E-03 5.55E-03 8.51E-03 4.07E-03 4.07E-03 1.37E-02 4.07E-03

Kr-87 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 0.00E+00

Rb-87 2.07E-03 8.14E-03 2.07E-03 2.07E-03 2.18E-03 2.07E-03 2.96E-03 4.81E-03 2.07E-03 2.07E-03 8.88E-03 2.18E-03

Kr-88 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 0.00E+00

Rb-88 8.51E-06 9.62E-06 8.88E-06 8.14E-06 4.07E-04 1.74E-05 9.99E-06 8.14E-06 8.51E-06 8.14E-06 1.33E-03 1.22E-04

Kr-89 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 0.00E+00

Rb-89 8.88E-06 1.33E-05 9.62E-06 7.77E-06 2.00E-04 1.15E-05 9.25E-06 8.51E-06 8.14E-06 7.77E-06 2.00E-03 9.62E-05

Sr-89 8.51E-04 2.59E-02 8.51E-04 8.51E-04 1.33E-03 1.67E-03 8.14E-03 2.18E-02 8.51E-04 8.51E-04 8.51E-03 9.62E-04

Rb-90 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 0.00E+00

Rb-90m 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 0.00E+00

Sr-90 2.89E-03 1.78E+00 2.89E-03 2.89E-03 3.03E-03 3.18E-03 9.99E-03 2.85E-02 2.89E-03 2.89E-03 1.15E-02 3.00E-03

Y-90 1.89E-07 5.55E-06 1.89E-07 1.89E-07 1.59E-03 3.70E-03 2.04E-02 4.81E-02 1.89E-07 5.55E-06 8.14E-03 2.89E-02

Rb-91 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 0.00E+00

Sr-91 1.37E-04 6.66E-04 1.37E-04 1.04E-04 7.03E-04 1.04E-03 3.07E-03 3.26E-03 1.41E-04 1.26E-04 1.41E-02 2.52E-04

Y-91 1.78E-05 2.33E-04 5.92E-06 1.92E-05 1.11E-03 2.78E-03 1.67E-02 4.81E-02 9.99E-06 2.37E-04 2.37E-02 2.55E-01

Y-91m 5.18E-06 4.07E-06 3.63E-06 3.33E-06 5.92E-05 2.81E-05 3.63E-05 3.59E-05 5.18E-06 4.44E-06 9.99E-04 1.85E-04

Sr-92 7.77E-05 4.44E-04 7.77E-05 6.29E-05 4.44E-04 8.14E-04 2.44E-03 1.74E-03 8.14E-05 7.40E-05 8.51E-03 1.85E-04

Y-92 8.14E-06 7.40E-06 5.55E-06 5.92E-06 2.00E-03 2.78E-03 4.81E-03 2.37E-03 9.62E-06 8.51E-06 4.81E-03 2.59E-03

Sr-93 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 0.00E+00

Y-93 6.29E-06 7.03E-06 4.07E-06 4.81E-06 1.85E-03 3.66E-03 1.15E-02 1.26E-02 7.77E-06 7.77E-06 5.55E-03 5.92E-03

Zr-93 5.55E-05 1.85E+00 7.77E-05 2.74E-05 4.44E-05 1.11E-04 5.55E-04 1.63E-03 2.18E-05 1.85E-05 3.55E-03 1.07E-02

Nb-93m 3.70E-05 2.00E-04 1.74E-05 3.70E-05 8.14E-05 1.59E-04 8.88E-04 2.59E-03 2.70E-04 3.66E-04 1.52E-02 5.18E-02

Y-94 3.70E-06 3.22E-06 3.29E-06 2.85E-06 5.92E-04 1.52E-04 3.70E-05 4.44E-06 3.26E-06 2.81E-06 2.44E-03 3.07E-04

Y-95 1.96E-06 1.55E-06 1.52E-06 1.81E-06 2.78E-04 4.07E-05 7.03E-06 2.33E-06 1.26E-06 1.52E-06 1.63E-03 1.89E-04

Zr-95 5.55E-03 4.81E-02 1.41E-03 4.44E-03 2.85E-03 2.92E-03 5.92E-03 1.30E-02 2.55E-03 3.70E-03 4.07E-02 1.18E-01

Nb-95 2.04E-03 1.04E-03 2.04E-04 2.15E-03 1.26E-03 1.41E-03 3.00E-03 6.29E-03 8.14E-04 1.81E-03 2.85E-02 4.44E-02

Y-96 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 0.00E+00

Zr-97 1.81E-04 3.15E-04 1.15E-04 1.41E-04 1.85E-03 4.81E-03 1.74E-02 2.48E-02 2.07E-04 2.00E-04 3.07E-02 1.33E-02

Nb-97 8.88E-06 7.03E-06 5.92E-06 5.92E-06 4.81E-04 3.59E-04 2.74E-04 5.92E-05 9.25E-06 7.77E-06 4.07E-03 7.40E-04

Nb-97m 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 0.00E+00

Nb-98m 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 0.00E+00

Mo-99 8.51E-05 9.25E-05 2.66E-05 7.77E-05 7.77E-04 1.92E-03 9.25E-03 2.15E-02 1.04E-04 1.18E-04 1.48E-02 2.41E-02

Tc-99 3.59E-05 3.59E-05 3.59E-05 3.59E-05 2.07E-03 4.44E-04 2.81E-03 8.14E-03 3.59E-05 4.81E-05 2.92E-02 1.26E-01

Tc-99m 7.03E-06 1.26E-05 4.44E-06 4.44E-06 5.92E-05 7.77E-05 1.55E-04 1.07E-04 8.88E-06 7.77E-06 1.63E-03 3.44E-04

Mo-101 4.44E-06 4.07E-06 4.07E-06 3.33E-06 3.29E-04 8.88E-05 2.44E-05 4.07E-06 3.70E-06 3.33E-06 3.29E-03 3.66E-04

Tc-101 9.99E-07 1.04E-06 9.25E-07 7.40E-07 1.22E-04 2.33E-05 4.81E-06 7.77E-07 8.51E-07 7.77E-07 1.70E-03 1.63E-04

Mo-102 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 0.00E+00

Tc-102 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 0.00E+00

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Se-79 5.55E-04 1.04E-03 2.89E-03 5.55E-04 5.55E-04 3.22E-03 1.67E-03 5.55E-04 5.55E-04 5.55E-04 6.29E-04 1.04E-02

Br-82 8.51E-04 1.04E-03 9.99E-04 8.88E-04 5.55E-04 8.88E-04 7.03E-04 1.11E-03 9.25E-04 9.62E-04 9.62E-04 3.29E-03

Br-83 1.48E-05 1.48E-05 1.52E-05 1.48E-05 1.48E-05 1.48E-05 1.48E-05 1.48E-05 1.48E-05 1.48E-05 1.70E-05 2.59E-04

Kr-83m 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 0.00E+00

Br-84 1.89E-05 1.52E-05 2.70E-05 1.78E-05 1.44E-05 2.11E-05 1.30E-05 2.15E-05 1.96E-05 1.52E-05 1.41E-05 2.26E-04

Br-85 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 0.00E+00

Kr-85 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 0.00E+00

Kr-85m 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 0.00E+00

Rb-86 4.07E-03 4.07E-03 4.07E-03 7.40E-03 3.70E-03 4.07E-03 4.07E-03 4.07E-03 4.07E-03 4.07E-03 5.18E-03 4.81E-03

Kr-87 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 0.00E+00

Rb-87 2.07E-03 2.07E-03 2.07E-03 4.07E-03 2.07E-03 2.07E-03 2.07E-03 2.07E-03 2.07E-03 2.07E-03 2.78E-03 2.81E-03

Kr-88 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 0.00E+00

Rb-88 8.88E-06 8.14E-06 1.04E-05 8.88E-06 8.14E-06 9.25E-06 7.77E-06 9.62E-06 9.25E-06 8.14E-06 7.77E-06 1.04E-04

Kr-89 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 0.00E+00

Rb-89 9.62E-06 7.03E-06 1.44E-05 1.04E-05 7.03E-06 1.11E-05 5.92E-06 1.18E-05 1.04E-05 7.03E-06 6.66E-06 8.88E-05

Sr-89 8.51E-04 8.51E-04 8.51E-04 2.07E-02 8.51E-04 8.51E-04 8.51E-04 8.51E-04 8.51E-04 8.51E-04 2.92E-03 5.18E-03

Rb-90 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 0.00E+00

Rb-90m 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 0.00E+00

Sr-90 2.89E-03 2.89E-03 2.89E-03 7.77E-01 2.89E-03 2.89E-03 2.89E-03 2.89E-03 2.89E-03 2.89E-03 6.29E-03 1.15E-01

Y-90 1.89E-07 1.92E-07 1.89E-07 5.55E-06 1.89E-07 1.89E-07 1.89E-07 1.89E-07 1.89E-07 1.89E-07 8.88E-07 7.03E-03

Rb-91 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 0.00E+00

Sr-91 1.48E-04 2.66E-04 1.48E-04 6.29E-04 1.07E-04 1.30E-04 1.07E-04 1.44E-04 1.41E-04 1.96E-04 7.40E-04 1.04E-03

Y-91 1.07E-05 9.99E-06 1.44E-05 2.37E-04 7.77E-06 1.48E-05 5.18E-06 2.15E-05 1.04E-05 7.03E-06 7.40E-06 3.29E-02

Y-91m 5.18E-06 9.62E-06 1.30E-05 5.55E-06 2.29E-06 8.51E-06 4.81E-07 5.92E-06 4.07E-06 7.77E-06 2.37E-06 5.55E-05

Sr-92 8.51E-05 1.26E-04 9.25E-05 3.00E-04 6.66E-05 8.14E-05 6.29E-05 8.88E-05 8.14E-05 1.07E-04 5.55E-04 6.66E-04

Y-92 9.62E-06 3.07E-05 1.48E-05 1.07E-05 4.44E-06 1.04E-05 2.04E-06 9.62E-06 6.29E-06 2.00E-05 8.14E-06 1.07E-03

Sr-93 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 0.00E+00

Y-93 8.14E-06 3.22E-05 9.25E-06 9.99E-06 3.63E-06 7.03E-06 2.63E-06 7.77E-06 4.81E-06 1.74E-05 9.62E-06 2.26E-03

Zr-93 4.81E-05 1.70E-05 1.26E-05 1.48E-01 4.07E-05 1.63E-05 8.51E-06 2.44E-05 1.37E-05 8.88E-06 4.07E-05 3.70E-02

Nb-93m 7.40E-05 2.11E-05 2.07E-05 7.40E-05 1.89E-05 4.07E-05 1.70E-05 2.22E-05 1.74E-05 1.74E-05 2.22E-05 6.66E-03

Y-94 4.07E-06 3.66E-06 9.99E-06 3.55E-06 1.92E-06 6.66E-06 2.66E-07 5.18E-06 3.63E-06 3.11E-06 9.99E-07 1.70E-04

Y-95 1.81E-06 1.04E-06 3.70E-06 1.63E-06 8.88E-07 2.66E-06 1.11E-07 2.92E-06 1.81E-06 8.51E-07 3.48E-07 9.62E-05

Zr-95 2.55E-03 2.66E-03 3.70E-03 8.88E-03 1.44E-03 3.44E-03 6.29E-04 5.18E-03 2.37E-03 1.59E-03 1.18E-03 1.85E-02

Nb-95 9.62E-04 1.33E-03 1.52E-03 1.26E-03 4.81E-04 1.48E-03 1.48E-04 2.48E-03 8.51E-04 6.29E-04 4.44E-04 6.66E-03

Y-96 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 0.00E+00

Zr-97 2.26E-04 8.88E-04 2.29E-04 4.07E-04 1.07E-04 1.85E-04 9.99E-05 2.15E-04 1.37E-04 4.44E-04 2.96E-04 5.18E-03

Nb-97 9.25E-06 2.04E-05 2.04E-05 9.62E-06 4.07E-06 1.37E-05 1.11E-06 9.99E-06 6.66E-06 1.55E-05 4.81E-06 2.70E-04

Nb-97m 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 0.00E+00

Nb-98m 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 0.00E+00

Mo-99 7.40E-05 3.15E-04 8.14E-05 9.99E-05 3.18E-05 7.40E-05 3.22E-05 1.04E-04 4.44E-05 1.48E-04 1.07E-04 4.81E-03

Tc-99 3.59E-05 3.59E-05 3.59E-05 3.59E-05 3.59E-05 3.59E-05 3.59E-05 3.59E-05 9.25E-04 3.59E-05 1.48E-04 1.59E-02

Tc-99m 8.88E-06 3.11E-05 1.30E-05 9.99E-06 3.33E-06 9.25E-06 2.29E-06 8.51E-06 2.96E-05 2.00E-05 1.04E-05 1.11E-04

Mo-101 4.81E-06 4.07E-06 1.22E-05 4.07E-06 2.26E-06 8.14E-06 2.74E-07 6.29E-06 4.44E-06 3.52E-06 1.15E-06 1.67E-04

Tc-101 1.11E-06 8.14E-07 2.59E-06 9.62E-07 5.18E-07 1.74E-06 1.55E-07 1.33E-06 5.55E-06 7.03E-07 3.29E-07 7.77E-05

Mo-102 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 0.00E+00

Tc-102 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 0.00E+00

A-6
Table A-2. Inhalation dose conversion factors 

based on ICRP-72. 

Inhalation Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Tc-103 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 0.00E+00

Ru-103 1.48E-03 6.29E-04 1.33E-04 1.48E-03 9.62E-04 1.30E-03 4.07E-03 1.07E-02 5.18E-04 1.22E-03 2.89E-02 8.14E-02

Rh-103m 7.77E-09 1.81E-08 4.81E-09 7.40E-09 3.15E-05 1.92E-05 1.11E-05 1.74E-06 6.29E-09 1.15E-08 3.40E-05 6.66E-05

Tc-104 6.66E-06 5.92E-06 5.92E-06 5.18E-06 5.55E-04 1.30E-04 3.55E-05 6.29E-06 5.92E-06 5.18E-06 2.85E-03 2.78E-04

Mo-105 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 0.00E+00

Tc-105 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 0.00E+00

Ru-105 3.29E-05 3.18E-05 2.15E-05 2.33E-05 7.03E-04 1.07E-03 2.33E-03 1.96E-03 4.07E-05 3.55E-05 9.25E-03 3.37E-03

Rh-105 1.92E-05 1.96E-05 1.07E-05 1.59E-05 2.92E-04 6.66E-04 2.89E-03 5.55E-03 1.85E-05 1.96E-05 7.77E-03 9.62E-03

Rh-105m 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 0.00E+00

Ru-106 4.07E-03 2.00E-03 9.25E-04 4.07E-03 4.81E-03 7.77E-03 4.07E-02 1.22E-01 1.74E-03 3.40E-03 8.14E-02 1.96E+00

Rh-106 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 0.00E+00

Pd-107 1.07E-07 1.59E-06 1.07E-07 1.07E-07 1.89E-05 4.81E-05 2.85E-04 8.51E-04 7.03E-05 3.70E-05 4.81E-04 1.78E-02

Rh-109 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 0.00E+00

Pd-109 8.51E-07 3.15E-06 3.70E-07 7.40E-07 7.03E-04 1.48E-03 5.18E-03 7.03E-03 1.18E-05 6.66E-06 9.25E-03 9.25E-03

Ag-109m 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 0.00E+00

Ag-110m 3.29E-02 1.33E-02 2.70E-03 3.52E-02 1.81E-02 7.40E-03 1.18E-02 1.92E-02 1.22E-02 3.03E-02 1.18E-01 2.63E-01

Ag-111 2.37E-05 1.74E-05 8.88E-06 2.29E-05 6.29E-04 1.55E-03 8.88E-03 2.33E-02 1.55E-05 2.07E-04 1.15E-02 4.81E-02

Cd-113m 7.77E-03 7.77E-03 7.77E-03 7.77E-03 8.14E-03 8.88E-03 1.33E-02 2.33E-02 1.26E+00 2.18E-01 1.55E-01 6.29E-01

Cd-115m 3.29E-04 2.92E-04 2.74E-04 3.11E-04 1.41E-03 2.92E-03 1.59E-02 4.44E-02 4.07E-02 7.40E-03 2.11E-02 2.15E-01

Sn-123 4.44E-04 8.88E-03 4.07E-04 4.44E-04 1.26E-03 2.59E-03 1.44E-02 4.07E-02 4.07E-04 4.44E-04 2.41E-02 2.29E-01

Sb-124 5.18E-03 7.03E-03 8.51E-04 5.18E-03 3.63E-03 4.44E-03 1.44E-02 3.59E-02 2.29E-03 4.81E-03 6.66E-02 1.63E-01

Sn-125 3.40E-04 2.37E-03 1.30E-04 3.26E-04 1.63E-03 3.70E-03 2.04E-02 5.55E-02 2.15E-04 2.92E-04 1.85E-02 7.40E-02

Sb-125 4.44E-03 3.22E-02 1.07E-03 3.70E-03 2.55E-03 2.22E-03 4.81E-03 1.07E-02 2.04E-03 5.18E-03 4.07E-02 1.18E-01

Te-125m 1.78E-04 2.18E-02 7.40E-05 1.85E-04 3.00E-04 5.92E-04 2.92E-03 8.14E-03 8.88E-04 1.92E-04 2.29E-02 1.07E-01

Sn-126 2.96E-02 1.04E-01 1.41E-02 2.33E-02 1.78E-02 1.78E-02 3.66E-02 8.14E-02 1.70E-02 2.26E-02 1.41E-01 6.66E-01

Sb-126 2.92E-03 2.59E-03 5.92E-04 2.85E-03 2.74E-03 5.18E-03 1.30E-02 2.89E-02 1.44E-03 2.66E-03 8.88E-02 6.29E-02

Sb-127 2.96E-04 5.18E-04 1.11E-04 2.78E-04 9.25E-04 2.29E-03 1.07E-02 2.85E-02 2.18E-04 3.55E-04 3.00E-02 4.44E-02

Te-127 4.07E-06 9.62E-06 4.07E-06 4.07E-06 3.33E-04 5.92E-04 1.81E-03 1.89E-03 1.26E-05 4.44E-06 4.81E-03 3.26E-03

Te-127m 2.26E-04 3.70E-02 1.67E-04 2.15E-04 3.70E-04 7.77E-04 5.92E-03 2.00E-02 2.78E-03 2.15E-04 3.63E-02 2.18E-01

Sb-129 5.92E-05 7.77E-05 4.07E-05 4.44E-05 1.04E-03 1.92E-03 4.07E-03 2.59E-03 7.03E-05 6.66E-05 1.37E-02 3.63E-03

Te-129 1.63E-06 1.89E-06 1.41E-06 1.37E-06 4.81E-04 3.40E-04 2.33E-04 4.44E-05 1.92E-06 1.55E-06 2.66E-03 6.66E-04

Te-129m 3.66E-04 1.26E-02 2.33E-04 3.40E-04 1.04E-03 2.48E-03 1.48E-02 4.07E-02 3.55E-03 3.33E-04 2.63E-02 1.81E-01

I-129 2.22E-04 7.40E-04 2.59E-04 2.04E-04 2.66E-04 2.22E-04 4.07E-04 7.40E-04 2.15E-04 2.18E-04 5.18E-03 3.22E-04

Sn-130 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 0.00E+00

Sn-130m 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 0.00E+00

I-130 1.30E-04 2.11E-04 2.33E-04 1.18E-04 4.81E-04 1.41E-04 1.52E-04 1.81E-04 1.18E-04 1.22E-04 3.03E-02 3.00E-04

Sb-131 1.07E-05 1.04E-05 8.51E-06 7.77E-06 5.18E-04 2.33E-04 1.15E-04 5.55E-05 9.62E-06 8.51E-06 4.07E-03 6.29E-04

Te-131 2.89E-06 2.78E-06 2.11E-06 2.18E-06 3.22E-04 1.04E-04 4.07E-05 3.03E-05 2.44E-06 2.33E-06 2.63E-03 4.07E-04

Te-131m 3.07E-04 5.92E-04 1.63E-04 2.59E-04 1.07E-03 2.37E-03 7.77E-03 1.41E-02 4.07E-04 3.11E-04 3.70E-02 1.85E-02

I-131 9.25E-05 2.55E-04 3.00E-04 1.18E-04 2.66E-04 8.51E-05 1.15E-04 1.89E-04 8.14E-05 8.88E-05 1.74E-02 3.15E-04

Xe-131m 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 0.00E+00

Sb-132 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 0.00E+00

Sb-132m 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 0.00E+00

Te-132 8.88E-04 1.41E-03 3.70E-04 8.51E-04 1.41E-03 4.07E-03 1.52E-02 3.48E-02 7.77E-04 8.51E-04 6.29E-02 3.70E-02

I-132 5.92E-05 7.03E-05 7.03E-05 4.81E-05 4.81E-04 6.66E-05 6.66E-05 6.29E-05 5.55E-05 5.18E-05 9.99E-03 1.81E-04

Sb-133 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 0.00E+00

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Tc-103 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 0.00E+00

Ru-103 6.66E-04 8.88E-04 1.11E-03 8.51E-04 3.29E-04 1.04E-03 1.11E-04 1.78E-03 5.92E-04 4.07E-04 3.00E-04 1.15E-02

Rh-103m 3.40E-08 5.55E-08 4.07E-08 8.14E-09 6.29E-09 1.48E-08 4.44E-09 6.29E-09 4.81E-09 2.11E-08 1.18E-08 1.15E-05

Tc-104 7.03E-06 6.29E-06 1.67E-05 6.29E-06 3.66E-06 1.15E-05 1.04E-06 9.25E-06 3.26E-05 5.55E-06 2.41E-06 1.74E-04

Mo-105 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 0.00E+00

Tc-105 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 0.00E+00

Ru-105 4.07E-05 1.41E-04 5.92E-05 4.81E-05 1.70E-05 4.07E-05 9.62E-06 3.70E-05 2.52E-05 8.51E-05 3.70E-05 9.62E-04

Rh-105 2.11E-05 7.77E-05 2.18E-05 2.55E-05 1.07E-05 1.89E-05 1.11E-05 2.18E-05 1.33E-05 4.07E-05 3.22E-05 1.67E-03

Rh-105m 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 0.00E+00

Ru-106 2.04E-03 1.22E-03 3.07E-03 2.44E-03 1.37E-03 2.96E-03 8.14E-04 4.81E-03 2.00E-03 9.99E-04 1.04E-03 2.44E-01

Rh-106 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 0.00E+00

Pd-107 1.07E-07 1.07E-07 1.07E-07 5.92E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.07E-07 1.30E-06 2.18E-03

Rh-109 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 0.00E+00

Pd-109 2.07E-06 1.11E-05 1.33E-06 1.55E-06 4.81E-07 9.99E-07 3.55E-07 8.88E-07 4.44E-07 2.66E-06 2.85E-06 1.96E-03

Ag-109m 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 0.00E+00

Ag-110m 1.44E-02 6.29E-03 2.41E-02 1.81E-02 7.77E-03 2.37E-02 8.88E-04 4.07E-02 1.37E-02 3.37E-03 2.22E-03 4.44E-02

Ag-111 1.78E-05 4.81E-05 2.15E-05 2.15E-05 1.07E-05 1.96E-05 9.62E-06 2.78E-05 1.37E-05 2.48E-05 1.92E-05 7.40E-03

Cd-113m 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 7.77E-03 1.15E-01

Cd-115m 2.92E-04 3.07E-04 3.15E-04 3.00E-04 2.81E-04 3.15E-04 2.74E-04 3.22E-04 2.89E-04 2.89E-04 2.81E-04 2.85E-02

Sn-123 4.07E-04 4.07E-04 4.44E-04 3.18E-03 4.07E-04 4.44E-04 4.07E-04 4.44E-04 4.07E-04 4.07E-04 6.66E-04 3.00E-02

Sb-124 2.55E-03 3.26E-03 4.07E-03 4.44E-03 1.44E-03 3.70E-03 5.92E-04 6.29E-03 2.41E-03 1.70E-03 1.59E-03 2.41E-02

Sn-125 2.33E-04 5.18E-04 2.78E-04 1.52E-03 1.48E-04 2.66E-04 1.15E-04 3.70E-04 1.92E-04 2.74E-04 4.07E-04 1.26E-02

Sb-125 2.22E-03 1.89E-03 3.29E-03 6.29E-03 1.30E-03 3.00E-03 7.77E-04 4.44E-03 2.04E-03 1.33E-03 1.18E-03 1.78E-02

Te-125m 1.44E-04 2.07E-04 1.07E-04 1.89E-03 7.03E-05 1.44E-04 5.55E-05 1.55E-04 1.15E-03 7.77E-05 1.74E-04 1.41E-02

Sn-126 1.74E-02 1.52E-02 2.26E-02 5.18E-02 1.18E-02 2.07E-02 9.25E-03 2.78E-02 1.70E-02 1.26E-02 1.15E-02 1.04E-01

Sb-126 1.67E-03 4.44E-03 2.29E-03 2.59E-03 8.14E-04 2.15E-03 5.55E-04 3.40E-03 1.33E-03 2.15E-03 1.67E-03 1.37E-02

Sb-127 2.52E-04 9.25E-04 2.85E-04 5.55E-04 1.26E-04 2.48E-04 1.18E-04 3.40E-04 1.70E-04 4.44E-04 4.07E-04 7.77E-03

Te-127 4.44E-06 5.55E-06 4.44E-06 9.25E-06 4.07E-06 4.44E-06 4.07E-06 4.44E-06 1.55E-05 4.81E-06 3.03E-05 7.40E-04

Te-127m 1.96E-04 2.11E-04 1.89E-04 9.99E-03 1.59E-04 1.96E-04 1.48E-04 2.07E-04 3.70E-03 1.63E-04 4.44E-04 2.92E-02

Sb-129 7.03E-05 2.26E-04 9.99E-05 9.25E-05 3.44E-05 7.40E-05 2.07E-05 7.03E-05 4.81E-05 1.44E-04 9.25E-05 1.33E-03

Te-129 1.78E-06 2.74E-06 2.78E-06 1.85E-06 1.26E-06 2.11E-06 9.99E-07 1.74E-06 1.85E-06 2.26E-06 4.81E-06 2.15E-04

Te-129m 2.92E-04 3.63E-04 3.18E-04 5.55E-03 2.37E-04 3.15E-04 2.18E-04 3.63E-04 4.81E-03 2.66E-04 7.03E-04 2.59E-02

I-129 5.55E-04 2.29E-04 2.22E-04 2.55E-04 2.55E-04 2.18E-04 2.07E-04 3.15E-04 3.70E+00 2.26E-04 7.77E-04 1.89E-01

Sn-130 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 0.00E+00

Sn-130m 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 0.00E+00

I-130 2.22E-04 1.52E-04 1.67E-04 1.89E-04 1.30E-04 1.37E-04 1.18E-04 2.63E-04 6.66E-02 2.04E-04 1.74E-03 3.59E-03

Sb-131 1.11E-05 1.48E-05 2.55E-05 1.07E-05 5.55E-06 1.74E-05 1.85E-06 1.37E-05 2.29E-04 1.18E-05 7.03E-06 2.63E-04

Te-131 2.89E-06 3.70E-06 6.29E-06 2.74E-06 1.44E-06 4.44E-06 6.29E-07 3.59E-06 2.52E-04 2.92E-06 2.41E-06 1.70E-04

Te-131m 3.26E-04 1.22E-03 3.44E-04 4.44E-04 1.55E-04 2.96E-04 1.48E-04 3.66E-04 1.33E-02 5.92E-04 5.55E-04 5.18E-03

I-131 2.59E-04 8.88E-05 9.99E-05 2.04E-04 1.37E-04 9.25E-05 7.03E-05 3.15E-04 7.77E-01 1.04E-04 1.37E-03 4.07E-02

Xe-131m 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 0.00E+00

Sb-132 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 0.00E+00

Sb-132m 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 0.00E+00

Te-132 8.14E-04 2.89E-03 8.51E-04 1.04E-03 4.07E-04 7.77E-04 4.44E-04 1.04E-03 2.37E-02 1.41E-03 3.03E-03 1.11E-02

I-132 7.40E-05 5.92E-05 8.51E-05 6.66E-05 4.81E-05 6.66E-05 4.81E-05 8.51E-05 7.03E-03 7.40E-05 6.29E-04 7.40E-04

Sb-133 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 0.00E+00

A-7
Table A-2. Inhalation dose conversion factors 

based on ICRP-72. 

Inhalation Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S Wall SI Wall ULI W all LLI W all Kidneys Liver ET Region Lung

Te-133 2.96E-06 2.89E-06 2.66E-06 2.33E-06 1.89E-04 4.81E-05 6.66E-05 9.62E-05 2.63E-06 2.48E-06 2.00E-03 2.33E-04

Te-133m 2.89E-05 2.52E-05 2.11E-05 2.04E-05 8.14E-04 5.18E-04 5.92E-04 5.18E-04 2.96E-05 2.52E-05 7.40E-03 1.04E-03

I-133 7.77E-05 1.15E-04 1.26E-04 7.40E-05 4.44E-04 8.51E-05 1.11E-04 1.41E-04 7.40E-05 7.40E-05 1.48E-02 2.18E-04

Xe-133 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 0.00E+00

Xe-133m 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 0.00E+00

Te-134 2.66E-05 2.37E-05 1.85E-05 1.81E-05 5.92E-04 4.81E-04 4.07E-04 9.62E-05 2.96E-05 2.44E-05 7.03E-03 9.25E-04

I-134 3.03E-05 3.29E-05 3.29E-05 2.33E-05 3.70E-04 3.40E-05 3.22E-05 2.66E-05 2.74E-05 2.59E-05 5.55E-03 1.41E-04

Cs-134 3.70E-02 3.55E-02 2.78E-02 2.55E-02 3.33E-02 3.70E-02 3.59E-02 4.07E-02 3.48E-02 3.52E-02 8.14E-02 3.15E-02

Cs-134m 1.33E-05 1.48E-05 1.18E-05 1.07E-05 8.88E-05 1.48E-05 1.59E-05 1.48E-05 1.26E-05 1.30E-05 2.48E-03 1.26E-04

I-135 7.77E-05 1.07E-04 1.15E-04 7.03E-05 4.07E-04 8.51E-05 9.62E-05 9.99E-05 7.40E-05 7.40E-05 1.48E-02 2.07E-04

Xe-135 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 0.00E+00

Xe-135m 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 0.00E+00

Cs-135 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.52E-03 3.44E-03 3.70E-03 4.81E-03 3.44E-03 3.44E-03 7.40E-03 3.52E-03

Cs-136 5.92E-03 5.92E-03 4.44E-03 4.07E-03 5.55E-03 5.92E-03 5.92E-03 6.29E-03 5.55E-03 5.55E-03 7.03E-02 5.18E-03

Xe-137 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 0.00E+00

Cs-137 2.52E-02 2.44E-02 2.11E-02 2.00E-02 2.37E-02 2.52E-02 2.55E-02 2.96E-02 2.41E-02 2.41E-02 4.81E-02 2.29E-02

Ba-137m 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 0.00E+00

Xe-138 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 0.00E+00

Cs-138 2.15E-05 2.26E-05 2.26E-05 1.81E-05 4.44E-04 2.85E-05 2.33E-05 1.78E-05 2.00E-05 1.92E-05 3.37E-03 1.33E-04

Cs-139 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 0.00E+00

Ba-139 8.14E-06 5.55E-05 8.14E-06 7.77E-06 4.81E-04 3.63E-04 8.88E-04 2.04E-04 8.14E-06 8.14E-06 1.85E-03 1.33E-04

Cs-140 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 0.00E+00

Ba-140 1.07E-03 9.99E-03 7.03E-04 4.44E-04 9.99E-04 2.52E-03 1.48E-02 4.81E-02 9.25E-04 6.29E-04 3.18E-02 7.40E-04

La-140 5.18E-04 4.81E-04 2.18E-04 4.07E-04 1.70E-03 4.07E-03 1.30E-02 2.48E-02 4.81E-04 1.41E-03 5.18E-02 1.48E-02

Ba-141 5.92E-06 2.85E-05 5.92E-06 4.81E-06 2.37E-04 1.18E-04 3.70E-04 1.78E-04 5.92E-06 5.55E-06 1.85E-03 1.07E-04

La-141 6.66E-06 4.81E-05 4.81E-06 5.55E-06 1.26E-03 1.81E-03 3.29E-03 1.92E-03 5.92E-06 8.14E-05 3.70E-03 2.63E-03

Ce-141 2.26E-04 3.70E-04 1.44E-05 2.18E-04 4.07E-04 9.25E-04 4.81E-03 1.37E-02 7.03E-05 2.96E-04 2.15E-02 1.22E-01

Ba-142 7.03E-06 1.52E-05 7.03E-06 4.81E-06 1.22E-04 7.40E-05 1.67E-04 4.44E-05 7.77E-06 6.66E-06 2.07E-03 8.14E-05

La-142 4.07E-05 3.52E-05 2.96E-05 2.92E-05 1.07E-03 8.88E-04 8.51E-04 2.37E-04 4.44E-05 4.81E-05 8.51E-03 9.99E-04

La-143 9.99E-07 1.81E-06 7.40E-07 8.14E-07 3.22E-04 7.77E-05 7.03E-05 1.18E-04 9.25E-07 7.03E-06 1.59E-03 3.15E-04

Ce-143 5.18E-05 6.66E-05 2.18E-05 4.81E-05 8.51E-04 2.00E-03 8.51E-03 1.74E-02 5.18E-05 6.66E-05 1.44E-02 1.96E-02

Pr-143 5.55E-08 8.51E-06 5.55E-08 5.55E-08 5.55E-04 1.37E-03 8.14E-03 2.26E-02 1.44E-05 7.03E-05 1.26E-02 7.03E-02

Ce-144 9.99E-04 7.40E-03 2.96E-04 9.99E-04 2.55E-03 6.29E-03 3.70E-02 1.11E-01 4.81E-04 2.15E-02 1.11E-01 1.55E+00

Pr-144 9.62E-08 8.14E-08 8.88E-08 7.77E-08 3.70E-04 8.51E-05 1.59E-05 8.51E-07 8.14E-08 7.40E-08 1.63E-03 2.41E-04

Pr-144m 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 0.00E+00

Ce-145 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 0.00E+00

Pr-145 6.66E-07 8.14E-07 4.44E-07 5.18E-07 9.99E-04 1.70E-03 4.07E-03 3.15E-03 1.26E-06 1.63E-06 4.44E-03 3.03E-03

Ce-146 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 0.00E+00

Pr-146 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 0.00E+00

Ce-147 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 0.00E+00

Pr-147 2.26E-06 2.41E-06 2.00E-06 1.70E-06 2.07E-04 4.07E-05 1.48E-05 1.85E-05 1.78E-06 1.74E-06 2.15E-03 2.74E-04

Nd-147 1.55E-04 3.63E-04 1.81E-05 1.59E-04 5.92E-04 1.41E-03 7.40E-03 1.96E-02 6.29E-05 2.29E-04 1.85E-02 7.03E-02

Pm-147 2.55E-07 1.81E-02 9.99E-08 2.41E-07 1.22E-04 3.03E-04 1.85E-03 5.55E-03 1.44E-07 4.81E-03 6.66E-02 1.44E-01

Pr-148 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 0.00E+00

Pm-148 2.89E-04 1.85E-04 7.03E-05 3.00E-04 1.55E-03 3.70E-03 1.85E-02 4.81E-02 1.78E-04 3.00E-04 2.37E-02 4.81E-02

Pm-148m 6.29E-03 3.03E-03 5.18E-04 6.66E-03 3.70E-03 4.07E-03 9.62E-03 2.18E-02 2.33E-03 5.55E-03 7.77E-02 1.44E-01

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Te-133 3.44E-06 5.55E-06 6.29E-06 3.29E-06 1.67E-06 4.44E-06 7.03E-07 4.07E-06 2.00E-04 3.33E-06 4.44E-06 1.18E-04

Te-133m 3.15E-05 6.66E-05 6.29E-05 3.18E-05 1.48E-05 4.44E-05 6.66E-06 3.44E-05 9.25E-04 4.81E-05 3.48E-05 5.18E-04

I-133 1.18E-04 8.51E-05 8.88E-05 1.04E-04 8.14E-05 7.77E-05 7.03E-05 1.33E-04 1.52E-01 1.04E-04 2.04E-03 7.77E-03

Xe-133 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 0.00E+00

Xe-133m 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 0.00E+00

Te-134 2.92E-05 6.66E-05 5.92E-05 3.03E-05 1.37E-05 4.07E-05 5.92E-06 3.07E-05 1.30E-04 5.18E-05 3.48E-05 4.07E-04

I-134 3.44E-05 2.66E-05 4.81E-05 3.11E-05 2.22E-05 3.70E-05 2.04E-05 4.07E-05 1.33E-03 3.00E-05 1.96E-04 2.89E-04

Cs-134 3.11E-02 3.70E-02 3.70E-02 3.33E-02 2.33E-02 3.48E-02 3.11E-02 3.33E-02 3.33E-02 4.07E-02 3.63E-02 3.55E-02

Cs-134m 1.26E-05 1.33E-05 1.41E-05 1.22E-05 1.04E-05 1.30E-05 1.18E-05 1.30E-05 1.26E-05 1.33E-05 1.37E-05 9.62E-05

I-135 1.11E-04 8.51E-05 9.99E-05 9.62E-05 7.40E-05 8.51E-05 7.03E-05 1.33E-04 3.03E-02 1.07E-04 1.22E-03 1.70E-03

Xe-135 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 0.00E+00

Xe-135m 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 0.00E+00

Cs-135 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 3.44E-03 4.07E-03 3.66E-03

Cs-136 4.81E-03 5.92E-03 6.29E-03 5.18E-03 3.55E-03 5.55E-03 4.81E-03 5.55E-03 5.55E-03 6.29E-03 5.92E-03 7.03E-03

Xe-137 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 0.00E+00

Cs-137 2.26E-02 2.55E-02 2.55E-02 2.33E-02 1.92E-02 2.41E-02 2.26E-02 2.33E-02 2.33E-02 2.59E-02 2.59E-02 2.48E-02

Ba-137m 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 0.00E+00

Xe-138 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 0.00E+00

Cs-138 2.29E-05 1.78E-05 3.33E-05 2.15E-05 1.70E-05 2.66E-05 1.48E-05 2.70E-05 2.44E-05 1.78E-05 1.59E-05 1.67E-04

Cs-139 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 0.00E+00

Ba-139 8.14E-06 9.25E-06 8.88E-06 5.55E-05 7.77E-06 8.51E-06 7.77E-06 8.14E-06 8.14E-06 8.88E-06 7.77E-05 2.04E-04

Cs-140 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 0.00E+00

Ba-140 8.14E-04 2.48E-03 8.14E-04 7.03E-03 4.81E-04 6.29E-04 5.18E-04 5.92E-04 5.92E-04 1.26E-03 1.26E-03 5.92E-03

La-140 4.81E-04 2.00E-03 5.55E-04 6.66E-04 2.37E-04 4.44E-04 2.11E-04 5.55E-04 3.00E-04 9.62E-04 6.29E-04 5.55E-03

Ba-141 6.29E-06 7.03E-06 9.25E-06 2.66E-05 4.81E-06 7.40E-06 4.07E-06 7.03E-06 6.29E-06 6.29E-06 2.92E-05 1.30E-04

La-141 5.92E-06 9.62E-06 7.03E-06 1.37E-05 4.81E-06 6.29E-06 4.07E-06 6.29E-06 5.18E-06 7.40E-06 5.18E-06 8.51E-04

Ce-141 1.04E-04 1.59E-04 1.67E-04 1.37E-04 4.44E-05 1.63E-04 1.37E-05 2.74E-04 8.14E-05 7.40E-05 5.18E-05 1.55E-02

Ba-142 8.51E-06 1.44E-05 1.18E-05 1.63E-05 4.81E-06 8.51E-06 3.66E-06 8.88E-06 7.40E-06 1.07E-05 1.92E-05 9.62E-05

La-142 4.44E-05 9.62E-05 8.14E-05 4.44E-05 2.18E-05 5.92E-05 8.88E-06 4.81E-05 3.37E-05 7.40E-05 2.78E-05 5.55E-04

La-143 1.04E-06 2.59E-06 1.37E-06 1.70E-06 6.29E-07 1.07E-06 5.55E-07 1.11E-06 8.14E-07 1.44E-06 9.99E-07 1.22E-04

Ce-143 6.29E-05 2.96E-04 6.29E-05 7.77E-05 2.33E-05 5.18E-05 2.33E-05 6.29E-05 3.07E-05 1.33E-04 8.51E-05 4.07E-03

Pr-143 5.55E-08 5.55E-08 5.55E-08 8.51E-06 5.55E-08 5.55E-08 5.55E-08 5.55E-08 5.55E-08 5.55E-08 2.96E-07 1.04E-02

Ce-144 5.55E-04 3.48E-04 7.77E-04 4.44E-03 4.07E-04 7.77E-04 2.59E-04 1.15E-03 5.18E-04 3.03E-04 2.85E-04 1.96E-01

Pr-144 1.04E-07 8.51E-08 2.48E-07 8.88E-08 5.18E-08 1.67E-07 9.62E-09 1.37E-07 9.62E-08 7.40E-08 2.89E-08 1.11E-04

Pr-144m 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 0.00E+00

Ce-145 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 0.00E+00

Pr-145 8.51E-07 3.11E-06 1.11E-06 1.07E-06 4.07E-07 8.14E-07 2.44E-07 8.14E-07 5.18E-07 1.81E-06 9.25E-07 9.62E-04

Ce-146 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 0.00E+00

Pr-146 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 0.00E+00

Ce-147 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 0.00E+00

Pr-147 2.52E-06 1.85E-06 5.92E-06 2.07E-06 1.11E-06 4.07E-06 1.22E-07 3.18E-06 2.22E-06 1.48E-06 5.18E-07 1.11E-04

Nd-147 8.88E-05 2.70E-04 1.22E-04 1.30E-04 3.55E-05 1.18E-04 2.18E-05 1.92E-04 6.29E-05 1.15E-04 7.77E-05 9.99E-03

Pm-147 1.59E-07 1.07E-07 2.15E-07 1.44E-03 1.22E-07 2.00E-07 9.62E-08 2.78E-07 1.44E-07 1.04E-07 9.99E-07 1.81E-02

Pr-148 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 0.00E+00

Pm-148 2.11E-04 7.40E-04 2.48E-04 2.78E-04 9.99E-05 2.33E-04 7.40E-05 3.63E-04 1.41E-04 3.40E-04 2.33E-04 9.62E-03

Pm-148m 2.85E-03 3.59E-03 4.81E-03 3.70E-03 1.44E-03 4.44E-03 3.70E-04 7.77E-03 2.59E-03 1.67E-03 1.15E-03 2.18E-02

A-8
Table A-2. Inhalation dose conversion factors 

based on ICRP-72. 

Inhalation Dose Conversion Factors (rem/μCi) 

Nuclide Adrenals B Surface Brain Breast S W all SI W all ULI W all LLI Wall Kidneys Liver ET Region Lung

Pm-149 2.92E-06 4.81E-06 1.04E-06 2.66E-06 6.29E-04 1.48E-03 7.77E-03 1.70E-02 2.41E-06 9.62E-06 8.51E-03 1.74E-02

Pm-151 5.18E-05 6.66E-05 2.44E-05 4.44E-05 6.29E-04 1.44E-03 5.92E-03 1.04E-02 5.55E-05 5.92E-05 1.33E-02 1.04E-02

Sm-151 1.81E-06 4.07E-01 7.77E-07 6.29E-07 3.55E-05 8.88E-05 5.55E-04 1.67E-03 9.62E-07 1.07E-01 4.07E-03 1.15E-02

Eu-152 1.78E-01 7.03E-01 3.37E-02 4.81E-02 6.29E-02 6.66E-02 8.51E-02 5.55E-02 1.18E-01 9.99E-01 7.77E-02 2.29E-01

Sm-153 2.04E-05 2.81E-04 7.03E-06 1.67E-05 4.81E-04 1.15E-03 5.55E-03 1.15E-02 1.63E-05 3.11E-04 1.04E-02 1.63E-02

Eu-154 1.55E-01 1.52E+00 2.96E-02 4.44E-02 5.55E-02 5.92E-02 7.77E-02 6.29E-02 1.07E-01 1.26E+00 1.04E-01 3.70E-01

Eu-155 7.03E-03 4.44E-01 1.04E-03 1.55E-03 2.37E-03 2.55E-03 4.44E-03 6.66E-03 5.18E-03 1.37E-01 2.15E-02 7.03E-02

Eu-156 1.81E-03 5.18E-03 3.22E-04 1.52E-03 1.89E-03 3.59E-03 1.33E-02 3.37E-02 2.63E-03 7.03E-03 4.44E-02 8.51E-02

Tb-160 6.29E-03 5.18E-02 1.11E-03 4.44E-03 3.22E-03 4.07E-03 1.04E-02 2.48E-02 5.18E-03 2.00E-02 5.92E-02 1.74E-01

Ho-166m 5.55E-01 2.66E+00 8.88E-02 1.18E-01 2.74E-01 1.89E-01 2.33E-01 1.37E-01 3.48E-01 2.26E+00 1.52E-01 4.44E-01

Be-7 1.96E-04 8.51E-05 1.55E-05 2.00E-04 1.07E-04 8.51E-05 1.26E-04 2.07E-04 6.66E-05 1.63E-04 1.52E-03 9.25E-04

Na-24 6.29E-04 1.11E-03 6.29E-04 4.81E-04 1.15E-03 5.92E-04 5.92E-04 6.29E-04 5.55E-04 5.55E-04 4.81E-02 7.03E-04

Mn-54 5.92E-03 4.07E-03 9.99E-04 5.18E-03 3.26E-03 2.48E-03 3.26E-03 4.44E-03 2.81E-03 7.40E-03 2.63E-02 2.33E-02

Fe-55 3.70E-04 2.66E-03 3.70E-04 3.70E-04 3.70E-04 4.07E-04 5.18E-04 7.77E-04 3.70E-04 3.15E-03 3.70E-04 1.48E-03

Fe-59 5.18E-03 4.07E-03 1.70E-03 4.07E-03 3.70E-03 4.07E-03 7.03E-03 1.33E-02 3.55E-03 1.11E-02 4.81E-02 8.88E-02

Co-57 1.81E-03 1.37E-03 7.77E-05 1.78E-03 9.99E-04 4.07E-04 1.04E-03 2.44E-03 5.55E-04 1.59E-03 7.03E-03 2.44E-02

Co-58 4.44E-03 1.92E-03 3.70E-04 4.81E-03 2.63E-03 1.85E-03 3.44E-03 6.66E-03 1.67E-03 3.70E-03 3.37E-02 4.81E-02

Co-60 8.14E-02 3.44E-02 7.77E-03 9.25E-02 4.44E-02 1.30E-02 1.70E-02 2.11E-02 3.15E-02 7.40E-02 2.70E-01 6.66E-01

Cu-64 3.18E-05 3.15E-05 6.66E-05 2.59E-05 2.59E-04 3.00E-04 8.88E-04 1.11E-03 3.11E-05 5.92E-05 5.55E-03 2.74E-03

Cu-67 1.22E-04 1.41E-04 4.44E-04 1.04E-04 4.07E-04 4.81E-04 1.96E-03 4.44E-03 1.11E-04 3.59E-04 1.11E-02 1.89E-02

W-181 3.70E-05 2.44E-04 2.04E-05 7.77E-06 4.07E-05 9.62E-05 3.52E-04 8.88E-04 3.07E-04 8.14E-05 1.59E-03 2.11E-05

W-185 1.18E-05 6.29E-04 1.18E-05 1.18E-05 1.15E-04 1.92E-04 2.48E-03 7.03E-03 1.74E-03 3.07E-04 6.29E-03 1.07E-04

W-187 6.66E-05 2.74E-04 6.66E-05 4.44E-05 3.70E-04 7.03E-04 4.07E-03 7.03E-03 2.85E-04 1.07E-04 1.44E-02 1.89E-04

W-188 5.92E-05 4.07E-03 4.44E-05 3.66E-05 1.63E-04 3.70E-04 9.62E-03 4.07E-02 1.15E-02 2.00E-03 9.99E-03 1.30E-04

Au-198 1.48E-04 1.22E-04 6.66E-05 1.33E-04 7.77E-04 1.67E-03 7.03E-03 1.59E-02 1.18E-04 1.44E-04 1.85E-02 2.15E-02

Au-199 4.07E-05 5.18E-05 1.96E-05 3.63E-05 3.03E-04 6.66E-04 3.07E-03 7.40E-03 3.29E-05 4.07E-05 1.18E-02 2.44E-02

Pb-203 1.89E-04 5.18E-04 1.07E-04 8.14E-05 2.07E-04 3.55E-04 8.14E-04 1.44E-03 7.77E-04 4.81E-04 1.04E-02 1.59E-04

Th-229 6.29E+00 1.89E+03 6.29E+00 6.29E+00 6.29E+00 6.29E+00 6.29E+00 6.66E+00 2.66E+01 9.25E+01 1.48E+03 1.85E+03

Th-230 1.11E+00 1.04E+03 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.15E+00 1.18E+00 1.63E+01 1.37E+01 2.63E+02 2.85E+02

Th-234 5.55E-05 2.89E-04 8.14E-06 5.92E-05 1.59E-03 4.07E-03 2.33E-02 6.66E-02 1.11E-04 7.77E-05 2.29E-02 2.11E-01

U-233 5.18E-01 1.59E+01 5.18E-01 5.18E-01 5.18E-01 5.18E-01 5.18E-01 5.55E-01 5.18E+00 2.07E+00 4.44E+01 1.04E+02

U-234 5.18E-01 1.44E+01 5.18E-01 5.18E-01 5.18E-01 5.18E-01 5.18E-01 5.55E-01 5.18E+00 1.96E+00 4.44E+01 9.99E+01

U-235 4.81E-01 1.37E+01 4.81E-01 4.81E-01 4.81E-01 4.81E-01 4.81E-01 5.18E-01 4.81E+00 1.81E+00 4.07E+01 8.88E+01

U-237 1.04E-04 7.40E-04 2.15E-05 8.88E-05 4.07E-04 9.99E-04 4.81E-03 1.26E-02 9.99E-04 1.07E-04 2.07E-02 5.18E-02

U-238 4.44E-01 1.30E+01 4.44E-01 4.44E-01 4.44E-01 4.44E-01 4.81E-01 4.81E-01 4.81E+00 1.78E+00 3.70E+01 8.14E+01

U-240 3.52E-05 1.37E-04 2.18E-05 2.63E-05 1.30E-03 2.78E-03 9.99E-03 1.30E-02 4.81E-04 4.44E-05 1.55E-02 1.04E-02

Np-237 4.81E+00 3.70E+03 4.81E+00 4.81E+00 4.81E+00 4.81E+00 4.81E+00 5.18E+00 1.37E+01 5.92E+01 4.81E+01 1.07E+02

Np-239 5.92E-05 2.00E-03 2.55E-05 4.81E-05 5.18E-04 1.22E-03 5.55E-03 1.22E-02 1.15E-04 1.37E-04 1.96E-02 2.63E-02

Np-240 1.63E-05 8.88E-05 1.15E-05 1.07E-05 5.55E-04 3.63E-04 2.74E-04 6.29E-05 1.74E-05 1.55E-05 8.88E-03 1.67E-03

Pu-238 8.88E+00 5.18E+03 8.88E+00 8.88E+00 8.88E+00 8.88E+00 8.88E+00 8.88E+00 2.22E+01 1.07E+03 5.55E+01 1.37E+02

Pu-239 9.99E+00 5.55E+03 9.99E+00 9.99E+00 9.99E+00 9.99E+00 9.99E+00 9.99E+00 2.37E+01 1.22E+03 5.55E+01 1.22E+02

Pu-240 9.99E+00 5.55E+03 9.99E+00 9.99E+00 9.99E+00 9.99E+00 9.99E+00 9.99E+00 2.37E+01 1.22E+03 5.55E+01 1.22E+02

Pu-241 2.07E-01 1.15E+02 2.07E-01 2.07E-01 2.07E-01 2.07E-01 2.07E-01 2.07E-01 3.55E-01 2.41E+01 2.26E-01 2.44E-01

Am-241 1.07E+01 6.29E+03 1.07E+01 1.07E+01 1.07E+01 1.07E+01 1.07E+01 1.07E+01 3.22E+01 3.70E+02 5.55E+01 1.37E+02

Cm-242 1.30E-01 9.99E+01 1.30E-01 1.30E-01 1.30E-01 1.30E-01 1.52E-01 2.11E-01 2.04E+00 2.63E+01 3.22E+01 1.33E+02

Nuclide Muscle Ovaries Pancreas R Marrow Skin Spleen Testes Thymus Thyroid Uterus Bld Wall Eff Dose

Pm-149 2.85E-06 1.26E-05 3.11E-06 5.55E-06 1.15E-06 2.66E-06 1.18E-06 3.48E-06 1.63E-06 5.92E-06 4.07E-06 3.44E-03

Pm-151 6.29E-05 2.92E-04 6.66E-05 7.77E-05 2.41E-05 5.55E-05 2.44E-05 6.29E-05 3.26E-05 1.41E-04 8.88E-05 2.55E-03

Sm-151 8.88E-07 6.29E-07 1.04E-06 3.22E-02 6.66E-07 5.92E-07 5.18E-07 6.29E-07 5.55E-07 5.18E-07 1.55E-05 1.48E-02

Eu-152 5.18E-02 5.18E-02 1.33E-01 2.59E-01 3.26E-02 4.81E-02 1.37E-02 4.81E-02 3.07E-02 3.70E-02 2.44E-02 1.55E-01

Sm-153 2.15E-05 1.04E-04 2.29E-05 1.07E-04 7.77E-06 1.78E-05 7.77E-06 2.18E-05 9.62E-06 4.44E-05 3.52E-05 2.96E-03

Eu-154 4.44E-02 4.44E-02 1.15E-01 3.37E-01 2.89E-02 4.44E-02 1.22E-02 4.44E-02 2.78E-02 3.37E-02 2.18E-02 1.96E-01

Eu-155 1.81E-03 1.81E-03 5.55E-03 3.70E-02 8.51E-04 1.70E-03 3.11E-04 1.85E-03 9.62E-04 1.22E-03 7.40E-04 2.55E-02

Eu-156 8.88E-04 2.00E-03 1.41E-03 2.52E-03 4.81E-04 1.18E-03 2.37E-04 1.74E-03 7.03E-04 9.25E-04 7.03E-04 1.41E-02

Tb-160 2.48E-03 2.92E-03 4.44E-03 1.07E-02 1.41E-03 3.37E-03 5.18E-04 4.81E-03 2.07E-03 1.63E-03 1.15E-03 2.70E-02

Ho-166m 1.41E-01 1.41E-01 3.00E+00 5.55E-01 8.51E-02 2.33E-01 3.59E-02 1.26E-01 7.77E-02 1.04E-01 6.66E-02 4.44E-01

Be-7 8.88E-05 9.25E-05 1.48E-04 1.15E-04 4.44E-05 1.37E-04 1.04E-05 2.37E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Na-24 6.29E-04 5.92E-04 6.29E-04 8.14E-04 4.44E-04 5.55E-04 4.81E-04 7.03E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Mn-54 2.66E-03 2.44E-03 4.44E-03 4.07E-03 1.48E-03 4.07E-03 6.29E-04 6.29E-03 8.14E-05 4.44E-05 3.00E-05 2.15E-04

Fe-55 3.70E-04 3.70E-04 3.70E-04 4.81E-03 3.70E-04 1.11E-02 3.70E-04 3.70E-04 7.03E-04 5.92E-04 7.40E-04 1.89E-03

Fe-59 2.92E-03 3.70E-03 4.44E-03 5.55E-03 1.89E-03 7.40E-03 1.70E-03 4.81E-03 2.44E-03 1.52E-03 1.15E-03 5.55E-03

Co-57 7.40E-04 2.85E-04 1.37E-03 8.88E-04 3.22E-04 1.30E-03 3.37E-05 2.29E-03 3.70E-04 3.70E-04 3.70E-04 1.48E-03

Co-58 2.04E-03 1.81E-03 3.37E-03 2.59E-03 1.07E-03 3.29E-03 2.07E-04 5.55E-03 2.66E-03 2.81E-03 2.29E-03 1.52E-02

Co-60 3.63E-02 8.51E-03 5.92E-02 4.44E-02 2.04E-02 6.29E-02 1.89E-03 1.04E-01 7.03E-04 1.55E-04 1.07E-04 3.70E-03

Cu-64 3.37E-05 7.03E-05 6.66E-05 3.66E-05 2.15E-05 3.22E-05 2.04E-05 3.52E-05 1.89E-03 8.51E-04 5.92E-04 7.77E-03

Cu-67 1.11E-04 1.70E-04 3.70E-04 1.18E-04 8.88E-05 1.15E-04 9.25E-05 1.22E-04 3.63E-02 5.92E-03 3.70E-03 1.15E-01

W-181 2.55E-05 9.25E-05 3.70E-05 7.77E-05 1.11E-05 2.70E-04 1.11E-05 1.41E-05 2.96E-05 4.44E-05 3.37E-05 6.29E-04

W-185 1.18E-05 1.22E-05 1.18E-05 2.22E-04 1.18E-05 1.48E-03 1.18E-05 1.18E-05 1.07E-04 1.33E-04 1.33E-04 2.70E-03

W-187 9.25E-05 2.96E-04 8.51E-05 1.33E-04 5.55E-05 2.44E-04 6.29E-05 7.40E-05 1.44E-05 4.44E-05 8.14E-05 1.59E-04

W-188 4.81E-05 8.88E-05 5.92E-05 1.41E-03 4.07E-05 9.99E-03 4.07E-05 4.07E-05 1.18E-05 1.18E-05 4.07E-04 8.14E-04

Au-198 1.37E-04 4.81E-04 1.52E-04 1.70E-04 7.03E-05 1.33E-04 7.03E-05 1.70E-04 7.03E-05 1.67E-04 8.88E-04 1.18E-03

Au-199 3.70E-05 1.26E-04 4.44E-05 4.44E-05 2.00E-05 3.70E-05 2.07E-05 4.81E-05 4.07E-05 5.92E-05 1.18E-03 3.11E-03

Pb-203 1.33E-04 2.70E-04 1.81E-04 2.37E-04 8.14E-05 1.44E-04 9.25E-05 1.26E-04 9.62E-05 2.44E-04 2.85E-04 4.07E-03

Th-229 6.29E+00 1.48E+01 6.29E+00 9.25E+01 6.29E+00 5.92E+00 1.48E+01 6.29E+00 2.66E-05 6.66E-05 1.04E-04 3.52E-03

Th-230 1.11E+00 8.51E+00 1.11E+00 3.70E+01 1.11E+00 1.11E+00 8.51E+00 1.11E+00 1.18E-04 1.89E-04 1.74E-04 5.55E-04

Th-234 3.03E-05 5.92E-05 4.44E-05 1.70E-04 1.52E-05 4.44E-05 1.63E-05 7.03E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-233 5.18E-01 5.18E-01 5.18E-01 1.55E+00 5.18E-01 5.18E-01 5.18E-01 5.18E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-234 5.18E-01 5.18E-01 5.18E-01 1.48E+00 5.18E-01 5.18E-01 5.18E-01 5.18E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

U-235 4.81E-01 4.81E-01 4.81E-01 1.41E+00 4.81E-01 4.81E-01 4.81E-01 4.81E-01 6.29E+00 6.29E+00 6.29E+00 2.63E+02

U-237 7.03E-05 2.44E-04 8.51E-05 1.59E-04 2.81E-05 8.14E-05 2.37E-05 1.18E-04 1.11E+00 1.11E+00 1.11E+00 5.18E+01

U-238 4.44E-01 4.44E-01 4.44E-01 1.37E+00 4.44E-01 4.44E-01 4.44E-01 4.44E-01 2.48E-05 2.41E-05 1.89E-05 2.92E-02

U-240 4.44E-05 1.78E-04 4.81E-05 8.14E-05 2.00E-05 3.70E-05 1.78E-05 4.07E-05 5.18E-01 5.18E-01 5.18E-01 1.33E+01

Np-237 4.81E+00 5.18E+01 4.81E+00 1.44E+02 4.81E+00 4.81E+00 5.18E+01 4.81E+00 5.18E-01 5.18E-01 5.18E-01 1.30E+01

Np-239 5.55E-05 2.41E-04 6.29E-05 1.96E-04 2.59E-05 5.18E-05 4.44E-05 6.29E-05 4.81E-01 4.81E-01 4.81E-01 1.15E+01

Np-240 1.78E-05 3.59E-05 3.70E-05 2.00E-05 8.14E-06 2.52E-05 3.70E-06 1.89E-05 4.44E-05 1.15E-04 1.89E-04 7.03E-03

Pu-238 8.88E+00 6.66E+01 8.88E+00 2.55E+02 8.88E+00 8.88E+00 7.03E+01 8.88E+00 4.44E-01 4.44E-01 4.44E-01 1.07E+01

Pu-239 9.99E+00 7.40E+01 9.99E+00 2.74E+02 9.99E+00 9.99E+00 7.77E+01 9.99E+00 2.59E-05 8.88E-05 3.37E-04 3.03E-03

Pu-240 9.99E+00 7.40E+01 9.99E+00 2.74E+02 9.99E+00 9.99E+00 7.77E+01 9.99E+00 4.81E+00 4.81E+00 4.81E+00 8.51E+01

Pu-241 2.07E-01 1.52E+00 2.07E-01 4.44E+00 2.07E-01 2.07E-01 1.55E+00 2.07E-01 3.52E-05 1.11E-04 1.15E-04 4.07E-03

Am-241 1.07E+01 1.22E+02 1.07E+01 2.15E+02 1.07E+01 1.07E+01 1.22E+02 1.07E+01 1.30E-05 2.74E-05 1.37E-05 5.18E-04

Cm-242 1.30E-01 1.78E+00 1.30E-01 7.03E+00 1.30E-01 1.30E-01 1.78E+00 1.30E-01 8.88E+00 8.88E+00 8.88E+00 1.70E+02

A-9
APPENDIX B 

CODE LISTING 

FIIDOS, VERSION 4.3

B-1
 program main 

 include 'fiparms.f' 

 include 'varblock.f' 

c ..... 

c start of program 

c ..... 

 open(unit=1,file='fiidos.out',status='unknown') 

c ..... 

c subroutine input is used to read and check the input data provided 

c by the user for consistency and any possible error conditions. If 

c succesful, rest of program should run without any difficulties. 

c ..... 

 write(*,*) ' Reading input file.' 

 call input 

c ..... 

c subroutine fisfrc is used to convert the weapon yield in kilotons into the 

c relative number of fission for each fissionable material-neutron energy set 

c ..... 

 write(*,*) ' Calculating fission yields.' 

 call fisfrc 

c ..... 

c set up ORIGEN2 input deck and run ORIGEN2 

c ..... 

 write(*,*) ' Writing ORIGEN2 input.' 

 call orgsrc 

 write(*,*) ' Calling ORIGEN2.' 

 call ORIGEN2 

c ..... 

c final dose calculation loop is controlled by setting the time index 

c (tmindx) to the desired value of the measurement index or exposure 

c index. The measurement index will vary from 1 to nmeas, while the 

c exposure index will vary from nmeas+1 to nmeas+nexp. Each exposure 

c is linked to a particular measurement index via xcmeas. 

c ..... 

 do 40 i=1,nexp 

 tcncnew=xtexp(i) 

 write(*,50) (8,l=1,70),i,nexp,xtexp(i),xdur(i) 

 tmindx=xcmeas(i) 

 call rri 

 if(xitrm(i).gt.3) go to 30 

 call rges 

 30 continue 

 call sfcalc 

 tmindx=i+nmeas 

 call rri 

 tmindx=i 

 istidx=0 

 isttm=tmindx 

 call dose 

 istidx=1 

c ..... 

c Handle integrated doses (itpm=2) 

c ..... 

 if(itpm.eq.2) then 

 do 31 k=1,sss 

 tdsum(k)=0.0 

 td1sum(k)=0.0 

 td2sum(k)=0.0 

 td3sum(k)=0.0 

 td4sum(k)=0.0 

 31 continue 

 do 32 k=1,ppp 

 sumexf(k)=0.0 

 32 continue 

 33 continue 

 if(timest(istidx).le.xtexp(isttm))then 

 istidx=istidx+1 

B-2
 go to 33 

 endif 

 oldtcnc=xtexp(isttm) 

 34 continue 

 tcncnew=timest(istidx) 

 tmindx=istidx-40 

 if(tcncnew.ge.xtexp(isttm+nexp))then 

 tcncnew=xtexp(isttm+nexp) 

 tmindx=isttm+nexp+nmeas 

 endif 

 call rri 

 tmindx=i 

 call dose 

 if(tcncnew.eq.xtexp(isttm+nexp))go to 35 

 oldtcnc=tcncnew 

 istidx=istidx+1 

 go to 34 

 35 continue 

 endif 

c 

 if(iout4.eq.1) call outputf 

 40 continue 

 tmindx=nexp+1 

 write(*,*) ' ' 

 write(*,*) ' Writing output file data.' 

 call outputf 

 50 format(70a1,' Processing exposure number ',i2,' of ',i2, 

 ;', texp=',g10.4,' dur=',g10.4,\) 

c ..... 

c close up output file and end program 

c ..... 

 998 write(*,*)' FIIDOS finished' 

 write(1,999) 

 999 format(/' end') 

 close(unit=1) 

 stop 

 end 

c ..... 

c block data initialization routine 

c ..... 

 block data init 

 include 'fiparms.f' 

 include 'varblock.f' 

 data tddcfsum,tddcf1sum /sss*0.,sss*0.,sss*0.,sss*0./ 

 data tddcf2sum,tddcf3sum /sss*0.,sss*0.,sss*0.,sss*0./ 

 data tddcf4sum /sss*0.,sss*0./ 

 data afp,afracc /www*0.,www*0./ 

 data aactin,aactp,akrxer,actinp /xxx*0.,yyy*0.,vvv*0.,xxx*0./ 

 data actpp /yyy*0./ 

 data sumfrac /ppp*0./ 

 data spec,sactp,sactin,skrxer /ooo*0.,ooo*0.,ooo*0.,ooo*0./ 

 data sfracc,gamma,gref /ooo*0.,ooo*0.,nnn*0./ 

 data alphaemit / 

 ;1.0,1.0,0.0,1.0,1.0,1.0,0.0,1.0,0.0,1.0, 

 ;0.0,0.0,1.0,1.0,1.0,0.0,1.0,1.0,0.0,0.0/ 

 data timest / 

 ;2.78e-7,5.98e-7,1.29e-6,2.78e-6,5.98e-6,1.29e-5, 

 ;2.78e-5,5.98e-5,1.29e-4,2.78e-4,5.98e-4,1.29e-3, 

 ;2.78e-3,5.98e-3,1.29e-2,2.78e-2,5.98e-2,1.29e-1, 

 ;2.78e-1,5.98e-1,1.29e+0,2.78e+0,5.98e+0,1.29e+1, 

 ;2.78e+1,5.98e+1,1.29e+2,2.78e+2,5.98e+2,1.29e+3, 

 ;2.78e+3,5.98e+3,1.29e+4,2.78e+4,5.98e+4,1.29e+5, 

 ;2.78e+5,5.98e+5,1.29e+6,2.78e+6/ 

 end 

B-3
c 

c fiparms.for - This file contains the variables dimension data to define 

c the problem size for the fiidos primary routines. This 

c enables a more straightforward path when additional 

c nuclides are added to fiidos or if some array sizes need to 

c be adjusted to accomodate a specific problem. 

c 

 integer zzz,yyy,xxx,www,vvv 

 integer uuu,ttt,sss 

 integer ppp,ooo,nnn 

 real rzero 

c 

c Maximum number of measurements + exposures 

c Should be ORIGEN2 AAA-50 

 parameter (zzz=100) 

c Number of acitvation product nuclides 

 parameter (yyy=20) 

c Number of actinide nuclides 

 parameter (xxx=20) 

c Total number of FP nuclides (also for fractionation) 

 parameter (www=150) 

c Number of noble gas nuclides (krypton and xenon) 

 parameter (vvv=20) 

c Number of standard time steps for ORIGEN 

c storage vectors; must be less than JJJJ in 

c params.f (zzz+uuu must be less than JJJ) 

 parameter (uuu=40) 

c Number of nuclides in DCF files 

c (wwww+xxxx+yyyy) 

 parameter (ttt=190) 

c Maximum number of organs in DCF files (+1) 

 parameter (sss=40) 

c Number of entries for Pu retention output 

 parameter (ppp=30) 

c Number of gamma energy groups 

 parameter (ooo=18) 

c Number of gamma radiation exposure factors 

 parameter (nnn=21) 

c Set zero for real variables 

 parameter (rzero=0.0) 

c 

B-4
 integer xitrm,xitmi,xcmeas,xitdcf,tindex,tmindx 

 integer nplut,numorgans,edosnum 

 character*80 title,dcfidinfo 

 character*11 orgnames 

c 

 common /doses/ td(zzz,sss),td1(zzz,sss),td2(zzz,sss), 

 ; td3(zzz,sss),td4(zzz,sss), 

 ; tdold(sss),td1old(sss),td2old(sss),td3old(sss), 

 ; td4old(sss), 

 ; tdsum(sss),td1sum(sss),td2sum(sss),td3sum(sss), 

 ; td4sum(sss), 

 ; tddcfsum(2,sss),tddcf1sum(2,sss), 

 ; tddcf2sum(2,sss),tddcf3sum(2,sss), 

 ; tddcf4sum(2,sss), 

 ; dcf(sss),osrnd(ttt,sss),alphaemit(xxx) 

 common /organs/ numorgans(2),edosnum(2),dcfidinfo(2), 

 ; orgnames(2,sss) 

 common /flags/ itpm,ikrxer,iactp,iactin,ifrac,iplut,xitrm(zzz), 

 ; xitmi(zzz),xcmeas(zzz),xitdcf(zzz) 

 common /fract/ nfrac,id(www),ffrac(www) 

 common /fusion/ fie,fue,xnu1(3),xnu14(3),xnufu,alpha(3),beta(3) 

 common /inp/ nexp,xbr(zzz),xdur(zzz),xkfac(zzz),xtexp(zzz) 

 common /inv/ afp(www),aactin(xxx),aactp(yyy),acttot, 

 ; akrxer(vvv),afracc(www),actinp(xxx),actpp(yyy) 

 common /look/ lookfp(www),lookap(yyy),lookan(xxx) 

 common /meas/ nmeas,nplut,xtmeas(zzz),xrimes(zzz),xactmes(zzz), 

 ; sf 

 common /plutm/ exfrac(zzz,ppp),sumfrac(ppp),sumexf(ppp), 

 ; oldexf(ppp) 

 common /outf/ iout1,iout2,iout3,iout4,iout5 

 common /spect/ spec(ooo),gref(nnn),sactp(ooo),sactin(ooo), 

 ; skrxer(ooo),sfracc(ooo),gamma(ooo) 

 common /time/ times(zzz),xtra(zzz),tindex(zzz),tyrs(ppp),tmindx, 

 ; tcncnew,oldtcnc,timest(uuu),isttm,istidx 

 common /title/ title 

 common /yield/ ykt(6),yfis(6),twyf,yfisf(6),cmvkt 

B-5
 subroutine input 

 include 'fiparms.f' 

 include 'varblock.f' 

c ..... 

c local variables 

c ..... 

 integer txitrm,txitmi,txcmeas,txitdcf,origord(zzz) 

 real lowdiff,lowtime 

c 

c .... 

c this subroutine obtains and checks the input data from the fiidos user 

c as much as possible - most random errors cause the program to crash 

c by trying to read incompatible data formats. miscellaneous number 

c errors may be caught before they cause trouble 

c if users never made mistrakes, most of this subroutine wouldn't be here 

c .... 

c array title - title of the problem 

c variable itpm - index for type of problem. the two types of problems are: 

c (1) discreet exposure cases; n measurement times and 

c m exposure times, generally m >= n 

c (2) integrated case; 1 measurement time and 

c 1 long term exposure time 

c variable iout1 - index for output control 

c (0) suppress output 

c (1) print relative gamma emission spectrum at the time 

c of measurement or the measured activity of radioc logical material, and the radiological contamination 

c scaling factor 

c variable iout2 - index for output control 

c (0) suppress output 

c (1) print the relative radionuclide inventories for 

c fission products, activation products, and actinide 

c elements at the time of exposure 

c variable iout3 - index for output control 

c (0) suppress output 

c (1) print the dose to each organ from each radionuclide. 

c variable iout4 - index for output control 

c (0) suppress output 

c (1) print intermediate organ dose results for each 

c exposure incident 

c variable iout5 - index for table creation 

c (0) suppress output 

c (1) create tables of organ doses for fission products, 

c activation products, actinides, and total as a 

c function of time - good for importing into spreadc sheet software for further analysis. Four 

c tables will be created for each set of dose 

c conversion factors used. 

c variable nmeas - number of measurement times 

c array xitrm(i) - index for type of i th radiological measurement 

c the six types of measurement are: 

c (1) radiation intensity - above contaminated surface 

c (2) radiation intensity - inside debris cloud 

c (3) radiation intensity - below debris cloud 

c (4) gross activity - airborne concentration 

c (5) gross activity - surface concentration 

c (6) gross activity - inhalation or ingestion intake 

c array xtmeas(i) - time at which i th radiological measurement was made 

c array xrimes(i) - i th radiation intensity measurement, for itrm = 1-3; 

c i th radionuclide index, if measured single species when 

c xitrm = 6 

c array xitmi(i) - index for i th type of radiation intensity measurement 

c device; the five types are: 

c (1) tissue free-in-air 

c (2) air, free-in-air 

c (3) film badge, free-in-air 

c (4) film badge, in-situ(midplane) 

B-6
c (5) film badge, in-situ(isotropic) 

c array xactmes(i)- i th measured gross activity 

c variable nexp - number of exposure incidents 

c array xtexp(i) - time at which i th exposure occurred 

c array xcmeas(i) - index for correspondence to measurement time 

c possible values are: 

c (1) Use nearest measurement time > exposure time 

c (0) Use nearest measurement time < exposure time (default) 

c (-n) Use n th measurement time 

c array xdur(i) - duration of i th exposure 

c array xbr(i) - breathing rate during i th exposure 

c array xkfac(i) - ratio of airborne to surface activity during i th exposure 

c array xitdcf(i) - index for type of dose conversion factor for i th exposure 

c - there are nine types: 

c (1) inhalation dcf (ornl tm-190) 

c (2) ingestion dcf (ornl tm-190) 

c (3) inhalation (large particles) dcf (ornl tm-190) 

c (4) inhalation dcf (icrp-30) 

c (5) ingestion dcf (icrp-30) 

c (6) inhalation (20 um large particles) dcf (icrp-30) 

c (7) inhalation dcf (icrp-30) 

c (8) ingestion dcf (icrp-30) 

c (9) inhalation (10 um large particles) dcf (icrp-30) 

c (10) inhalation dcf (icrp-72) 

c (11) ingestion dcf (icrp-72) 

c array ykt(i) - yield in kilotons from fm-ne set i. the six fm-ne sets are: 

c (1) u-235, fast neut. (2) u-235,14-mev neut. 

c (3) u-238, fast neut. (4) u-238,14-mev neut. 

c (5)pu-239, fast neut. (6)pu-239,14-mev neut. 

c because these yields are not usually known or reported 

c an alternative input is available and suggested 

c (1) -1 ; for a flag (2) total yield 

c (3) u-235 total yield (4) u-238 total yield 

c (5) pu-239 total yield (6) total fusion yield 

c variable iactp - index for treatment of activation products. the options are: 

c (0) do not include activation products 

c (1) include activation products 

c array actpp(i) - activation product production for i th radionuclide (ci/kt). 

c production data must be provided for twenty radionuclides 

c (1) be-7 (2) na-24 (3) mn-54 (4) fe-55 

c (5) fe-59 (6) co-57 (7) co-58 (8) co-60 

c (9) cu-64 (10)cu-67 (11) w-181 (12) w-185 

c (13) w-187 (14) w-188 (15)au-198 (16)au-199 

c (17)pb-203 (18)mn-56 (19)not used (20)not used 

c variable iactin - index for treatment of actinide elements. the options are: 

c (0) do not include actinide elements 

c (1) include actinide elements 

c array actinp(i) - actinide element production for i th radionuclide (ci/kt). 

c production data must be provided for twenty radionuclides 

c (1) th-229 (2) th-230 (3) th-234 (4) u-233 

c (5) u-234 (6) u-235 (7) u-237 (8) u-238 

c (9) u-240 (10)np-237 (11)np-239 (12)np-240 

c (13)pu-238 (14)pu-239 (15)pu-240 (16)pu-241 

c (17)am-241 (18)cm-242 (19)not used (20)not used 

c variable ikrxer - index for treatment of krypton and xenon. the options are: 

c (0) do not modify inventory 

c (1) remove krypton and xenon 

c variable ifrac - index for treament of fractionation of fission products. 

c the two choices are: 

c (0) do not modify inventory 

c (1) modify inventory for fractionation 

c variable nfrac - the number of radiological nuclides to be modified by 

c fractionation 

c array id(i) - index for the identification of the i th fission product 

c radionuclide to be changed. indices of fission product 

c radionuclides are listed in subroutine fraci. 

c array ffrac(i) - fraction of basic inventory of radionuclide i that is to 

B-7
c be present in fractionated fallout material 

c variable iplut - index for treatment of plutonium bioassay 

c (0) Suppress calculation 

c (1) Perform plutonium bioassay calculation 

c variable nplut - number of entries for plutonium calculation (max 30) 

c array tyrs(i) - time after exposure (yrs) for pu239 conc in urine 

c 

10 continue 

c ..... 

c problem identification and control data 

c ..... 

 open(unit=2,file='input.dat',status='old') 

 read(2,20) title 

 20 format(a80) 

 read(2,*) itpm 

 if(itpm.gt.2.or.itpm.lt.1)then 

 write(*,*) ' Error reading input file. Bad value of itpm.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) iout1 

 if(iout1.gt.1.or.iout1.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iout1.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) iout2 

 if(iout2.gt.1.or.iout2.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iout2.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) iout3 

 if(iout3.gt.1.or.iout3.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iout3.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) iout4 

 if(iout4.gt.1.or.iout4.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iout4.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) iout5 

 if(iout5.gt.1.or.iout5.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iout5.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 30 continue 

c ..... 

c radiological measurement data 

c ..... 

 read(2,*) nmeas 

B-8
 if(nmeas.le.0) then 

 write(*,*) ' Number of measurements cannot be zero or negative.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(itpm.eq.2.and.nmeas.gt.33) then 

 write(*,*) ' Number of measurements must be less than 33 when' 

 write(*,*) ' itpm = 2. Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(nmeas.gt.50) then 

 write(*,*) ' Number of measurements > 50. Problem will not run' 

 write(*,*) ' if nmeas+nexp>100.' 

 if(nmeas.gt.zzz) then 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 endif 

 do 40 i=1,nmeas 

 read(2,*) xitrm(i),xtmeas(i),xrimes(i),xitmi(i),xactmes(i) 

 origord(i)=i 

 if(xitrm(i).lt.1.or.xitrm(i).gt.6.or. 

 ; xitmi(i).lt.0.or.xitmi(i).gt.5) then 

 write(*,*) ' Error reading input file. Bad itrm or itmi value.' 

 write(*,*) ' Last value of tmeas read was ',xtmeas(i) 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(xtmeas(i).lt.2.78e-7) then 

 write(*,*) ' Times shorter than 2.78e-7 hours not permitted.' 

 write(*,*) ' Adjusting time ',xtmeas,' to 2.78e-7 hours.' 

 xtmeas(i)=2.78e-7 

 endif 

 if(xtmeas(i).gt.1.e7) then 

 write(*,*) ' Calculations for times longer than 1000 years' 

 write(*,*) ' are not reliable, but the problem will run.' 

 endif 

 40 continue 

c ..... 

c sort measurement data in chronologic order 

c ..... 

 if(nmeas.gt.1) then 

 do 42 i=1,nmeas 

 do 41 j=1,nmeas-1 

 if(xtmeas(j).gt.xtmeas(j+1))then 

 txitrm=xitrm(j) 

 txtmeas=xtmeas(j) 

 txrimes=xrimes(j) 

 txitmi=xitmi(j) 

 txactmes=xactmes(j) 

 torigord=origord(j) 

c 

 xitrm(j)=xitrm(j+1) 

 xtmeas(j)=xtmeas(j+1) 

 xrimes(j)=xrimes(j+1) 

 xitmi(j)=xitmi(j+1) 

 xactmes(j)=xactmes(j+1) 

 origord(j)=origord(j+1) 

c 

B-9
 xitrm(j+1)=txitrm 

 xtmeas(j+1)=txtmeas 

 xrimes(j+1)=txrimes 

 xitmi(j+1)=txitmi 

 xactmes(j+1)=txactmes 

 origord(j+1)=torigord 

 endif 

 41 continue 

 42 continue 

 endif 

c ..... 

c dose calculation data and determination of relevant measurement 

c ..... 

 read(2,*) nexp 

 if(nexp.le.0) then 

 write(*,*) ' Number of exposures cannot be zero or negative.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(itpm.eq.2.and.nexp.gt.33) then 

 write(*,*) ' Number of exposures must be less than 33 when' 

 write(*,*) ' itpm = 2. Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(nexp+nmeas.gt.100) then 

 write(*,*) ' nmeas+nexp exceeds max value of 100.' 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 do 60 i=1,nexp 

 lowtime = 1e7 

 txcmeas = 0 

 read(2,*) xtexp(i),xcmeas(i),xdur(i),xbr(i),xkfac(i),xitdcf(i) 

 if(xcmeas(i).gt.1) then 

 write(*,*) ' Error reading input file. Bad cmeas number.' 

 write(*,*) ' Last value of texp read was ',xtexp(i) 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(xitdcf(i).lt.1.or.xitdcf(i).gt.2) then 

 write(*,*) ' Error reading input file. Bad itdcf number.' 

 write(*,*) ' Last value of texp read was ',xtexp(i) 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(abs(xcmeas(i)).gt.nmeas) then 

 write(*,*) ' Error in exposure/measurement correspondence.' 

 write(*,*) ' Last value of texp read was ',xtexp(i) 

 write(*,*) ' Program quitting' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(xtexp(i).lt.2.78e-7) then 

 write(*,*) ' Times shorter than 2.78e-7 hours not permitted.' 

 write(*,*) ' Adjusting time ',xtexp,' to 2.78e-7 hours.' 

 xtexp(i)=2.78e-7 

B-10
 endif 

 if(xtexp(i).gt.1.e7) then 

 write(*,*) ' Calculations for times longer than 1000 years' 

 write(*,*) ' are not reliable, but the problem will run.' 

 write(*,*) ' Some elements may underflow in ORIGEN, causing' 

 write(*,*) ' problems for FIIDOS in the dose calculation.' 

 endif 

c ..... 

c determine corresponding measurement time (for xcmeas(i)=0 or 1) 

c ..... 

 if(xcmeas(i).eq.0) then 

 do 50 j=1,nmeas 

 lowdiff=xtexp(i)-xtmeas(j) 

 if(lowdiff.gt.rzero.and.lowdiff.lt.lowtime) then 

 lowtime=lowdiff 

 txcmeas=j 

 endif 

 50 continue 

 if(txcmeas.eq.0) then 

 write(*,*) ' Warning! No measurement times earlier than ', 

 ; xtexp(i) 

 write(*,*) ' Adjusting to find closest later time.' 

 xcmeas(i)=1 

 endif 

 endif 

c 

 if(xcmeas(i).eq.1) then 

 do 51 j=1,nmeas 

 lowdiff=xtmeas(j)-xtexp(i) 

 if(lowdiff.gt.rzero.and.lowdiff.lt.lowtime) then 

 lowtime=lowdiff 

 txcmeas=j 

 endif 

 51 continue 

c 

 if(txcmeas.eq.0) then 

 write(*,*) ' Warning! No measurement times later than ', 

 ; xtexp(i) 

 write(*,*) ' Adjusting correspondence to closest earlier time.' 

 xcmeas(i)=0 

 do 52 j=1,nmeas 

 lowdiff=xtexp(i)-xtmeas(j) 

 if(lowdiff.gt.rzero.and.lowdiff.lt.lowtime) then 

 lowtime=lowdiff 

 txcmeas=j 

 endif 

 52 continue 

 endif 

 endif 

c 

 if(txcmeas.eq.0.and.xcmeas(i).ge.0) then 

 write(*,*) ' Bizarre error in exposure-measurement time', 

 ; 'correspondence!' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(xcmeas(i).ge.0)xcmeas(i)=txcmeas 

 if(xcmeas(i).lt.0)then 

 do 53 j=1,nmeas 

 if((abs(xcmeas(i)).eq.origord(j)).and.(xcmeas(i).lt.0)) 

 ; xcmeas(i)=j 

 53 continue 

 endif 

 60 continue 

c ..... 

B-11
c sort exposure data in chronologic order 

c ..... 

 if(nexp.gt.1) then 

 do 72 i=1,nexp 

 do 71 j=1,nexp-1 

 if(xtexp(j).gt.xtexp(j+1))then 

 txtexp=xtexp(j) 

 txcmeas=xcmeas(j) 

 txdur=xdur(j) 

 txbr=xbr(j) 

 txkfac=xkfac(j) 

 txitdcf=xitdcf(j) 

c 

 xtexp(j)=xtexp(j+1) 

 xcmeas(j)=xcmeas(j+1) 

 xdur(j)=xdur(j+1) 

 xbr(j)=xbr(j+1) 

 xkfac(j)=xkfac(j+1) 

 xitdcf(j)=xitdcf(j+1) 

c 

 xtexp(j+1)=txtexp 

 xcmeas(j+1)=txcmeas 

 xdur(j+1)=txdur 

 xbr(j+1)=txbr 

 xkfac(j+1)=txkfac 

 xitdcf(j+1)=txitdcf 

 endif 

 71 continue 

 72 continue 

 endif 

c ..... 

c check measurement and exposure data for various incompatibilities 

c ..... 

c integrated exposures (itpm=2) not allowed with itrm=6 

 if(itpm.eq.2) then 

 do 73 i=1,nexp 

 if(xitrm(i).eq.6) then 

 write(*,*) ' You cannot use an integrated exposure (itpm=2)' 

 write(*,*) ' with a gross activity ingestion/inhalation ', 

 ; '(itrm=6).' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 73 continue 

 endif 

c cannot have multiple exposures to a single ingestion 

 do 75 i=1,nmeas 

 if(xitrm(i).eq.6) then 

 itrmexp=0 

 do 74 j=1,nexp 

 if(xcmeas(j).eq.i) itrmexp=itrmexp+1 

 74 continue 

 if(itrmexp.gt.1) then 

 write(*,*) ' You cannot have multiple exposures to a single' 

 write(*,*) ' gross activity ingestion or inhalation (itrm=6).' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 endif 

 75 continue 

c ..... 

c shot data 

c ..... 

B-12
 read(2,*) (ykt(i),i=1,6) 

 read(2,*) iactp 

 if(iactp.gt.1.or.iactp.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iactp.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(iactp.eq.0) go to 80 

 read(2,*) (actpp(i),i=1,20) 

 80 continue 

 read(2,*) iactin 

 if(iactin.gt.1.or.iactin.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iactin.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(iactin.eq.0) go to 90 

 read(2,*) (actinp(i),i=1,20) 

 90 continue 

c ..... 

c fallout data 

c ..... 

 read(2,*) ikrxer 

 if(ikrxer.gt.1.or.ikrxer.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of ikrxer.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) ifrac 

 if(ifrac.gt.1.or.ifrac.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of ifrac.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(ifrac.eq.0) go to 120 

 open(unit=3,file='frac.gam',status='unknown') 

 nfrac=0 

 105 read(2,*,end=110) id(nfrac+1) 

 read(2,*) ffrac(nfrac+1) 

 read(2,*)(gamma(j),j=1,ooo) 

 write(3,*)(gamma(j),j=1,ooo) 

 nfrac=nfrac+1 

 go to 105 

 110 continue 

 close(unit=3) 

 120 continue 

c ..... 

c plutonium data 

c ..... 

 read(2,*)iplut 

 if(iplut.gt.1.or.iplut.lt.0)then 

 write(*,*) ' Error reading input file. Bad value of iplut.' 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 if(iplut.eq.0) go to 140 

 read(2,*)nplut 

B-13
 if(nplut.gt.ppp) then 

 write(*,*) ' Number of entries for Pu retention currently' 

 write(*,*) ' limited to ',ppp 

 write(*,*) ' Program quitting.' 

 close(unit=1) 

 close(unit=2) 

 stop 

 endif 

 read(2,*) (tyrs(i),i=1,nplut) 

 140 continue 

 close(unit=2) 

c ..... 

c write output file header info 

c ..... 

 write(1,500) title,itpm,iout1,iout2,iout3,iout4,iout5 

 write(1,510) nmeas 

 write(1,520) (xitrm(i),i=1,nmeas) 

 write(1,530) (xtmeas(i),i=1,nmeas) 

 write(1,540) (xrimes(i),i=1,nmeas) 

 write(1,550) (xitmi(i),i=1,nmeas) 

 write(1,560) (xactmes(i),i=1,nmeas) 

 write(1,570) nexp 

 write(1,580) (xtexp(i),i=1,nexp) 

 write(1,590) (xcmeas(i),i=1,nexp) 

 write(1,600) (xdur(i),i=1,nexp) 

 write(1,610) (xbr(i),i=1,nexp) 

 write(1,620) (xkfac(i),i=1,nexp) 

 write(1,630) (xitdcf(i),i=1,nexp) 

 write(1,650) iactp 

 write(1,670) iactin 

 write(1,690) ikrxer 

 write(1,700) ifrac 

 if(ifrac.ne.1) go to 230 

 write(1,710) nfrac 

 write(1,720) (id(i),i=1,nfrac) 

 write(1,730) (ffrac(i),i=1,nfrac) 

 230 write(1,740) iplut 

 if(iplut.ne.1) go to 240 

 write(1,750) nplut 

 write(1,760) (tyrs(i),i=1,nplut) 

c 

c ..... 

c Set up integrated exposures if itpm=2 (Not echoed in output file) 

c ..... 

 240 if(itpm.eq.2) then 

 do 300 i=1,nexp 

 xtexp(i+nexp)=xtexp(i)+xdur(i) 

 xcmeas(i+nexp)=xcmeas(i) 

 xdur(i+nexp)=xdur(i) 

 xbr(i+nexp)=xbr(i) 

 xkfac(i+nexp)=xkfac(i) 

 xitdcf(i+nexp)=xitdcf(i) 

 300 continue 

 endif 

c ..... 

c format block 

c ..... 

 500 format(34x,'fiidos input'/ 

 ;8x,'title:',3x,a80,/ 

 ;8x,80('-')/ 

 ;8x,'itpm problem type single/integrated 1/2',i10/ 

 ;8x,'iout1 print spectrum no/yes 0/1',i10/ 

 ;8x,'iout2 print inventory no/yes 0/1',i10/ 

 ;8x,'iout3 print dose inventory no/yes 0/1',i10/ 

 ;8x,'iout4 print intermediate doses no/yes 0/1',i10/ 

 ;8x,'iout5 print dose tables no/yes 0/1',i10) 

 510 format(/ 

B-14
 ;8x,'nmeas number of measurement calculations ',i10) 

 520 format( 

 ;8x,'itrm rad measurement indices ', 

 ;10i10,19(/64x,10i10)) 

 530 format( 

 ;8x,'tmeas time of rad measurements ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 540 format( 

 ;8x,'rimes rad intensity (itrm=1-3); index nuclide (itrm=6)', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 550 format( 

 ;8x,'itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 ', 

 ;10i10,19(/64x,10i10)) 

 560 format( 

 ;8x,'actmes activity measurement (itrm=4-6) ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 570 format(/ 

 ;8x,'nexp number of exposure calculations ',i10) 

 580 format( 

 ;8x,'texp exposed @ h+(hr) ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 590 format( 

 ;8x,'icmeas rad exposure to measurement indices (re-sorted) ', 

 ;10i10,19(/64x,10i10)) 

 600 format( 

 ;8x,'dur duration (hr) ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 610 format( 

 ;8x,'br breathing rate (m**3/hr) ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 620 format( 

 ;8x,'kfac resuspension factors (m**-1) ', 

 ;5x,1p10g10.3,19(/69x,1p10g10.3)) 

 630 format( 

 ;8x,'itdcf dose conversion factor set index 1/2 ', 

 ;10i10,19(/64x,10i10)) 

 650 format(/ 

 ;8x,'iactp activation products no/yes 0/1',i10) 

 670 format( 

 ;8x,'iactin actinides no/yes 0/1',i10) 

 690 format( 

 ;8x,'ikrxer noble gases removed no/yes 0/1',i10) 

 700 format( 

 ;8x,'ifrac fractionation no/yes 0/1',i10) 

 710 format( 

 ;8x,'nfrac number of fission products to be fractionated ',i10) 

 720 format(/8x,'isotope id''s',5x,5i10/(25x,5i10)) 

 730 format(/8x,'fractionation factor ',1p5g10.3/(29x,5g10.3)) 

 740 format(/ 

 ;8x,'iplut plutonium bioassay no/yes 0/1',i10) 

 750 format( 

 ;8x,'nplut number of entries for plutonium bioassay ',i10) 

 760 format( 

 ;8x,'tyrs times after shot for Pu conc in urine ', 

 ;5x,1p10g10.3) 

 770 format(//34x,'fiidos output') 

 900 continue 

 write(1,770) 

 return 

 end 

B-15
 subroutine fisfrc 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine calulates the total weapon yield in number of fissions and 

c the fraction of that yield from each fissionable-neutron energy set. 

c ..... 

c variable ykttot - total yield of device both fusion and fission (new input) 

c variables ykt235,ykt238,ykt239- fission yield of u235,u238,pu239 (new input) 

c variables yktfus - fusion yield (new input) 

c array ykt(i) - yield in kilotons from fm-ne set i (old input) 

c array yfis(i) - yield in fissions from fm-ne set i 

c variable twyf - total weapon yield in fissions. 

c array yfisf(i) - fraction of total weapon yield from fm-ne set i.(results) 

c variable cmvkt - conversion factor of fissions per kt 

c variable fif - fission fraction of yield (derived) 

c variable fie - energy recovered per fission 

c variable fue - energy recovered per fusion 

c variable xnu1 - neutrons released from 1 mev fission 

c variable xnu14 - neutrons released from 14 mev fission 

c variable xnufu - neutrons released from fusion 

c variable fifi1 - probability of a fission neutron causing a 1 mev fission 

c variable fufi14 - probability of a fusion neutron causing a 14 mev fission 

c variable fufi1 - probability of a fusion neutron causing a 1 mev fission 

c variable alpha - ratio of fufi14/fifi1 

c variable beta - ratio of fufi1/fifi1 

c variable frac1 - fraction of yield from fissions from 1 mev neutrons 

c variable frac14 - fraction of yield from fissions from 14 mev neutrons 

c variable fracfu - fraction of yield from fusion 

c ..... 

 twyf=0.0 

 frac14=0.0 

 frac1=0.0 

 fracfu=0.0 

 if(ykt(1).ge.0) go to 20 

c 

c option to determine the fission fractions from fusion/fission ratios 

c uses new input 

 ykttot=ykt(2) 

 ykt235=ykt(3) 

 ykt238=ykt(4) 

 ykt239=ykt(5) 

 yktfus=ykt(6) 

 if(abs(ykttot-ykt235-ykt238-ykt239-yktfus).gt.0.02*ykttot) 

 ;write(*,*)' recheck fission/fusion yield inputs ; do not add up' 

 fif=(ykt235+ykt238+ykt239)/ykttot 

 do 10 i=1,3 

 a=(1-fif)*fie/fue*xnufu*(xnu14(i)-xnu1(i))*alpha(i) 

 b=fif*xnu1(i)+(1-fif)*fie/fue*xnufu*(alpha(i)+beta(i)) 

 c=-fif 

 if(xnu14(i).ne.xnu1(i).and.a.ne.0)fifi1=(-b+sqrt(b*b-4*a*c))/(2*a) 

 if(xnu14(i).eq.xnu1(i).or .a.eq.0)fifi1=-c/b 

 frac14=(1-fif)*fie/fue*xnufu*alpha(i)*fifi1 

 frac1=fif-frac14 

 fracfu=(1-fif) 

 if(i.eq.1)ykt(1)=ykt235*frac1 

 if(i.eq.1)ykt(2)=ykt235*frac14 

 if(i.eq.2)ykt(3)=ykt238*frac1 

 if(i.eq.2)ykt(4)=ykt238*frac14 

 if(i.eq.3)ykt(5)=ykt239*frac1 

 if(i.eq.3)ykt(6)=ykt239*frac14 

 10 continue 

c 

 20 do 30 i=1,6 

 yfis(i)=ykt(i)*cmvkt 

 twyf =twyf + yfis(i) 

 30 continue 

 40 do 50 i=1,6 

B-16
 yfisf(i)=yfis(i)/twyf 

 50 continue 

c .... 

 return 

 end 

c ..... 

 block data init1 

 common /fusion/ fie,fue,xnu1(3),xnu14(3),xnufu,alpha(3),beta(3) 

 common /yield/ ykt(6),yfis(6),twyf,yfisf(6),cmvkt 

 data cmvkt /1.45e+23/ 

 data fie,fue, xnu1, xnu14, xnufu, alpha, beta/ 

 ; 180.,17.6,2.5,2.5,3.0,4.5,4.4,4.8, 1. ,.93,3.5,.94,.29,.83,.18/ 

 end 

B-17
 subroutine orgsrc 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine writes out the input file for the origen2 code 

c it uses the data read in by input.dat 

c ..... 

c array a - first section of origen2 input 

c array b - second section of origen2 input 

c array c - third section of origen2 input 

c array ahe - curies of actinides (heavy elements) 

c array ale - curies of activation products (light elements) 

c array ihe - origen2 actinide identification number 

c array ile - origen2 activation product identification number 

c ..... 

 character*80 a(45),b(41),c 

c 

 equivalence (yfisf(1),u235ff),(yfisf(3),u238ff),(yfisf(5),pu239ff) 

 equivalence (yfisf(2),u23514),(yfisf(4),u23814),(yfisf(6),pu23914) 

c 

 dimension ahe(100),ihe(100),ale(100),ile(100) 

 dimension idactp(20),dactp(20),idactin(20),dactin(20) 

c 

 data idactp/04070,110240,250540,260550,260590,270570, 

 ; 270580,270600,290640,290670,741810,741850,741870, 

 ; 741880,791980,791990,250560,000000,000000,000000/ 

 data idactin/902290,902300,902340,922330,922340,922350, 

 ;922370,922380,922400,932370,932390,932400,942380, 

 ;942390,942400,942410,952410,962420,000000,000000/ 

 data dactp/1.,1.28E-05,2.57E-08,8.45E-09,1.78E-07,1., 

 ;1.13E-07,4.17E-09,1.52E-05,3.11E-06,6.62E-08,1.07E-07,8.06E-06, 

 ;1.16E-07,2.97E-06,2.55E-06,7.46E-05,1.,1.,1./ 

 data dactin/2.99E-12,2.85E-13,3.33E-07,1.39E-13,8.98E-14,3.12E-17, 

 ;1.19E-06,4.92E-18,1.37E-05,1.03E-14,3.41E-06,1.78E-04,2.50E-10, 

 ;9.13E-13,3.36E-12,1.53E-09,5.08E-11,4.92E-08,1.,1./ 

 data a/ 

 ;'-1', 

 ;'-1', 

 ;'-1', 

 ;'BAS 1E14 FISSIONS', 

 ;'LIB 0 1 2 3 0 0 0 9 3 0 1 15', 

 ;'PHO 101 102 103 10', 

 ;'CUT 7 0.0 25 -1. 26 -1. 27 .1 -1', 

 ;'OPTL 8 8 8 8 8 8 5 17*8', 

 ;'OPTA 8 8 8 8 8 8 5 17*8', 

 ;'OPTF 8 8 8 8 8 8 5 17*8', 

 ;'RDA title for run', 

 ;'TIT test of inventory mix', 

 ;'RDA put cinder u235 ff inventory in vector -1', 

 ;'INP -1 2 -1 -1 1 1', 

 ;'RDA put cinder u238 ff inventory in vector -2', 

 ;'INP -2 2 -1 -1 1 1', 

 ;'RDA put cinder pu239 ff inventory in vector -3', 

 ;'INP -3 2 -1 -1 1 1', 

 ;'RDA put endf6 u235 14 inventory in vector -4', 

 ;'INP -4 2 -1 -1 1 1', 

 ;'RDA put endf6 u238 14 inventory in vector -5', 

 ;'INP -5 2 -1 -1 1 1', 

 ;'RDA put endf6 pu239 14 inventory in vector -6', 

 ;'INP -6 2 -1 -1 1 1', 

 ;'RDA move fraction of cinder u235 ff inventory to vector 1', 

 ;'MOV -1 1 0 1.0', 

 ;'RDA add fraction of cinder u238 ff inventory to vector 1', 

 ;'ADD -2 1 0 1.0', 

 ;'RDA add fraction of cinder pu239 ff inventory to vector 1', 

 ;'ADD -3 1 0 1.0', 

 ;'RDA move fraction of endf6 u235 14 inventory to vector 1', 

 ;'ADD -4 1 0 1.0', 

B-18
 ;'RDA add fraction of endf6 u238 14 inventory to vector 1', 

 ;'ADD -5 1 0 1.0', 

 ;'RDA add fraction of endf6 pu239 14 inventory to vector 1', 

 ;'ADD -6 1 0 1.0', 

 ;'RDA put actinide inventory in vector -7', 

 ;'INP -7 2 -1 -1 1 1', 

 ;'RDA add fraction of actinide inventory to vector -7', 

 ;'ADD -7 1 0 1.0', 

 ;'RDA put activated light element inventory in vector -8', 

 ;'INP -8 2 -1 -1 1 1', 

 ;'RDA add fraction of light element inventory to vector -8', 

 ;'ADD -8 1 0 1.0', 

 ;'HED 1 CHARGE'/ 

 data b/ 

 ;'RDA decay inv in vector 1 to .001s, put results in vector -1', 

 ;'DEC 2.778E-7 1 -1 3 0 ', 

 ;'DEC 5.985E-7 -1 -2 3 0 ', 

 ;'DEC 1.289E-6 -2 -3 3 0 ', 

 ;'DEC 2.778E-6 -3 -4 3 0 ', 

 ;'DEC 5.985E-6 -4 -5 3 0 ', 

 ;'DEC 1.289E-5 -5 -6 3 0 ', 

 ;'DEC 2.778E-5 -6 -7 3 0 ', 

 ;'DEC 5.985E-5 -7 -8 3 0 ', 

 ;'DEC 1.289E-4 -8 -9 3 0 ', 

 ;'DEC 2.778E-4 -9 -10 3 0 ', 

 ;'DEC 5.985E-4 -10 -11 3 0 ', 

 ;'DEC 1.289E-3 -11 -12 3 0 ', 

 ;'DEC 2.778E-3 -12 -13 3 0 ', 

 ;'DEC 5.985E-3 -13 -14 3 0 ', 

 ;'DEC 1.289E-2 -14 -15 3 0 ', 

 ;'DEC 2.778E-2 -15 -16 3 0 ', 

 ;'DEC 5.985E-2 -16 -17 3 0 ', 

 ;'DEC 1.289E-1 -17 -18 3 0 ', 

 ;'DEC 2.778E-1 -18 -19 3 0 ', 

 ;'DEC 5.985E-1 -19 -20 3 0 ', 

 ;'DEC 1.289E+0 -20 -21 3 0 ', 

 ;'DEC 2.778E+0 -21 -22 3 0 ', 

 ;'DEC 5.985E+0 -22 -23 3 0 ', 

 ;'DEC 1.289E+1 -23 -24 3 0 ', 

 ;'DEC 2.778E+1 -24 -25 3 0 ', 

 ;'DEC 5.985E+1 -25 -26 3 0 ', 

 ;'DEC 1.289E+2 -26 -27 3 0 ', 

 ;'DEC 2.778E+2 -27 -28 3 0 ', 

 ;'DEC 5.985E+2 -28 -29 3 0 ', 

 ;'DEC 1.289E+3 -29 -30 3 0 ', 

 ;'DEC 2.778E+3 -30 -31 3 0 ', 

 ;'DEC 5.985E+3 -31 -32 3 0 ', 

 ;'DEC 1.289E+4 -32 -33 3 0 ', 

 ;'DEC 2.778E+4 -33 -34 3 0 ', 

 ;'DEC 5.985E+4 -34 -35 3 0 ', 

 ;'DEC 1.289E+5 -35 -36 3 0 ', 

 ;'DEC 2.778E+5 -36 -37 3 0 ', 

 ;'DEC 5.985E+5 -37 -38 3 0 ', 

 ;'DEC 1.289E+6 -38 -39 3 0 ', 

 ;'DEC 2.778E+6 -39 -40 3 0 '/ 

c 

c ..... 

c use data from fiidos 

c ..... 

 ntimes=nmeas+nexp 

 if(itpm.eq.2)ntimes=ntimes+nexp 

 do 10 n=1,nmeas 

 times(n)=xtmeas(n) 

 10 continue 

 do 20 n=1,nexp 

 times(n+nmeas)=xtexp(n) 

 if(itpm.eq.2)times(n+nmeas+nexp)=xtexp(n+nexp) 

B-19
 20 continue 

c 

 if(iactp.ne.0) then 

 nactp=yyy 

 do 30 i=1,nactp 

 ile(i)=idactp(i) 

 ale(i)=actpp(i) 

 30 continue 

 else 

 nactp=1 

 ile(1)=0 

 ale(1)=0. 

 endif 

c 

 if(iactin.ne.0) then 

 nactin=xxx 

 do 40 i=1,nactin 

 ihe(i)=idactin(i) 

 ahe(i)=actinp(i) 

 40 continue 

 else 

 nactin=1 

 ihe(1)=0 

 ahe(1)=0. 

 endif 

c ..... 

c set up desired decay times based on standard decay times 

c ..... 

 intmax=1 

 do 50 nt=1,ntimes 

 bigind=3*log10(times(nt)/2.778e-7)+.99999 

 tindex(nt)=min(bigind,40.) 

 xtra(nt)=times(nt)-2.778e-7*10.**((tindex(nt)-1.)/3.) 

 intmax=max(tindex(nt),intmax) 

 50 continue 

 open(unit=3,file='orgsrc.dat',status='old') 

 open(unit=2,file='tape5.inp') 

c 

 write(2,90)(a(i),i=1,11) 

 write(2,100)title 

 write(2,90)(a(i),i=13,25) 

 write(2,101)u235ff*1.e-6 

 write(2,90)a(27) 

 write(2,102)u238ff*1.e-6 

 write(2,90)a(29) 

 write(2,103)pu239ff*1.e-6 

 write(2,90)a(31) 

 write(2,104)u23514*1.e-6 

 write(2,90)a(33) 

 write(2,105)u23814*1.e-6 

 write(2,90)a(35) 

 write(2,106)pu23914*1.e-6 

 if(nactin.ne.0)then 

 write(2,90)(a(i),i=37,40) 

 endif 

 if(nactp.ne.0)then 

 write(2,90)(a(i),i=41,44) 

 endif 

 write(2,90)a(45) 

 write(2,90)(b(nt),nt=1,intmax+1) 

 do 60 nt=1,ntimes 

 write(2,108)xtra(nt),-1*tindex(nt),-1*(nt+40),3,1 

 60 continue 

 write(2,107) 

 write(2,108)xtra(1),-1*tindex(1),2,3,1 

 write(2,109)2,times(1) 

 write(2,110)2 

B-20
 70 read(3,90,end=80)c 

 write(2,90)c 

 go to 70 

 80 continue 

 write(2,111) 

 ; (ihe(i),ahe(i)/dactin(i)*3.7e10/6.023e23/1.45e+9,i=1,nactin),0,0. 

 write(2,113) 

 write(2,112) 

 ; (ile(i),ale(i)/dactp(i)*3.7e10/6.023e23/1.45e+9,i=1,nactp),0,0. 

 write(2,113) 

 write(2,114) 

c 

90 format(a80) 

95 format(1p,e10.3,i5,e10.3) 

100 format('TIT ',a80) 

101 format('MOV -1 1 0 ',1pg10.3) 

102 format('ADD -2 1 0 ',1p,g10.3) 

103 format('ADD -3 1 0 ',1p,g10.3) 

104 format('ADD -4 1 0 ',1pg10.3) 

105 format('ADD -5 1 0 ',1p,g10.3) 

106 format('ADD -6 1 0 ',1p,g10.3) 

107 format('RDA DUMMY DECAY') 

108 format('DEC ',g12.5,4i6) 

109 format('HED ',i3,1x,1pg8.2,'H') 

110 format('OUT ',i3,' 1 -1 0') 

111 format(('2',4(1x,i6,1p,e12.5))) 

112 format(('1',4(1x,i6,1p,e12.5))) 

113 format(' 0') 

114 format('END') 

c 

 close(unit=3) 

 close(unit=2) 

 return 

 end 

B-21
 subroutine rri 

 include 'fiparms.f' 

 include 'varblock.f' 

c calculates the relative radionuclide inventory for the purpose of 

c providing data to be used to modify the relative gamma emission spectum 

c .... 

c indices for control of inventory treatment 

c variable ikrxer - index for treatment of noble gases 

c variable iactp - index for treatment of activation products 

c variable iactin - index for treatment of actinides 

c variable ifrac - index for treatment of fractionation of fission products 

c 0) no treatment 1) treatment required 

c ..... 

c calculate gross fission product inventory 

c ..... 

 call gfpi 

c ..... 

c remove krypton and xenon if desired 

c ..... 

 if(ikrxer.eq.1) call krxeri 

c ..... 

c add activation products if desired 

c ..... 

 if(iactp.eq.1) call actpi 

c ..... 

c add actinides if desired 

c ..... 

 if(iactin.eq.1) call actini 

c ..... 

c fractionate results if desired 

c ..... 

 if(ifrac.eq.1) call fraci 

 return 

 end 

B-22
 subroutine gfpi 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine accepts the relative radiological inventory of fission 

c products from calculations of origen2. 

c ..... 

c array afp(i) -relativve inventory of fission products 

c given in units of curies per 10**14 fissions. 

c variable acttot - total activity from all radionuclides 

c array lookfp(i) - lookup fission product # i in origen2 inventory 

c array xnew(i,j) - origen2 inventory isotope j; time i 

c array dis(i) - decay constant for origen2 isotope i (sec-1) 

c array q(i) - energy per disintegration (watts) 

c variable ertfpf - energy rate for fiidos fiss prod inventory 

c variable e50fpf - 50 yr cum energy from fiidos fiss prod inventory 

c variable ertfpo - energy rate for origen2 fiss prod inventory 

c variable e50fpo - 50 yr cum energy from origen2 fiss prod inventory 

c ..... 

c commons from origen2 

 INCLUDE 'params.f' 

 DIMENSION XNEW(AAAA,BBBB),COEFF(CCCC,BBBB),NPROD(CCCC,BBBB), 

 $MMAX(BBBB),KAP(BBBB) 

 COMMON /BIG/NUCL(BBBB),Q(BBBB),FG(0004),TOCAP(BBBB),GENNEU(GGGG), 

 $ALPHAN(GGGG),SPONF(GGGG),SFNU(GGGG),FISS(GGGG),NUCAB(BBBB), 

 $AMPC(BBBB),WMPC(BBBB),XSTORE(JJJJ,BBBB),DIS(BBBB),B(BBBB), 

 $ABUND(KKKK),NON0(BBBB),KD(BBBB),LOC(DDDD),NGF(BBBB),NGN(BBBB), 

 $NGR(LLLL),GGR(LLLL),AA(DDDD),LOCA(DDDD),NFUDFP(FFFF,OOOO) 

 COMMON /NUDSCR/DUM1(CCCC,BBBB),DUM2(HHHH,BBBB),S(2),CIMN(BBBB), 

 $ CSUM(BBBB),NONP(BBBB),NQ(BBBB),XP(BBBB),XPAR(BBBB),XTEMP(BBBB), 

 $ D(BBBB),AP(IIII),LOCP(IIII),LONG(BBBB) 

 EQUIVALENCE (DUM1(1,1),COEFF(1,1)),(DUM2(1,1),NPROD(1,1)), 

 $(NONP(1),MMAX(1)),(KAP(1),NQ(1)),(XNEW(1,1),DUM1(1,1)) 

c ..... 

 ertfpf=0. 

 e50fpf=0. 

 do 10 i=1,www 

 mmm=lookfp(i) 

 value=XSTORE(tmindx+40,mmm) 

 afp(i)=value*DIS(mmm)*1.6283e13 

 ertfpf=ertfpf+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50fpf=e50fpf+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 10 continue 

c 

 ertfpo=0. 

 e50fpo=0. 

 do 20 mmm=818,1598 

 value=XSTORE(tmindx+40,mmm) 

 ertfpo=ertfpo+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50fpo=e50fpo+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 20 continue 

c ..... 

c calculate total activity 

c ..... 

 acttot=0.0 

 do 30 i=1,www 

 acttot=acttot+afp(i) 

 30 continue 

 return 

 end 

c ..... 

 blockdata lookdata 

 include 'fiparms.f' 

 include 'varblock.f' 

B-23
 data lookfp/ 

 +870,896,904,905,911,919,920,921,928,934, 

 +935,941,942,946,947,948,956,957,958,959, 

 +965,966,967,968,974,975,982,983,985,986, 

 +993,1000,1001,1002,1008,1016,1017,1018,1029,1037, 

 +1038,1039,1052,1053,1059,1060,1067,1068,1069,1077, 

 +1083,1084,1085,1086,1087,1093,1094,1103,1122,1124, 

 +1126,1135,1143,1161,1181,1259,1268,1276,1278,1279, 

 +1288,1289,1299,1300,1301,1318,1319,1320,1321,1327, 

 +1328,1331,1338,1339,1340,1341,1342,1346,1347,1348, 

 +1349,1353,1354,1355,1356,1358,1359,1365,1366,1369, 

 +1370,1374,1375,1376,1377,1385,1391,1392,1393,1398, 

 +1399,1406,1407,1411,1412,1413,1418,1419,1420,1425, 

 +1426,1434,1435,1436,1442,1443,1444,1451,1452,1460, 

 +1461,1468,1469,1470,1471,1477,1479,1480,1489,1503, 

 +1504,1513,1522,1530,1539,1545,1569,1597,1599,1600/ 

 data lookap/ 

 +1600, 38,118,124,128, 1600 ,130,132,147,150, 

 +605,610,613,614,656,657,120, 3*1600/ 

 data lookan/ 

 +738,739,743,753,754,755,757,758,760,765, 

 +767,768,773,774,775,776,784,793, 2*1600/ 

 end 

B-24
 subroutine krxeri 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine removes krypton and xenon (noble gases) from inventory and 

c records amount of removed inventory so that gamma energy spectrum can be 

c modified. 

c ..... 

c array afp(i) - amount of radionuclide i determined for time of concern. 

c array akrxer(j)- amount of noble gas j removed from inventory 

c at time of concern. 

c array noble(j) - radionuclide position corresponding to j th noble gas. 

c ..... 

 dimension noble(13) 

 data noble/4,7,8,10,12,14,87,96,97,103,104,107,110/ 

c ..... 

 10 continue 

 do 20 j=1,13 

 akrxer(j)=afp(noble(j)) 

 afp(noble(j))=0.0 

 acttot=acttot-akrxer(j) 

 20 continue 

 return 

 end 

B-25
 subroutine actpi 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine accepts the relative radionuclide inventory 

c of activation products from calculations of origen2. 

c ..... 

c the twenty radionuclides are: 

c (1) be-7 (2) na-24 (3) mn-54 (4) fe-55 

c (5) fe-59 (6) co-57 (7) co-58 (8) co-60 

c (9) cu-64 (10)cu-67 (11) w-181 (12) w-185 

c (13) w-187 (14) w-188 (15)au-198 (16)au-199 

c (17)pb-203 (18)mn-56 (19)not used (20)not used 

c array aactp(i) - relative inventory of activation product radionuclides 

c given in units of curie per 10**14 fissions. 

c array lookap(i) - lookup activation product # i in origen2 inventory 

c array xnew(i,j) - origen2 inventory isotope j; time i 

c array dis(i) - decay constant for origen2 isotope i (sec-1) 

c array q(i) - energy per disintegration (watts) 

c variable ertapf - energy rate for fiidos act prod inventory 

c variable e50apf - 50 yr cum energy from fiidos act prod inventory 

c variable ertapo - energy rate for origen2 act prod inventory 

c variable e50apo - 50 yr cum energy from origen2 act prod inventory 

c ..... 

c common from origen2 

 INCLUDE 'params.f' 

 DIMENSION XNEW(AAAA,BBBB),COEFF(CCCC,BBBB),NPROD(CCCC,BBBB), 

 $MMAX(BBBB),KAP(BBBB) 

 COMMON /BIG/NUCL(BBBB),Q(BBBB),FG(0004),TOCAP(BBBB),GENNEU(GGGG), 

 $ALPHAN(GGGG),SPONF(GGGG),SFNU(GGGG),FISS(GGGG),NUCAB(BBBB), 

 $AMPC(BBBB),WMPC(BBBB),XSTORE(JJJJ,BBBB),DIS(BBBB),B(BBBB), 

 $ABUND(KKKK),NON0(BBBB),KD(BBBB),LOC(DDDD),NGF(BBBB),NGN(BBBB), 

 $NGR(LLLL),GGR(LLLL),AA(DDDD),LOCA(DDDD),NFUDFP(FFFF,OOOO) 

 COMMON /NUDSCR/DUM1(CCCC,BBBB),DUM2(HHHH,BBBB),S(2),CIMN(BBBB), 

 $ CSUM(BBBB),NONP(BBBB),NQ(BBBB),XP(BBBB),XPAR(BBBB),XTEMP(BBBB), 

 $ D(BBBB),AP(IIII),LOCP(IIII),LONG(BBBB) 

 EQUIVALENCE (DUM1(1,1),COEFF(1,1)),(DUM2(1,1),NPROD(1,1)), 

 $(NONP(1),MMAX(1)),(KAP(1),NQ(1)),(XNEW(1,1),DUM1(1,1)) 

c ..... 

 ertapf=0. 

 e50apf=0. 

 do 10 i=1,yyy 

 mmm=lookap(i) 

 value=XSTORE(tmindx+40,mmm) 

 aactp(i)=value*DIS(mmm)*1.6283e13 

 ertapf=ertapf+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50apf=e50apf+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 10 continue 

c 

 ertapo=0. 

 e50apo=0. 

 do 20 mmm=1,688 

 value=XSTORE(tmindx+40,mmm) 

 ertapo=ertapo+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50apo=e50apo+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 20 continue 

c ..... 

c calculate total activity 

c ..... 

 do 30 i=1,yyy 

 acttot=acttot+aactp(i) 

 30 continue 

 return 

 end 

B-26
 subroutine actini 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine calculates the relative radionuclide inventory of 

c actinide elements from calculations of origen2. 

c ..... 

c the twenty radionuclides are: 

c (1) th-229 (2) th-230 (3) th-234 (4) u-233 

c (5) u-234 (6) u-235 (7) u-237 (8) u-238 

c (9) u-240 (10)np-237 (11)np-239 (12)np-240 

c (13)pu-238 (14)pu-239 (15)pu-240 (16)pu-241 

c (17)am-241 (18)cm-242 (19)not used (20)not used 

c array aactin(i) - relative inventory of actinide radionuclides given 

c in units of curie per 10**14 fissions. 

c array lookan(i) - lookup actinide # i in origen2 inventory 

c array xnew(i,j) - origen2 inventory isotope i; time j 

c array dis(i) - decay constant for origen2 isotope i (sec-1) 

c array q(i) - energy per disintegration (watts) 

c variable ertanf - energy rate for fiidos actinide inventory 

c variable e50anf - 50 yr cum energy from fiidos actinide inventory 

c variable ertano - energy rate for origen2 actinide inventory 

c variable e50ano - 50 yr cum energy from origen2 actinide inventory 

c ..... 

c commons from origen2 

 INCLUDE 'params.f' 

 DIMENSION XNEW(AAAA,BBBB),COEFF(CCCC,BBBB),NPROD(CCCC,BBBB), 

 $MMAX(BBBB),KAP(BBBB) 

 COMMON /BIG/NUCL(BBBB),Q(BBBB),FG(0004),TOCAP(BBBB),GENNEU(GGGG), 

 $ALPHAN(GGGG),SPONF(GGGG),SFNU(GGGG),FISS(GGGG),NUCAB(BBBB), 

 $AMPC(BBBB),WMPC(BBBB),XSTORE(JJJJ,BBBB),DIS(BBBB),B(BBBB), 

 $ABUND(KKKK),NON0(BBBB),KD(BBBB),LOC(DDDD),NGF(BBBB),NGN(BBBB), 

 $NGR(LLLL),GGR(LLLL),AA(DDDD),LOCA(DDDD),NFUDFP(FFFF,OOOO) 

 COMMON /NUDSCR/DUM1(CCCC,BBBB),DUM2(HHHH,BBBB),S(2),CIMN(BBBB), 

 $ CSUM(BBBB),NONP(BBBB),NQ(BBBB),XP(BBBB),XPAR(BBBB),XTEMP(BBBB), 

 $ D(BBBB),AP(IIII),LOCP(IIII),LONG(BBBB) 

 EQUIVALENCE (DUM1(1,1),COEFF(1,1)),(DUM2(1,1),NPROD(1,1)), 

 $(NONP(1),MMAX(1)),(KAP(1),NQ(1)),(XNEW(1,1),DUM1(1,1)) 

c ..... 

 ertanf=0. 

 e50anf=0. 

 do 10 i=1,xxx 

 mmm=lookan(i) 

 value=XSTORE(tmindx+40,mmm) 

 aactin(i)=value*DIS(mmm)*1.6283e13 

 ertanf=ertanf+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50anf=e50anf+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 10 continue 

c 

 ertano=0. 

 e50ano=0. 

 do 20 mmm=689,817 

 value=XSTORE(tmindx+40,mmm) 

 ertano=ertano+value*Q(mmm)/1.6e-13 

 if(DIS(mmm).ne.0) 

 $ e50ano=e50ano+value*Q(mmm)/1.6e-13/DIS(mmm)* 

 $ (1-exp(-1.*DIS(mmm)*50.*365.*24.*3600.)) 

 20 continue 

c ..... 

c calculate total activity 

c ..... 

 do 30 i=1,xxx 

 acttot=acttot+aactin(i) 

 30 continue 

 return 

 end 

B-27
 subroutine fraci 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine modifies the relative radionuclide inventory of fission 

c products with user supplied fractionation factors. 

c ..... 

c the one hundred and fifty radionuclides are: 

c (1) se-79 (2) br-82 (3) br-83 (4) kr-83m (5) br-84 

c (6) br-85 (7) kr-85 (8) kr-85m (9) rb-86 (10) kr-87 

c (11) rb-87 (12) kr-88 (13) rb-88 (14) kr-89 (15) rb-89 

c (16) sr-89 (17) rb-90 (18) rb-90m (19) sr-90 (20) y-90 

c (21) rb-91 (22) sr-91 (23) y-91 (24) y-91m (25) sr-92 

c (26) y-92 (27) sr-93 (28) y-93 (29) zr-93 (30) nb-93m 

c (31) y-94 (32) y-95 (33) zr-95 (34) nb-95 (35) y-96 

c (36) zr-97 (37) nb-97 (38) nb-97m (39) nb-98m (40) mo-99 

c (41) tc-99 (42) tc-99m (43) mo-101 (44) tc-101 (45) mo-102 

c (46) tc-102 (47) tc-103 (48) ru-103 (49) rh-103m (50) tc-104 

c (51) mo-105 (52) tc-105 (53) ru-105 (54) rh-105 (55) rh-105m 

c (56) ru-106 (57) rh-106 (58) pd-107 (59) rh-109 (60) pd-109 

c (61) ag-109m (62) ag-110m (63) ag-111 (64) cd-113m (65) cd-115m 

c (66) sn-123 (67) sb-124 (68) sn-125 (69) sb-125 (70) te-125m 

c (71) sn-126 (72) sb-126 (73) sb-127 (74) te-127 (75) te-127m 

c (76) sb-129 (77) te-129 (78) te-129m (79) i-129 (80) sn-130 

c (81) sb-130m (82) i-130 (83) sb-131 (84) te-131 (85) te-131m 

c (86) i-131 (87) xe-131m (88) sb-132 (89) sb-132m (90) te-132 

c (91) i-132 (92) sb-133 (93) te-133 (94) te-133m (95) i-133 

c (96) xe-133 (97) xe-133m (98) te-134 (99) i-134 (100)cs-134 

c (101)cs-134m (102) i-135 (103)xe-135 (104)xe-135m (105)cs-135 

c (106)cs-136 (107)xe-137 (108)cs-137 (109)ba-137m (110)xe-138 

c (111)cs-138 (112)cs-139 (113)ba-139 (114)cs-140 (115)ba-140 

c (116)la-140 (117)ba-141 (118)la-141 (119)ce-141 (120)ba-142 

c (121)la-142 (122)la-143 (123)ce-143 (124)pr-143 (125)ce-144 

c (126)pr-144 (127)pr-144m (128)ce-145 (129)pr-145 (130)ce-146 

c (131)pr-146 (132)ce-147 (133)pr-147 (134)nd-147 (135)pm-147 

c (136)pr-148 (137)pm-148 (138)pm-148m (139)pm-149 (140)pm-151 

c (141)sm-151 (142)eu-152 (143)sm-153 (144)eu-154 (145)eu-155 

c (146)eu-156 (147)tb-160 (148)ho-166m (149)not used (150)not used 

c array afp(i) - relative radionuclide inventory of fission products in units 

c of curies per 10**14 fissions. 

c array afracc(id(i))-change in the amount of relative radionuclide inventory 

c for the i th fractionated fission product. 

c array id(i) - fission product number for the i th fractionated fission 

c product. 

c ..... 

 do 10 i=1,nfrac 

 afracc(i)=(ffrac(i)-1.)*afp(id(i)) 

 afp(id(i))=afp(id(i))*ffrac(i) 

 acttot=acttot+afracc(i) 

 10 continue 

 return 

 end 

B-28
 subroutine rges 

 include 'fiparms.f' 

 include 'varblock.f' 

c calculates the relative radionuclide gamma energy spectrum for the purpose of 

c providing data to be used to in subroutine sfcalc. 

c ..... 

c indices for control of inventory treatment are: 

c variable ikrxer - index for treatment of noble gases 

c variable iactp - index for treatment of activation products 

c variable iactin - index for treatment of actinides 

c variable ifrac - index for treatment of fractionation of fission products 

c 0) no treatment 1) treatment required 

c ..... 

c calculate gross fission product gamma spectrum 

c ..... 

 call gfpg 

c ..... 

c remove krypton and xenon if desired 

c ..... 

 if(ikrxer.eq.1) call krxerg 

c ..... 

c add activation products if desired 

c ..... 

 if(iactp.eq.1) call actpg 

c ..... 

c add actinides if desired 

c ..... 

 if(iactin.eq.1) call acting 

c ..... 

c fractionate results if desired 

c ..... 

 if(ifrac.eq.1) call fracg 

 return 

 end 

B-29
 subroutine gfpg 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine accepts the relative radiological gamma energy spectrum 

c of fission products from calculations of origen2. 

c ..... 

c array spec(j) - relative gamma emission spectrum for energy group j 

c of the fission products 

c array gspec(j,k,l)-rel gammma energy spectrum from origen2 

c energy group j; isotope type k; time loc l 

c ..... 

c common from origen2 

 common /spectra/ gspec(ooo,3,zzz) 

c ..... 

 do 10 j=1,ooo 

 spec(j)=gspec(j,3,tmindx) 

 10 continue 

c convert from gamma/sec to gamma/hr 

 do 20 j=1,ooo 

 spec(j)=spec(j)*3600. 

 20 continue 

 return 

 end 

B-30
 subroutine krxerg 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine calculates the spectrum produced by krypton and xenon (noble 

c gases) and removes it from the relative radionuclide gamma 

c spectrum at the time of concern. 

c ..... 

c array akrxer(i)- amount of noble gas i removed from inventory 

c at time of concern. 

c array gamma(j) - photons per disintegration for each energy group i. read in 

c one isotope at a time. 

c array spec(j) - relative gamma energy spectrum for energy group j modified 

c by subtracting the spectrum of the noble gases. 

c ..... 

 10 continue 

 open(unit=2,file='krxe.gam',status='old') 

 20 continue 

 do 30 j=1,ooo 

 skrxer(j)=0.0 

 30 continue 

 do 40 i=1,13 

 read(2,*)(gamma(j),j=1,ooo) 

 do 40 j=1,ooo 

 skrxer(j)=skrxer(j)+akrxer(i)*gamma(j) 

 40 continue 

 do 50 j=1,ooo 

 skrxer(j)=skrxer(j)*1.332e+14 

 spec(j)=spec(j)-skrxer(j) 

 50 continue 

 close(unit=2) 

 return 

 end 

B-31
 subroutine actpg 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine accepts the gamma energy spectrum of activation products 

c from calculations of origen2 

c and adds it to the relative radionuclide gamma spectrum at time of concern 

c ..... 

c the twenty radionuclides are: 

c (1) be-7 (2) na-24 (3) mn-54 (4) fe-55 

c (5) fe-59 (6) co-57 (7) co-58 (8) co-60 

c (9) cu-64 (10)cu-67 (11) w-181 (12) w-185 

c (13) w-187 (14) w-188 (15)au-198 (16)au-199 

c (17)pb-203 (18)mn-56 (19)not used (20)not used 

c array sactp(j) - relative gamma energy spectrum for energy group j 

c of the activation products. 

c array spec(j) - relative gamma energy spectrum for energy group j which is 

c modified by adding spectrum of the activation products. 

c array gspec(j,k,l)-rel gammma energy spectrum from origen2 

c energy group j; isotope type k; time loc l 

c common from origen2 

 common /spectra/ gspec(ooo,3,zzz) 

c ..... 

 do 10 j=1,ooo 

 sactp(j)=gspec(j,1,tmindx) 

 10 continue 

c convert from gamma/sec to gamma/hr 

 do 20 j=1,ooo 

 sactp(j)=sactp(j)*3600. 

 spec(j)=spec(j)+sactp(j) 

 20 continue 

 return 

 end 

B-32
 subroutine acting 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine accepts the gamma energy spectrum of actinide elements 

c from calculations of origen2. 

c and adds it to the relative radionuclide gamma spectrum at time of concern 

c ..... 

c the twenty radionuclides are: 

c (1) th-229 (2) th-230 (3) th-234 (4) u-233 

c (5) u-234 (6) u-235 (7) u-237 (8) u-238 

c (9) u-240 (10)np-237 (11)np-239 (12)np-240 

c (13)pu-238 (14)pu-239 (15)pu-240 (16)pu-241 

c (17)am-241 (18)cm-242 (19)not used (20)not used 

c array sactin(j) - relative gamma energy spectrum for energy group j 

c of the actinides. 

c array spec(j) - relative gamma energy spectrum for energy group j which 

c is modified by adding spectrum of the actinides. 

c array gspec(j,k,l)-rel gammma energy spectrum from origen2 

c energy group j; isotope type k; time loc l 

c ..... 

c common from origen2 

 common /spectra/ gspec(ooo,3,zzz) 

c ..... 

 do 10 j=1,ooo 

 sactin(j)=gspec(j,2,tmindx) 

 10 continue 

c convert from gamma/sec to gamma/hr 

 do 20 j=1,ooo 

 sactin(j)=sactin(j)*3600. 

 spec(j)=spec(j)+sactin(j) 

 20 continue 

 return 

 end 

B-33
 subroutine fracg 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine modifies the gamma energy spectrum caused by the 

c the fractionation of fission products at the time of concern. 

c ..... 

c the one hundred and fifty radionuclides are: 

c (1) se-79 (2) br-82 (3) br-83 (4) kr-83m (5) br-84 

c (6) br-85 (7) kr-85 (8) kr-85m (9) rb-86 (10) kr-87 

c (11) rb-87 (12) kr-88 (13) rb-88 (14) kr-89 (15) rb-89 

c (16) sr-89 (17) rb-90 (18) rb-90m (19) sr-90 (20) y-90 

c (21) rb-91 (22) sr-91 (23) y-91 (24) y-91m (25) sr-92 

c (26) y-92 (27) sr-93 (28) y-93 (29) zr-93 (30) nb-93m 

c (31) y-94 (32) y-95 (33) zr-95 (34) nb-95 (35) y-96 

c (36) zr-97 (37) nb-97 (38) nb-97m (39) nb-98m (40) mo-99 

c (41) tc-99 (42) tc-99m (43) mo-101 (44) tc-101 (45) mo-102 

c (46) tc-102 (47) tc-103 (48) ru-103 (49) rh-103m (50) tc-104 

c (51) mo-105 (52) tc-105 (53) ru-105 (54) rh-105 (55) rh-105m 

c (56) ru-106 (57) rh-106 (58) pd-107 (59) rh-109 (60) pd-109 

c (61) ag-109m (62) ag-110m (63) ag-111 (64) cd-113m (65) cd-115m 

c (66) sn-123 (67) sb-124 (68) sn-125 (69) sb-125 (70) te-125m 

c (71) sn-126 (72) sb-126 (73) sb-127 (74) te-127 (75) te-127m 

c (76) sb-129 (77) te-129 (78) te-129m (79) i-129 (80) sn-130 

c (81) sb-130m (82) i-130 (83) sb-131 (84) te-131 (85) te-131m 

c (86) i-131 (87) xe-131m (88) sb-132 (89) sb-132m (90) te-132 

c (91) i-132 (92) sb-133 (93) te-133 (94) te-133m (95) i-133 

c (96) xe-133 (97) xe-133m (98) te-134 (99) i-134 (100)cs-134 

c (101)cs-134m (102) i-135 (103)xe-135 (104)xe-135m (105)cs-135 

c (106)cs-136 (107)xe-137 (108)cs-137 (109)ba-137m (110)xe-138 

c (111)cs-138 (112)cs-139 (113)ba-139 (114)cs-140 (115)ba-140 

c (116)la-140 (117)ba-141 (118)la-141 (119)ce-141 (120)ba-142 

c (121)la-142 (122)la-143 (123)ce-143 (124)pr-143 (125)ce-144 

c (126)pr-144 (127)pr-144m (128)ce-145 (129)pr-145 (130)ce-146 

c (131)pr-146 (132)ce-147 (133)pr-147 (134)nd-147 (135)pm-147 

c (136)pr-148 (137)pm-148 (138)pm-148m (139)pm-149 (140)pm-151 

c (141)sm-151 (142)eu-152 (143)sm-153 (144)eu-154 (145)eu-155 

c (146)eu-156 (147)tb-160 (148)ho-166m (149)not used (150)not used 

c array afracc(i)- amount of relative radionuclide inventory for fiss products 

c changed by fractionation. 

c array gamma(j) - photons per disintegration for each energy group j read in 

c one isotope at a time. 

c array spec(j) - relative gamma energy spectrum for energy group j modified 

c by change in spectrum from fractionation of fiss products. 

c ..... 

 10 continue 

 open(unit=2,file='frac.gam',status='old') 

 20 continue 

 do 30 j=1,ooo 

 sfracc(j)=0.0 

 30 continue 

 do 40 i=1,nfrac 

 read(2,*)(gamma(j),j=1,ooo) 

 do 40 j=1,ooo 

 sfracc(j)=sfracc(j)+afracc(i)*gamma(j) 

 40 continue 

 do 50 j=1,ooo 

 sfracc(j)=sfracc(j)*1.332e+14 

 spec(j)=spec(j)+sfracc(j) 

 50 continue 

 close(unit=2) 

 return 

 end 

B-34
 subroutine sfcalc 

 include 'fiparms.f' 

 include 'varblock.f' 

c this subroutine calculates the scaling factor that specifies the radiological 

c contamination in units of 10**14 fissions per m**2 or m**3. 

c ..... 

c variable itrm - index for type of radiological measurement 

c the six types of measurement are 

c (1) radiation intensity above contaminated surface 

c (2) radiation intensity inside debris cloud 

c (3) radiation intensity below debris cloud 

c (4) gross activity - airborne concentration 

c (5) gross activity - surface concentration 

c (6) gross activity - inhalation or ingestion intake 

c array spec(j) - relative gamma emission spectrum at time of measurement 

c (gamma/hr per 10**14 fissions). 

c variable acttot - total relative activity of radiological material 

c (curie per 10**14 fissions). 

c array xactmes(t)- measured activity of radiological material 

c (curie,curie per m**2, or curie per m**3) at 

c time index t. 

c array gref(j) - gamma radiation exposure factor for surface, in-cloud, 

c or below-cloud measurement instrument itmi 

c (r/hr per gamma/hr/m**2). 

c variable sf - scaling factor (10*14 fissions per m**2 or m**3) 

c array xrimes(t) - measured radiation intensity(r/hr)at time index t 

c ..... 

 10 continue 

 20 if(xitrm(tmindx).gt.3) go to 90 

c ..... 

c xitrm=1,2,3 

c ..... 

 30 if(xitrm(tmindx).eq.1) open(unit=2,file='gref.sur',status='old') 

 if(xitrm(tmindx).eq.2) open(unit=2,file='gref.inc',status='old') 

 if(xitrm(tmindx).eq.3) open(unit=2,file='gref.blc',status='old') 

 40 continue 

 do 50 j=1,xitmi(tmindx) 

 read(2,*)(gref(i),i=1,nnn) 

 50 continue 

 do 60 i=1,nnn 

 gref(i)=gref(i)/1.e+4 

 60 continue 

 es=0.0 

 do 70 i=1,15 

 es=es+spec(i)*gref(nnn+1-i) 

 70 continue 

 es=es+ 0.55*spec(16)*gref(6) 

 es=es+ 0.45*spec(16)*gref(5) 

 80 continue 

 sf=xrimes(tmindx)/es 

 close(unit=2) 

 go to 110 

c ..... 

c xitrm=4,5,6 

c ..... 

 90 continue 

 if(xitrm(tmindx).lt.6.or.xrimes(tmindx).eq.0.) go to 100 

c logic for specific activity 

 irimes=int(xrimes(tmindx)) 

 if(irimes.lt.151) r=acttot/afp(irimes) 

 if(irimes.gt.150.and.irimes.lt.171) r=acttot/aactp(irimes-150) 

 if(irimes.gt.170) r=acttot/aactin(irimes-170) 

 sf=r*xactmes(tmindx)/acttot 

 go to 110 

 100 continue 

 sf=xactmes(tmindx)/acttot 

 110 continue 

B-35
 return 

 end 

B-36
 subroutine dose 

 include 'fiparms.f' 

 include 'varblock.f' 

c .... 

c this subroutine calculates the organ doses contributed by each radionuclide 

c and the total organ doses. 

c .... 

c array xbr(t) - breathing rate(m**3/hr) at time t 

c array xdur(t) - duration of exposure(hr) at time t 

c array xkfac(t) - ratio of airborne to surface at time t 

c variable sf - scaling factor (10**14 fissions per m**2, if itrm=1,5; 

c 10**14 fissions per m**3, if itrm=2,3,4; 10**14 fissions 

c intake, if itrm=6) 

c array xitdcf(t)- index for type of dose conversion factor(see input) 

c array afp(i) - relative amount of fission product radionuclides 

c (curie per 10**14 fissions) 

c array aactp(i) - relative amount of activation product radionuclides 

c (curie per 10**14 fissions) 

c array aactin(i)- relative amount of actinide element radionuclides 

c (curie per 10**14 fissions) 

c array dcf(j) - dose conversion factor(rem/curie)for inhalation or ingestion 

c array d(i,j) - dose to organ j for radionuclide i (rem) 

c array td(i,j) - total dose to organ j at time i 

c variable upfrac- pu239 uptake fraction for ingestion or inhalation 

c in curies per curies 

c array exfrac(i,j) - pu239 excretion fraction in urine curies per day from 

c exposure i, j years from shot 

c array sumfrac(i)-pu239 total excretion for multiple exposures 

c array tyrs(i) - times after shot for excretion factors(years) 

c 

c ..... 

c array xitdcf - index for type of dose conversion factor 

c (1) inhalation dcf (currently ICRP 72) 

c (2) ingestion dcf (currently ICRP 72) 

c ..... 

 const=xbr(tmindx)*xdur(tmindx)*xkfac(tmindx)*sf 

c ..... 

c open DCF files 

c ..... 

 if(xitdcf(tmindx).eq.1) 

 ; open(unit=2,file='inh.dcf',status='old') 

 if(xitdcf(tmindx).eq.2) 

 ; open(unit=2,file='ing.dcf',status='old') 

c..... 

c read initial information from DCF file 

c..... 

 read(2,*) numorgans(xitdcf(tmindx)),edosnum(xitdcf(tmindx)) 

 read(2,1) dcfidinfo(xitdcf(tmindx)) 

 read(2,2) (orgnames(xitdcf(tmindx),i), 

 ; i=1,numorgans(xitdcf(tmindx))) 

 1 format(a80) 

 2 format(40a11) 

c..... 

c initialize total dose arrays for current time index 

c..... 

 3 do 10 j=1,sss 

 td(tmindx,j)=0.0 

 td1(tmindx,j)=0.0 

 td2(tmindx,j)=0.0 

 td3(tmindx,j)=0.0 

 td4(tmindx,j)=0.0 

 do 9 i=1,ttt 

 osrnd(i,j)=0.0 

 9 continue 

 10 continue 

c..... 

c read in dcf set 

B-37
c..... 

 do 70 i=1,ttt 

 20 read(2,*) (dcf(j),j=1,numorgans(xitdcf(tmindx))) ! Read in dcfs 

 do 21 j=numorgans(xitdcf(tmindx))+1,sss 

 dcf(j)=0.0 

 21 continue 

c total all doses by radionuclide group (fp,actp,actin) but 

c separate doses from alpha emitters from doses from beta+gamma 

c emitters in actinide group 

 60 do 69 j=1,sss 

 dcf(j)=dcf(j)*1.e+6 

 if(i.le.150)then 

 osrnd(i,j)=const*afp(i)*dcf(j) 

 td1(tmindx,j)=td1(tmindx,j)+osrnd(i,j) 

 elseif(i.le.170)then 

 osrnd(i,j)=const*aactp(i-150)*dcf(j) 

 td2(tmindx,j)=td2(tmindx,j)+osrnd(i,j) 

 elseif(i.le.190)then 

 osrnd(i,j)=const*aactin(i-170)*dcf(j) 

 td3(tmindx,j)=td3(tmindx,j)+(osrnd(i,j)* 

 ; (1.0-alphaemit(i-170))) 

 td4(tmindx,j)=td4(tmindx,j)+(osrnd(i,j)*alphaemit(i-170)) 

 else 

 endif 

 69 continue 

 70 continue 

 close(unit=2) 

 if (itpm.eq.2)go to 120 

c 

 80 do 81 j=1,sss 

 td(tmindx,j)=td1(tmindx,j)+td2(tmindx,j)+td3(tmindx,j)+ 

 ; td4(tmindx,j) 

 tddcfsum(xitdcf(tmindx),j)=tddcfsum(xitdcf(tmindx),j)+ 

 ; td(tmindx,j) 

 tddcf1sum(xitdcf(tmindx),j)=tddcf1sum(xitdcf(tmindx),j)+ 

 ; td1(tmindx,j) 

 tddcf2sum(xitdcf(tmindx),j)=tddcf2sum(xitdcf(tmindx),j)+ 

 ; td2(tmindx,j) 

 tddcf3sum(xitdcf(tmindx),j)=tddcf3sum(xitdcf(tmindx),j)+ 

 ; td3(tmindx,j) 

 tddcf4sum(xitdcf(tmindx),j)=tddcf4sum(xitdcf(tmindx),j)+ 

 ; td4(tmindx,j) 

 81 continue 

 go to 300 

c 

 120 do 121 j=1,sss 

 td(tmindx,j)=td1(tmindx,j)+td2(tmindx,j)+td3(tmindx,j)+ 

 ; td4(tmindx,j) 

 121 continue 

 if(istidx.ne.0)then 

 timelog=alog(oldtcnc/tcncnew) 

 do 130 j=1,sss 

c 

 a=0.0 

 if(td(tmindx,j)*tdold(j).ne.0)a=alog(tdold(j)/td(tmindx,j))/ 

 ; timelog 

 tdsum(j)=tdsum(j)+td(tmindx,j)/xdur(tmindx)*tcncnew/(1+a)* 

 ; (1.0-(oldtcnc/tcncnew)**(1+a)) 

c 

 a=0.0 

 if(td1(tmindx,j)*td1old(j).ne.0)a=alog(td1old(j)/td1(tmindx,j))/ 

 ; timelog 

 td1sum(j)=td1sum(j)+td1(tmindx,j)/xdur(tmindx)*tcncnew/(1+a)* 

 ; (1.0-(oldtcnc/tcncnew)**(1+a)) 

c 

 a=0.0 

 if(td2(tmindx,j)*td2old(j).ne.0)a=alog(td2old(j)/td2(tmindx,j))/ 

B-38
 ; timelog 

 td2sum(j)=td2sum(j)+td2(tmindx,j)/xdur(tmindx)*tcncnew/(1+a)* 

 ; (1.0-(oldtcnc/tcncnew)**(1+a)) 

c 

 a=0.0 

 if(td3(tmindx,j)*td3old(j).ne.0)a=alog(td3old(j)/td3(tmindx,j))/ 

 ; timelog 

 td3sum(j)=td3sum(j)+td3(tmindx,j)/xdur(tmindx)*tcncnew/(1+a)* 

 ; (1.0-(oldtcnc/tcncnew)**(1+a)) 

c 

 a=0.0 

 if(td4(tmindx,j)*td4old(j).ne.0)a=alog(td4old(j)/td4(tmindx,j))/ 

 ; timelog 

 td4sum(j)=td4sum(j)+td4(tmindx,j)/xdur(tmindx)*tcncnew/(1+a)* 

 ; (1.0-(oldtcnc/tcncnew)**(1+a)) 

c 

 if(tcncnew.eq.xtexp(isttm+nexp))then 

 td(tmindx,j)=tdsum(j) 

 td1(tmindx,j)=td1sum(j) 

 td2(tmindx,j)=td2sum(j) 

 td3(tmindx,j)=td3sum(j) 

 td4(tmindx,j)=td4sum(j) 

 endif 

 130 continue 

 endif 

c 

 do 140 j=1,sss 

 tdold(j)=td(tmindx,j) 

 td1old(j)=td1(tmindx,j) 

 td2old(j)=td2(tmindx,j) 

 td3old(j)=td3(tmindx,j) 

 td4old(j)=td4(tmindx,j) 

 140 continue 

c 

 if(tcncnew.eq.xtexp(isttm+nexp))then 

 150 do 151 j=1,sss 

 td(tmindx,j)=td1(tmindx,j)+td2(tmindx,j)+td3(tmindx,j)+ 

 ; td4(tmindx,j) 

 tddcfsum(xitdcf(tmindx),j)=tddcfsum(xitdcf(tmindx),j)+ 

 ; td(tmindx,j) 

 tddcf1sum(xitdcf(tmindx),j)=tddcf1sum(xitdcf(tmindx),j)+ 

 ; td1(tmindx,j) 

 tddcf2sum(xitdcf(tmindx),j)=tddcf2sum(xitdcf(tmindx),j)+ 

 ; td2(tmindx,j) 

 tddcf3sum(xitdcf(tmindx),j)=tddcf3sum(xitdcf(tmindx),j)+ 

 ; td3(tmindx,j) 

 tddcf4sum(xitdcf(tmindx),j)=tddcf4sum(xitdcf(tmindx),j)+ 

 ; td4(tmindx,j) 

 151 continue 

 endif 

c 

 300 continue 

 if(iplut.eq.0) go to 500 

c 

c implement jones pu239 retention and excretion function 

c times are relative to the shot, not to the exposure 

c 

 if(xitdcf(tmindx).eq.1) then 

 upfrac=.05 

 else 

 upfrac=1.e-5 

 endif 

c 

 a1=4.75e-3 

 a2=2.39e-4 

 a3=8.55e-5 

 a4=1.42e-5 

B-39
 x1=5.58e-1 

 x2=4.42e-2 

 x3=3.80e-3 

 x4=2.84e-5 

 do 400 i=1,nplut 

 if(itpm.eq.2.and.istidx.ne.0) then 

 t=365.*tyrs(i)-tcncnew/24. 

 if(t.lt.0.0) t=0.0 

 else 

 t=365.*tyrs(i)-xtexp(tmindx)/24. 

 if(t.le.0.0) go to 395 

 endif 

c ..... 

c Calculate basic excretion fraction 

c ..... 

 ft=(a1*exp(-x1*t)+a2*exp(-x2*t)+a3*exp(-x3*t)+a4*exp(-x4*t)) 

 exfrac(tmindx,i)=const*aactin(14)*upfrac*ft 

 addnp=const*aactin(11)*2.35/(24360*365)*upfrac*ft 

 if(upfrac.eq.0.05) exfrac(tmindx,i)=exfrac(tmindx,i)+2.4*addnp 

 if(upfrac.eq.1.e-5) exfrac(tmindx,i)=exfrac(tmindx,i)+100.*addnp 

c ..... 

c Adjust excretion if exposure time + duration exceeds measurement time 

c ..... 

 if(itpm.eq.1.and.((xtexp(tmindx)+xdur(tmindx))/24.0.gt.365.* 

 ; tyrs(i))) then 

 timedif=365.*tyrs(i)-xtexp(tmindx)/24.0 

 exfrac(tmindx,i) = exfrac(tmindx,i)/xdur(tmindx)*timedif*24.0 

 endif 

c ..... 

c Handle integrated plutonium intake 

c ..... 

 if(itpm.eq.2)then 

 if(istidx.ne.0)then 

 t=365.*tyrs(i)-oldtcnc/24. 

 if(t.lt.0.0) go to 390 

 ftold=(a1*exp(-x1*t)+a2*exp(-x2*t)+a3*exp(-x3*t)+a4*exp(-x4*t)) 

 if((tcncnew/24.0).gt.(365.0*tyrs(i))) then 

 timedif=365.0*tyrs(i)-oldtcnc/24.0 

 else 

 timedif=tcncnew/24.0-oldtcnc/24.0 

 endif 

c 

 a=0.0 

 exfden=max(exfrac(tmindx,i),oldexf(i)) 

 if(exfden.le.0) go to 390 

 if((exfrac(tmindx,i)*oldexf(i).ne.0).and.(abs(exfrac(tmindx,i) 

 ; -oldexf(i))/exfden.gt.0.001)) then 

 a=alog((oldexf(i)/ftold)/(exfrac(tmindx,i)/ft))/timedif 

 sumexf(i)=sumexf(i)+exfrac(tmindx,i)/a/xdur(tmindx)* 

 ; (exp(a*timedif)-1.0)*24.0 

 else 

 sumexf(i)=sumexf(i)+(exfrac(tmindx,i)+oldexf(i))/2/ 

 ; xdur(tmindx)*timedif*24 

 endif 

 390 if(tcncnew.eq.xtexp(isttm+nexp)) then 

 exfrac(tmindx,i)=sumexf(i) 

 sumfrac(i)=sumfrac(i)+exfrac(tmindx,i) 

 endif 

 endif 

 oldexf(i)=exfrac(tmindx,i) 

c ..... 

c Handle standard plutonium intake 

c ..... 

 else 

 sumfrac(i)=sumfrac(i)+exfrac(tmindx,i) 

 endif 

 395 continue 

B-40
 400 continue 

c 

 500 return 

 end 

B-41
 subroutine outputf 

 include 'fiparms.f' 

 include 'varblock.f' 

c ..... 

 character*2 atorby(2) 

 character*7 nucld1(100),nucld2(90) 

 data atorby/'at','by'/ 

 data nucld1/'se-79','br-82','br-83','kr-83m','br-84','br-85', 

 ;'kr-85','kr-85m','rb-86','kr-87','rb-87','kr-88','rb-88','kr-89', 

 ;'rb-89','sr-89','rb-90','rb-90m','sr-90',' y-90','rb-91','sr-91', 

 ;' y-91',' y-91m','sr-92',' y-92','sr-93',' y-93','zr-93','nb-93m', 

 ;' y-94',' y-95','zr-95','nb-95',' y-96','zr-97','nb-97','nb-97m', 

 ;'nb-98m','mo-99','tc-99','tc-99m','mo-101','tc-101','mo-102', 

 ;'tc-102','tc-103','ru-103','rh-103m','tc-104','mo-105','tc-105', 

 ;'ru-105','rh-105','rh-105m','ru-106','rh-106','pd-107','rh-109', 

 ;'pd-109','ag-109m','ag-110m','ag-111','cd-113m','cd-115m', 

 ;'sn-123','sb-124','sn-125','sb-125','te-125m','sn-126','sb-126', 

 ;'sb-127','te-127','te-127m','sb-129','te-129','te-129m',' i-129', 

 ;'sn-130','sb-130m',' i-130','sb-131','te-131','te-131m',' i-131', 

 ;'xe-131m','sb-132','sb-132m','te-132',' i-132','sb-133','te-133', 

 ;'te-133m',' i-133','xe-133','xe-133m','te-134',' i-134','cs-134'/ 

 data nucld2/ 

 ;'cs-134m',' i-135','xe-135','xe-135m','cs-135','cs-136','xe-137', 

 ;'cs-137','ba-137m','xe-138','cs-138','cs-139','ba-139','cs-140', 

 ;'ba-140','la-140','ba-141','la-141','ce-141','ba-142','la-142', 

 ;'la-143','ce-143','pr-143','ce-144','pr-144','pr-144m','ce-145', 

 ;'pr-145','ce-146','pr-146','ce-147','pr-147','nd-147','pm-147', 

 ;'pr-148','pm-148','pm-148m','pm-149','pm-151','sm-151','eu-152', 

 ;'sm-153','eu-154','eu-155','eu-156','tb-160','ho-166m',' ',' ', 

 ;'be-7','na-24','mn-54','fe-55','fe-59','co-57','co-58','co-60', 

 ;'cu-64','cu-67',' w-181',' w-185',' w-187',' w-188','au-198', 

 ;'au-199','pb-203',' ',' ',' ','th-229','th-230','th-234',' u-233' 

 ;,' u-234',' u-235',' u-237',' u-238',' u-240','np-237','np-239', 

 ;'np-240','pu-238','pu-239','pu-240','pu-241','am-241','cm-242', 

 ;' ',' '/ 

c ..... 

c print program results based on specified output options 

c ..... 

 if(tmindx.le.nexp) then 

 write(1,10)xtmeas(xcmeas(tmindx)) 

 else 

 write(1,20) 

 endif 

 if(tmindx.gt.nexp) go to 450 

 10 format(1x//10x,'time of measurement ',1pg12.3,' hours') 

 20 format(1x//10x,'total of all measurements and exposures') 

c ..... 

c print gamma spectrum information, if specified by IOUT1 

c ..... 

 if(iout1.eq.0) go to 50 

 if(xitrm(xcmeas(tmindx)).le.3) write(1,30) 

 if(xitrm(xcmeas(tmindx)).le.3) write(1,40) 

 ;(i,spec(i)-sactp(i)-sactin(i),sactp(i),sactin(i),spec(i), 

 ;skrxer(i),sfracc(i),i=1,ooo) 

 30 format(8x, 

 ;'spec(j)-relative gamma emission spectrum at time of measurement' 

 ;/26x,'(gamma/hr per 10**14 fissions)' 

 ;//1x,'group # fission product activation product ', 

 ;'actinides total noble gases fractionated') 

 40 format(1x,i5,1pg16.3,4g18.3,g16.3) 

c ..... 

c if activity intake measured, indicate index radionuclide or gross activity 

c ..... 

 50 if(xitrm(xcmeas(tmindx)).eq.6.and.xrimes(xcmeas(tmindx)).gt.0) 

 ; go to 60 

 if(xitrm(xcmeas(tmindx)).ge.4) write(1,90) xactmes(xcmeas(tmindx)) 

 go to 70 

B-42
 60 irimes=ifix(xrimes(xcmeas(tmindx))) 

 write(1,100) irimes,xactmes(xcmeas(tmindx)) 

 70 write(1,80) sf 

 80 format(/8x,'sf',7x, 

 ;'scaling factor(10**14 fissions [per m**2, m**3])',1pg10.3) 

 90 format(//8x'actmes measured gross activity (curies)',1pg26.3) 

 100 format(//8x'actmes measured activity of radionuclide #',i3, 

 ;1pg20.3) 

c ..... 

c print relative inventory, if specified by IOUT2 

c ..... 

 if(iout2.eq.0.or.itpm.eq.2) go to 300 

 write(1,200)(i,i=1,10) 

 write(1,210)(j*10-10,(afp(i+j*10-10),i=1,10),j=1,15) 

 write(1,210)(j*10-160,(aactp(i+j*10-160),i=1,10),j=16,17) 

 write(1,210)(j*10-180,(aactin(i+j*10-180),i=1,10),j=18,19) 

 write(1,220) acttot 

 200 format(/' inventory of 150 fission products, 20 activation', 

 ;' products, 20 actinides (ci/10**14 fissions)'/(10i12)) 

 210 format(0pi4,1p10g12.3) 

 220 format(/8x,'acttot total activity(curies/10**14 fissions)', 

 ;1pg20.3) 

c ..... 

c print isotopic organ doses, if specified by IOUT3 

c ..... 

 300 if(iout3.eq.0.or.itpm.eq.2) go to 400 

 numgroups=int(numorgans(xitdcf(tmindx))/12) 

c 

 if (numgroups.ge.1) then 

 do 301 k=1,numgroups 

 if (k.eq.1) then 

 write(1,311)(orgnames(xitdcf(tmindx),(k-1)*12+j),j=1,12) 

 else 

 write(1,313)(orgnames(xitdcf(tmindx),(k-1)*12+j),j=1,12) 

 endif 

 write(1,312)(i,(osrnd(i,(k-1)*12+j),j=1,12),i=1,150) 

 write(1,312)(i-150,(osrnd(i,(k-1)*12+j),j=1,12),i=151,170) 

 write(1,312)(i-170,(osrnd(i,(k-1)*12+j),j=1,12),i=171,190) 

 301 continue 

 endif 

 if (numgroups*12.eq.numorgans(xitdcf(tmindx))) goto 400 

c 

 if (numgroups.eq.0) then 

 write(1,311)(orgnames(xitdcf(tmindx),j), 

 ; j=1,numorgans(xitdcf(tmindx))) 

 else 

 write(1,313)(orgnames(xitdcf(tmindx),numgroups*12+j), 

 ; j=1,(numorgans(xitdcf(tmindx))-(numgroups*12))) 

 endif 

c 

 write(1,312)(i,(osrnd(i,numgroups*12+j), 

 ; j=1,(numorgans(xitdcf(tmindx))-(numgroups*12))), 

 ; i=1,150) 

 write(1,312)(i-150,(osrnd(i,numgroups*12+j), 

 ; j=1,(numorgans(xitdcf(tmindx))-(numgroups*12))), 

 ; i=151,170) 

 write(1,312)(i-170,(osrnd(i,numgroups*12+j), 

 ; j=1,(numorgans(xitdcf(tmindx))-(numgroups*12))), 

 ; i=171,190) 

 goto 400 

 311 format(//19x,'dose commitment in rem from each radionuclide'// 

 ;' iso #',1a11,11a12) 

 312 format(1x,i3,1x,1p12g12.3) 

 313 format(/' iso #',1a11,11a12) 

c ..... 

c print intermediate organ doses, if specified by IOUT4 

c ..... 

B-43
 400 if(iout2.eq.0.and.itpm.eq.1)write(1,220)acttot 

 write(1,410) atorby(1),xtexp(tmindx),xdur(tmindx) 

c 

 401 write(1,411)(orgnames(xitdcf(tmindx),i),td1(tmindx,i), 

 ; td2(tmindx,i),td3(tmindx,i),td4(tmindx,i), 

 ; td(tmindx,i),i=1,numorgans(xitdcf(tmindx))) 

 410 format(//11x,'total dose commitments in rem for intake ',a2, 

 ;' time =',1pg10.3,' hours'/ 

 ;11x,'with duration time =',1pg10.3,' hours'//10x, 

 ;' fission products activation products actinides(g+b) ', 

 ;' actinides(a) total') 

 411 format(a11,2x,1pg11.3,1pg18.3,1pg19.3,1pg17.3,1pg16.3) 

c ..... 

c print relative contribution to eff dose from radionuclide if >1% 

c ..... 

 if (edosnum(xitdcf(tmindx)).eq.0) goto 500 

 419 write(1,431) 

 do 420 i=1,100 

 if(osrnd(i,edosnum(xitdcf(tmindx))).gt. 

 ; td(tmindx,edosnum(xitdcf(tmindx)))/100.) 

 ; write(1,432) nucld1(i),osrnd(i,edosnum(xitdcf(tmindx))), 

 ; 100.*osrnd(i,edosnum(xitdcf(tmindx)))/ 

 ; td(tmindx,edosnum(xitdcf(tmindx))) 

 420 continue 

 do 430 i=101,190 

 if(osrnd(i,edosnum(xitdcf(tmindx))).gt. 

 ; td(tmindx,edosnum(xitdcf(tmindx)))/100.) 

 ; write(1,432) nucld2(i-100),osrnd(i,edosnum(xitdcf(tmindx))), 

 ; 100.*osrnd(i,edosnum(xitdcf(tmindx)))/ 

 ; td(tmindx,edosnum(xitdcf(tmindx))) 

 430 continue 

 go to 500 

 431 format(//' radionuclides contributing > 1% to effective dose', 

 ; ' equivalent'//' nuclide rem percent') 

 432 format(1x,a7,1pg13.3,0pf7.1) 

c 

 450 write(1,451) 

 do 460 j=1,2 

 if(tddcfsum(j,numorgans(j)).gt.1e-10) then 

 write(1,*) ' ' 

 write(1,*) ' ' 

 write(1,*) ' Doses from Specified DCF File' 

 write(1,454) dcfidinfo(j) 

 write(1,452) 

 write(1,453)(orgnames(j,i),tddcf1sum(j,i),tddcf2sum(j,i), 

 ; tddcf3sum(j,i),tddcf4sum(j,i),tddcfsum(j,i), 

 ; i=1,numorgans(j)) 

 endif 

 460 continue 

 451 format(//11x,'total dose commitments in rem for all intakes', 

 ;' by DCF set') 

 452 format(/10x, 

 ;' fission products activation products actinides(g+b) ', 

 ;' actinides(a) total') 

 453 format(a11,2x,1pg11.3,1pg18.3,1pg19.3,1pg17.3,1pg16.3) 

 454 format(' DCF File Info: ',a80) 

c ..... 

c print plutonium excretion information, if specified 

c ..... 

 500 if (iplut.eq.0) go to 600 

 if (tmindx.gt.nexp) then 

 write(1,593) 

 else 

 if(xitdcf(tmindx).ne.2 .and. xitdcf(tmindx).ne.5 ) 

 ; write(1,590)'inhalation',.05 

 if(xitdcf(tmindx).eq.2 .or. xitdcf(tmindx).eq.5 ) 

 ; write(1,590)'ingestion ',1.0e-5 

B-44
 endif 

 write(1,591) (tyrs(i),i=1,nplut) 

 if (tmindx.gt.nexp) then 

 write(1,592) (sumfrac(i),i=1,nplut) 

 else 

 write(1,592) (exfrac(tmindx,i),i=1,nplut) 

 endif 

 590 format(/5x,'pu239 fraction in urine from ',a10,' exposure ', 

 ;' uptake fraction=',1pe9.3) 

 591 format(/' time after shot (yrs) ',1p10g10.2) 

 592 format(/' conc (ci/day) or (ci/1.4l)',1p10g10.2) 

 593 format(/5x,'pu239 fraction in urine from all exposures') 

c ..... 

c print table output file, if specified by IOUT5 

c NOTE: Table output limited in versions 4.2 and later to alpha emitters 

c and gamma plus beta emitters only - no radionuclide groupings 

c or bioassay results are provided in the tables. If such data is 

c needed, use version 4.1 

c ..... 

 600 if(tmindx.le.nexp.or.iout5.ne.1) go to 700 

 open(unit=4,file='fiidost.out',status='unknown') 

c 

 do 620 k=1,2 

 if(tddcfsum(k,numorgans(k)).gt.1e-10) then 

 write(4,690) ' alpha emitters ',dcfidinfo(k) 

 write(4,691) (orgnames(k,j),j=1,numorgans(k)) 

 do 613 i=1,nexp 

 if(xitdcf(i).eq.k) write(4,694) xtexp(i),(td4(i,j), 

 ; j=1,numorgans(k)) 

 613 continue 

 write(4,690) 'gamma+beta emitters ',dcfidinfo(k) 

 write(4,691) (orgnames(k,j),j=1,numorgans(k)) 

 do 614 i=1,nexp 

 if(xitdcf(i).eq.k) write(4,694) xtexp(i),(td(i,j)-td4(i,j), 

 ; j=1,numorgans(k)) 

 614 continue 

 endif 

 620 continue 

c 

 670 close(unit=4) 

c 

 680 format(23x,'FIIDOS Data Tables') 

 681 format(1x,'Total dose commitments in rem for all intakes', 

 ;' by DCF set and type of nuclide (with totals)') 

 682 format(/11x,a12,' Doses from Inhalation and/or Ingestion') 

 683 format(//5x,'Pu239 fraction in urine from all exposures') 

 684 format(/' time after shot (yrs) ',1p,50(', ',g7.2)) 

 685 format(10x,' exp tm concentrations (ci/day)', 

 ;' or (ci/1.4l)') 

 686 format(15x,1pg10.4,1p,40(',',g9.2)) 

 687 format(13x,' total ',1p,40(',',g9.2)) 

c 

 690 format(//19x,'Dose commitment in rem from ',a20,'.', 

 ; /19x,'DCF File Info: ',a80) 

 691 format(/,2x,'exp tm ',40(', ',a10)) 

 

 694 format(1x,1pg10.4,1p,40(',',g11.3)) 

 695 format(1x,' total ',1p,40(',',g11.3)) 

c 

 700 continue 

 return 

 end 

B-45
APPENDIX C 

SAMPLE PROBLEMS

C-1
SAMPLE PROBLEMS 

A set of six, small example problems has been devised to illustrate the utility of FIIDOS. The 

first four problems all address the same radiation exposure scenario, but each problem uses a 

different type of radiological measurement and the time of the measurement is not necessarily 

coincident with the time of the exposure. All of the first four scenarios use the ICRP-72 

inhalation dose conversion factor table. These are nearly identical to the example problems 

given in the previous FIIDOS manual, with only minor changes that reflect the effect the 

incorporation of ORIGEN into FIIDOS has had on the results. The set thus shows the capability 

of FIIDOS to utilize different types of radiological measurement information. The fifth example 

problem is used to show the results from the same gross activity intake used in the fourth 

example problem, but using the ICRP-72 ingestion dose conversion factor table. The last 

example problem is a complete fission product, activation product, and actinide problem. It also 

illustrates the Pu-239 excretion calculation. 

The radiation exposure scenario addressed by the first four examples involves a 15-minute 

inhalation exposure to deposited fallout four hours after the detonation. The weapon yield is 10 

KT, all from U-235 fast neutron fission. No activation products or actinide elements are 

considered. The fallout is considered to be depleted of the fission gases krypton and xenon, but 

no other fractionation effects are considered. The specified breathing rate is 1.2 m3

/hr. The 

airborne activity-surface activity ratio, or resuspension factor is 10-5 m

-1. ICRP-72 inhalation 

dose conversion factors are used throughout. 

The table below shows the radiological measurements used for each example problem. 

Problem Type of Radiological Measurement Value Time 

One Radiation Intensity 10.0 R/hr H+1 Hour 

Two Airborne Activity Concentration 6.914 μCi/m3 H+1 Hour 

Three Surface Activity Concentration 0.132 Ci/m2 H+4 Hour 

Four Inhalation Activity Intake 0.3974 μCi H+4 Hour 

The FIIDOS computer program output for the four example problems is given in Figures C-1 

through C-4. All example problems have produced the same calculated organ doses using 

different types of radiological measurements. 

The four example problems produced the same results because the problem input data are 

consistent. Figure C-5 shows the FIIDOS output from the calculation that was used to develop 

the consistent input data for the example problem set. The calculation was performed as a 

multiple exposure problem with exposure times of H+l hour and H+4 hour and a measurement 

time of H+1 hour. The calculation was keyed to a radiation intensity above a contaminated 

surface of 10 R/hr at H+1 hour; the radiological measurement for Example Problem 1. 

14 As seen in Figure C-5, at H+1 hour, the radiological contamination scaling factor, is 2.54 x 10

fissions/m2 14 (carried out to greater precision, actual value is 2.541 x 10 fissions/m2

), and the 

total activity of the fallout material is 0.272 Ci/1014 fissions (actual value to greater precision is 

0.2721 Ci/1014 fissions). The gross surface activity is thus 0.6914 Ci/m2

. With a resuspension 

factor of 10-5 m

-1 -6 , the gross airborne activity is 6.914 x 10 Ci/m3

 at H+1 hour, the radiological 

measurement for Example Problem 2. 

C-2
14 As seen in Figure C-5, at H+4 hour, the radiological contamination scaling factor is 2.54 x 10

fissions/m2, and the total activity of the fallout material is 0.05214 Ci/1014 fissions. The gross 

surface activity is thus 0.13247 Ci/m2 at H+4 hour, the radiological measurement for Example 

Problem 3 (though only 3 digits of precision are shown). 

As given above, at H+4 hour the gross surface activity is 0.13247 Ci/m2. With a resuspension 

factor of 10-5 m

-1 -6 , the gross airborne activity is 1.3247 x 10 Ci/m3

. For a 0.25-hour exposure 

with a breathing rate of 1.2 m3 -6 /hr, the gross activity intake is thus 0.3974 x 10 Ci, the 

radiological measurement for Example Problem 4. 

The input data in Example Problem 4 is convenient for illustrating the effects of assuming 

different pathways and using different dose conversion factors. Figure C-5 shows the output of 

Example Problem 5, which is identical to Example Problem 4 except that the mode of intake was 

changed to ingestion. Table 18 shows the committed organ doses calculated for the intake of 

0.3974 μCi of fission products via ingestion or inhalation using the 11 sets of dose conversion 

factors that have been incorporated into the various versions of FIIDOS over the years. 

Currently, only ICRP-72 dose conversion factors are used. 

Example Problem 6 shows a full example with all types of radionuclides present. The output is 

given in Figure C-7. In general, if the problem is concerned with a complete set of fission 

product inventories, the change in results with the current version of FIIDOS versus the original 

version is within a few percent. However, the amount of specific isotopes can change 

significantly. Thus if the problem is governed by either a specific isotope input or an isotope for 

dose, then more significant changes are possible. 

C-3
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM ONE 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 1 

 tmeas time of rad measurements 1.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 10.0 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 2 

 actmes activity measurement (itrm=4-6) 0.00 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 0.250 

 br breathing rate (m**3/hr) 1.20 

 kfac resuspension factors (m**-1) 1.000E-05 

 itdcf dose conversion factor set index 1/2 1 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 1.00 hours 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 2.54 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 0.250 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

Figure C-1. Example Problem 1 - Inhalation Intake Based on Radiation Intensity 

C-4
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 1.861E-05 3.5 

 sr-92 2.052E-05 3.9 

 y-92 2.930E-05 5.6 

 y-93 4.289E-05 8.1 

 zr-97 6.272E-05 11.9 

 mo-99 1.596E-05 3.0 

 ru-105 5.592E-06 1.1 

 i-131 2.292E-05 4.3 

 te-132 2.524E-05 4.8 

 i-133 8.737E-05 16.6 

 i-134 1.031E-05 2.0 

 i-135 4.197E-05 8.0 

 ba-139 5.746E-06 1.1 

 la-141 2.730E-05 5.2 

 la-142 1.463E-05 2.8 

 ce-143 2.606E-05 4.9 

 ce-144 6.025E-06 1.1 

 pr-145 1.535E-05 2.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-1. Example Problem 1 - Inhalation Intake Based on Radiation Intensity (concluded). 

C-5
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM TWO 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 4 

 tmeas time of rad measurements 1.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 0.00 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 0 

 actmes activity measurement (itrm=4-6) 6.914E-06 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 0.250 

 br breathing rate (m**3/hr) 1.20 

 kfac resuspension factors (m**-1) 1.000E-05 

 itdcf dose conversion factor set index 1/2 1 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 1.00 hours 

 actmes measured gross activity (curies) 6.914E-06 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 2.541E-05 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 0.250 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-10 0.00 0.00 0.00 1.940E-10 

 bone surf 6.665E-10 0.00 0.00 0.00 6.665E-10 

 brain 1.655E-10 0.00 0.00 0.00 1.655E-10 

 breast 1.577E-10 0.00 0.00 0.00 1.577E-10 

 st wall 3.192E-09 0.00 0.00 0.00 3.192E-09 

 si wall 4.332E-09 0.00 0.00 0.00 4.332E-09 

 uli wall 1.109E-08 0.00 0.00 0.00 1.109E-08 

 lli wall 1.226E-08 0.00 0.00 0.00 1.226E-08 

 kidneys 1.897E-10 0.00 0.00 0.00 1.897E-10 

 liver 2.182E-10 0.00 0.00 0.00 2.182E-10 

 et region 3.062E-08 0.00 0.00 0.00 3.062E-08 

 lung 1.066E-08 0.00 0.00 0.00 1.066E-08 

 muscle 2.120E-10 0.00 0.00 0.00 2.120E-10 

 ovaries 4.476E-10 0.00 0.00 0.00 4.476E-10 

 pancreas 2.386E-10 0.00 0.00 0.00 2.386E-10 

 r marrow 5.019E-10 0.00 0.00 0.00 5.019E-10 

 skin 1.308E-10 0.00 0.00 0.00 1.308E-10 

 spleen 1.977E-10 0.00 0.00 0.00 1.977E-10 

 testes 1.176E-10 0.00 0.00 0.00 1.176E-10 

 thymus 2.342E-10 0.00 0.00 0.00 2.342E-10 

 thyroid 3.032E-08 0.00 0.00 0.00 3.032E-08 

 uterus 2.950E-10 0.00 0.00 0.00 2.950E-10 

 ubld wall 1.108E-09 0.00 0.00 0.00 1.108E-09 

 eff dose 5.269E-09 0.00 0.00 0.00 5.269E-09 

Figure C-2. Example Problem 2 - Intake Based on Inhalation of Airborne Activity.

C-6
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 1.861E-10 3.5 

 sr-92 2.052E-10 3.9 

 y-92 2.930E-10 5.6 

 y-93 4.289E-10 8.1 

 zr-97 6.271E-10 11.9 

 mo-99 1.595E-10 3.0 

 ru-105 5.592E-11 1.1 

 i-131 2.292E-10 4.3 

 te-132 2.524E-10 4.8 

 i-133 8.736E-10 16.6 

 i-134 1.031E-10 2.0 

 i-135 4.197E-10 8.0 

 ba-139 5.745E-11 1.1 

 la-141 2.729E-10 5.2 

 la-142 1.463E-10 2.8 

 ce-143 2.606E-10 4.9 

 ce-144 6.024E-11 1.1 

 pr-145 1.535E-10 2.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-10 0.00 0.00 0.00 1.940E-10 

 bone surf 6.665E-10 0.00 0.00 0.00 6.665E-10 

 brain 1.655E-10 0.00 0.00 0.00 1.655E-10 

 breast 1.577E-10 0.00 0.00 0.00 1.577E-10 

 st wall 3.192E-09 0.00 0.00 0.00 3.192E-09 

 si wall 4.332E-09 0.00 0.00 0.00 4.332E-09 

 uli wall 1.109E-08 0.00 0.00 0.00 1.109E-08 

 lli wall 1.226E-08 0.00 0.00 0.00 1.226E-08 

 kidneys 1.897E-10 0.00 0.00 0.00 1.897E-10 

 liver 2.182E-10 0.00 0.00 0.00 2.182E-10 

 et region 3.062E-08 0.00 0.00 0.00 3.062E-08 

 lung 1.066E-08 0.00 0.00 0.00 1.066E-08 

 muscle 2.120E-10 0.00 0.00 0.00 2.120E-10 

 ovaries 4.476E-10 0.00 0.00 0.00 4.476E-10 

 pancreas 2.386E-10 0.00 0.00 0.00 2.386E-10 

 r marrow 5.019E-10 0.00 0.00 0.00 5.019E-10 

 skin 1.308E-10 0.00 0.00 0.00 1.308E-10 

 spleen 1.977E-10 0.00 0.00 0.00 1.977E-10 

 testes 1.176E-10 0.00 0.00 0.00 1.176E-10 

 thymus 2.342E-10 0.00 0.00 0.00 2.342E-10 

 thyroid 3.032E-08 0.00 0.00 0.00 3.032E-08 

 uterus 2.950E-10 0.00 0.00 0.00 2.950E-10 

 ubld wall 1.108E-09 0.00 0.00 0.00 1.108E-09 

 eff dose 5.269E-09 0.00 0.00 0.00 5.269E-09 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-2. Example Problem 2 - Intake Based on Inhalation of Airborne Activity (concluded).

C-7
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM THREE 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 5 

 tmeas time of rad measurements 4.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 0.00 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 0 

 actmes activity measurement (itrm=4-6) 0.132 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 0.250 

 br breathing rate (m**3/hr) 1.20 

 kfac resuspension factors (m**-1) 1.000E-05 

 itdcf dose conversion factor set index 1/2 1 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 4.00 hours 

 actmes measured gross activity (curies) 0.132 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 2.54 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 0.250 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

Figure C-3. Example Problem 3 - Intake Based on Inhalation of Resuspended Surface Activity.

C-8
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 1.861E-05 3.5 

 sr-92 2.052E-05 3.9 

 y-92 2.930E-05 5.6 

 y-93 4.289E-05 8.1 

 zr-97 6.272E-05 11.9 

 mo-99 1.596E-05 3.0 

 ru-105 5.592E-06 1.1 

 i-131 2.292E-05 4.3 

 te-132 2.524E-05 4.8 

 i-133 8.737E-05 16.6 

 i-134 1.031E-05 2.0 

 i-135 4.197E-05 8.0 

 ba-139 5.746E-06 1.1 

 la-141 2.730E-05 5.2 

 la-142 1.463E-05 2.8 

 ce-143 2.606E-05 4.9 

 ce-144 6.025E-06 1.1 

 pr-145 1.535E-05 2.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-3. Example Problem 3 - Intake Based on Inhalation of Resuspended Surface Activity 

(concluded). 

C-9
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM FOUR 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 6 

 tmeas time of rad measurements 4.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 0.00 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 0 

 actmes activity measurement (itrm=4-6) 3.974E-07 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 1.00 

 br breathing rate (m**3/hr) 1.00 

 kfac resuspension factors (m**-1) 1.00 

 itdcf dose conversion factor set index 1/2 1 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 4.00 hours 

 actmes measured gross activity (curies) 3.974E-07 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 7.622E-06 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 1.00 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

Figure C-4. Example Problem 4 - Intake Based on Inhalation of Gross Activity.

C-10
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 1.861E-05 3.5 

 sr-92 2.052E-05 3.9 

 y-92 2.930E-05 5.6 

 y-93 4.289E-05 8.1 

 zr-97 6.272E-05 11.9 

 mo-99 1.596E-05 3.0 

 ru-105 5.592E-06 1.1 

 i-131 2.292E-05 4.3 

 te-132 2.524E-05 4.8 

 i-133 8.737E-05 16.6 

 i-134 1.031E-05 2.0 

 i-135 4.197E-05 8.0 

 ba-139 5.746E-06 1.1 

 la-141 2.730E-05 5.2 

 la-142 1.463E-05 2.8 

 ce-143 2.606E-05 4.9 

 ce-144 6.025E-06 1.1 

 pr-145 1.535E-05 2.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-4. Example Problem 4 - Intake Based on Inhalation of Gross Activity (concluded). 

C-11
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM BASIS 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 1 

 tmeas time of rad measurements 1.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 10.0 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 2 

 actmes activity measurement (itrm=4-6) 0.00 

 nexp number of exposure calculations 2 

 texp exposed @ h+(hr) 1.00 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 1 

 dur duration (hr) 0.250 0.250 

 br breathing rate (m**3/hr) 1.20 1.20 

 kfac resuspension factors (m**-1) 1.000E-05 1.000E-05 

 itdcf dose conversion factor set index 1/2 1 1 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 1.00 hours 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 2.54 

 acttot total activity(curies/10**14 fissions) 0.272 

 total dose commitments in rem for intake at time = 1.00 hours 

 with duration time = 0.250 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 4.360E-05 0.00 0.00 0.00 4.360E-05 

 bone surf 1.129E-04 0.00 0.00 0.00 1.129E-04 

 brain 3.869E-05 0.00 0.00 0.00 3.869E-05 

 breast 3.454E-05 0.00 0.00 0.00 3.454E-05 

 st wall 9.737E-04 0.00 0.00 0.00 9.737E-04 

 si wall 7.640E-04 0.00 0.00 0.00 7.640E-04 

 uli wall 1.607E-03 0.00 0.00 0.00 1.607E-03 

 lli wall 1.536E-03 0.00 0.00 0.00 1.536E-03 

 kidneys 4.317E-05 0.00 0.00 0.00 4.317E-05 

 liver 4.592E-05 0.00 0.00 0.00 4.592E-05 

 et region 8.817E-03 0.00 0.00 0.00 8.817E-03 

 lung 1.648E-03 0.00 0.00 0.00 1.648E-03 

 muscle 4.773E-05 0.00 0.00 0.00 4.773E-05 

 ovaries 8.396E-05 0.00 0.00 0.00 8.396E-05 

 pancreas 6.603E-05 0.00 0.00 0.00 6.603E-05 

 r marrow 9.222E-05 0.00 0.00 0.00 9.222E-05 

 skin 2.965E-05 0.00 0.00 0.00 2.965E-05 

 spleen 5.161E-05 0.00 0.00 0.00 5.161E-05 

 testes 2.422E-05 0.00 0.00 0.00 2.422E-05 

 thymus 5.304E-05 0.00 0.00 0.00 5.304E-05 

 thyroid 3.066E-03 0.00 0.00 0.00 3.066E-03 

 uterus 6.189E-05 0.00 0.00 0.00 6.189E-05 

 ubld wall 1.857E-04 0.00 0.00 0.00 1.857E-04 

 eff dose 8.805E-04 0.00 0.00 0.00 8.805E-04 

Figure C-5. Basis for Example Problem Set Input. 

C-12
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 2.315E-05 2.6 

 sr-92 4.421E-05 5.0 

 y-92 1.442E-05 1.6 

 y-93 5.249E-05 6.0 

 y-94 1.583E-05 1.8 

 zr-97 7.093E-05 8.1 

 mo-99 1.647E-05 1.9 

 tc-101 1.087E-05 1.2 

 ru-105 8.887E-06 1.0 

 sb-131 1.284E-05 1.5 

 te-131 1.408E-05 1.6 

 i-131 1.211E-05 1.4 

 te-132 2.592E-05 2.9 

 te-133m 3.572E-05 4.1 

 i-133 7.165E-05 8.1 

 te-134 5.471E-05 6.2 

 i-134 4.167E-05 4.7 

 i-135 5.760E-05 6.5 

 cs-138 3.145E-05 3.6 

 ba-139 2.461E-05 2.8 

 ba-141 1.041E-05 1.2 

 la-141 4.065E-05 4.6 

 la-142 5.577E-05 6.3 

 ce-143 2.624E-05 3.0 

 pr-145 2.173E-05 2.5 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 time of measurement 1.00 hours 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 2.54 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 0.250 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 1.940E-05 0.00 0.00 0.00 1.940E-05 

 bone surf 6.665E-05 0.00 0.00 0.00 6.665E-05 

 brain 1.655E-05 0.00 0.00 0.00 1.655E-05 

 breast 1.577E-05 0.00 0.00 0.00 1.577E-05 

 st wall 3.192E-04 0.00 0.00 0.00 3.192E-04 

 si wall 4.332E-04 0.00 0.00 0.00 4.332E-04 

 uli wall 1.109E-03 0.00 0.00 0.00 1.109E-03 

 lli wall 1.226E-03 0.00 0.00 0.00 1.226E-03 

 kidneys 1.897E-05 0.00 0.00 0.00 1.897E-05 

 liver 2.182E-05 0.00 0.00 0.00 2.182E-05 

 et region 3.062E-03 0.00 0.00 0.00 3.062E-03 

 lung 1.066E-03 0.00 0.00 0.00 1.066E-03 

 muscle 2.120E-05 0.00 0.00 0.00 2.120E-05 

 ovaries 4.477E-05 0.00 0.00 0.00 4.477E-05 

 pancreas 2.386E-05 0.00 0.00 0.00 2.386E-05 

 r marrow 5.019E-05 0.00 0.00 0.00 5.019E-05 

 skin 1.308E-05 0.00 0.00 0.00 1.308E-05 

 spleen 1.977E-05 0.00 0.00 0.00 1.977E-05 

 testes 1.176E-05 0.00 0.00 0.00 1.176E-05 

 thymus 2.342E-05 0.00 0.00 0.00 2.342E-05 

 thyroid 3.033E-03 0.00 0.00 0.00 3.033E-03 

 uterus 2.950E-05 0.00 0.00 0.00 2.950E-05 

 ubld wall 1.108E-04 0.00 0.00 0.00 1.108E-04 

 eff dose 5.270E-04 0.00 0.00 0.00 5.270E-04 

Figure C-5. Basis for Example Problem Set Input (continued). 

C-13
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 1.861E-05 3.5 

 sr-92 2.052E-05 3.9 

 y-92 2.930E-05 5.6 

 y-93 4.289E-05 8.1 

 zr-97 6.272E-05 11.9 

 mo-99 1.596E-05 3.0 

 ru-105 5.592E-06 1.1 

 i-131 2.292E-05 4.3 

 te-132 2.524E-05 4.8 

 i-133 8.737E-05 16.6 

 i-134 1.031E-05 2.0 

 i-135 4.197E-05 8.0 

 ba-139 5.746E-06 1.1 

 la-141 2.730E-05 5.2 

 la-142 1.463E-05 2.8 

 ce-143 2.606E-05 4.9 

 ce-144 6.025E-06 1.1 

 pr-145 1.535E-05 2.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 6.300E-05 0.00 0.00 0.00 6.300E-05 

 bone surf 1.796E-04 0.00 0.00 0.00 1.796E-04 

 brain 5.524E-05 0.00 0.00 0.00 5.524E-05 

 breast 5.031E-05 0.00 0.00 0.00 5.031E-05 

 st wall 1.293E-03 0.00 0.00 0.00 1.293E-03 

 si wall 1.197E-03 0.00 0.00 0.00 1.197E-03 

 uli wall 2.716E-03 0.00 0.00 0.00 2.716E-03 

 lli wall 2.762E-03 0.00 0.00 0.00 2.762E-03 

 kidneys 6.214E-05 0.00 0.00 0.00 6.214E-05 

 liver 6.774E-05 0.00 0.00 0.00 6.774E-05 

 et region 1.188E-02 0.00 0.00 0.00 1.188E-02 

 lung 2.715E-03 0.00 0.00 0.00 2.715E-03 

 muscle 6.893E-05 0.00 0.00 0.00 6.893E-05 

 ovaries 1.287E-04 0.00 0.00 0.00 1.287E-04 

 pancreas 8.989E-05 0.00 0.00 0.00 8.989E-05 

 r marrow 1.424E-04 0.00 0.00 0.00 1.424E-04 

 skin 4.273E-05 0.00 0.00 0.00 4.273E-05 

 spleen 7.139E-05 0.00 0.00 0.00 7.139E-05 

 testes 3.599E-05 0.00 0.00 0.00 3.599E-05 

 thymus 7.646E-05 0.00 0.00 0.00 7.646E-05 

 thyroid 6.099E-03 0.00 0.00 0.00 6.099E-03 

 uterus 9.139E-05 0.00 0.00 0.00 9.139E-05 

 ubld wall 2.965E-04 0.00 0.00 0.00 2.965E-04 

 eff dose 1.407E-03 0.00 0.00 0.00 1.407E-03 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-5. Basis for Example Problem Set Input (concluded). 

C-14
 fiidos input 

 title: FIIDOS VERSION 4.3 EXAMPLE PROBLEM FIVE 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 0 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 6 

 tmeas time of rad measurements 4.00 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 0.00 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 0 

 actmes activity measurement (itrm=4-6) 3.974E-07 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 4.00 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 1.00 

 br breathing rate (m**3/hr) 1.00 

 kfac resuspension factors (m**-1) 1.00 

 itdcf dose conversion factor set index 1/2 2 

 iactp activation products no/yes 0/1 0 

 iactin actinides no/yes 0/1 0 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 4.00 hours 

 actmes measured gross activity (curies) 3.974E-07 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 7.622E-06 

 acttot total activity(curies/10**14 fissions) 5.214E-02 

 total dose commitments in rem for intake at time = 4.00 hours 

 with duration time = 1.00 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 3.017E-05 0.00 0.00 0.00 3.017E-05 

 bone surf 6.645E-05 0.00 0.00 0.00 6.645E-05 

 brain 1.508E-05 0.00 0.00 0.00 1.508E-05 

 breast 1.618E-05 0.00 0.00 0.00 1.618E-05 

 st wall 1.050E-03 0.00 0.00 0.00 1.050E-03 

 si wall 1.227E-03 0.00 0.00 0.00 1.227E-03 

 uli wall 3.019E-03 0.00 0.00 0.00 3.019E-03 

 lli wall 3.164E-03 0.00 0.00 0.00 3.164E-03 

 kidneys 7.360E-05 0.00 0.00 0.00 7.360E-05 

 liver 6.117E-05 0.00 0.00 0.00 6.117E-05 

 et region 1.655E-05 0.00 0.00 0.00 1.655E-05 

 lung 2.007E-05 0.00 0.00 0.00 2.007E-05 

 muscle 2.953E-05 0.00 0.00 0.00 2.953E-05 

 ovaries 1.102E-04 0.00 0.00 0.00 1.102E-04 

 pancreas 5.406E-05 0.00 0.00 0.00 5.406E-05 

 r marrow 5.793E-05 0.00 0.00 0.00 5.793E-05 

 skin 1.813E-05 0.00 0.00 0.00 1.813E-05 

 spleen 4.002E-05 0.00 0.00 0.00 4.002E-05 

 testes 2.250E-05 0.00 0.00 0.00 2.250E-05 

 thymus 1.865E-05 0.00 0.00 0.00 1.865E-05 

 thyroid 6.294E-03 0.00 0.00 0.00 6.294E-03 

 uterus 6.994E-05 0.00 0.00 0.00 6.994E-05 

 ubld wall 2.031E-04 0.00 0.00 0.00 2.031E-04 

 eff dose 8.608E-04 0.00 0.00 0.00 8.608E-04 

Figure C-6. Example Problem 5 - Intake Based on Ingestion of Gross Activity.

C-15
radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 4.311E-05 5.0 

 sr-92 4.869E-05 5.7 

 y-92 4.997E-05 5.8 

 y-93 8.115E-05 9.4 

 zr-97 9.250E-05 10.7 

 i-131 4.533E-05 5.3 

 te-132 3.206E-05 3.7 

 i-133 1.777E-04 20.6 

 i-134 1.421E-05 1.7 

 i-135 8.533E-05 9.9 

 ba-139 1.259E-05 1.5 

 la-141 4.234E-05 4.9 

 la-142 1.774E-05 2.1 

 ce-143 2.651E-05 3.1 

 pr-145 2.330E-05 2.7 

 pu239 fraction in urine from ingestion exposure uptake fraction=1.000E-05 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Ingestion DCFs (From FGR-13) - 5-24-2001 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 3.017E-05 0.00 0.00 0.00 3.017E-05 

 bone surf 6.645E-05 0.00 0.00 0.00 6.645E-05 

 brain 1.508E-05 0.00 0.00 0.00 1.508E-05 

 breast 1.618E-05 0.00 0.00 0.00 1.618E-05 

 st wall 1.050E-03 0.00 0.00 0.00 1.050E-03 

 si wall 1.227E-03 0.00 0.00 0.00 1.227E-03 

 uli wall 3.019E-03 0.00 0.00 0.00 3.019E-03 

 lli wall 3.164E-03 0.00 0.00 0.00 3.164E-03 

 kidneys 7.360E-05 0.00 0.00 0.00 7.360E-05 

 liver 6.117E-05 0.00 0.00 0.00 6.117E-05 

 et region 1.655E-05 0.00 0.00 0.00 1.655E-05 

 lung 2.007E-05 0.00 0.00 0.00 2.007E-05 

 muscle 2.953E-05 0.00 0.00 0.00 2.953E-05 

 ovaries 1.102E-04 0.00 0.00 0.00 1.102E-04 

 pancreas 5.406E-05 0.00 0.00 0.00 5.406E-05 

 r marrow 5.793E-05 0.00 0.00 0.00 5.793E-05 

 skin 1.813E-05 0.00 0.00 0.00 1.813E-05 

 spleen 4.002E-05 0.00 0.00 0.00 4.002E-05 

 testes 2.250E-05 0.00 0.00 0.00 2.250E-05 

 thymus 1.865E-05 0.00 0.00 0.00 1.865E-05 

 thyroid 6.294E-03 0.00 0.00 0.00 6.294E-03 

 uterus 6.994E-05 0.00 0.00 0.00 6.994E-05 

 ubld wall 2.031E-04 0.00 0.00 0.00 2.031E-04 

 eff dose 8.608E-04 0.00 0.00 0.00 8.608E-04 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 0.0 0.0 0.0 

 end 

Figure C-6. Example Problem 5 - Intake Based on Ingestion of Gross Activity (concluded). 

C-16
C-17
 fiidos input 

 title: RESIDENCE ISLAND - FIIDOS VERSION 4.3 EXAMPLE PROBLEM SIX 

 -------------------------------------------------------------------------------- 

 itpm problem type single/integrated 1/2 1 

 iout1 print spectrum no/yes 0/1 0 

 iout2 print inventory no/yes 0/1 1 

 iout3 print dose inventory no/yes 0/1 0 

 iout4 print intermediate doses no/yes 0/1 1 

 iout5 print dose tables no/yes 0/1 0 

 nmeas number of measurement calculations 1 

 itrm rad measurement indices 1 

 tmeas time of rad measurements 16.0 

 rimes rad intensity (itrm=1-3); index nuclide (itrm=6) 1.00 

 itmi meas index tis/air/fb/fb-man/fb-man 1/2/3/4/5 2 

 actmes activity measurement (itrm=4-6) 0.00 

 nexp number of exposure calculations 1 

 texp exposed @ h+(hr) 16.0 

 icmeas rad exposure to measurement indices (re-sorted) 1 

 dur duration (hr) 1.00 

 br breathing rate (m**3/hr) 1.20 

 kfac resuspension factors (m**-1) 6.000E-06 

 itdcf dose conversion factor set index 1/2 1 

 iactp activation products no/yes 0/1 1 

 iactin actinides no/yes 0/1 1 

 ikrxer noble gases removed no/yes 0/1 1 

 ifrac fractionation no/yes 0/1 0 

 iplut plutonium bioassay no/yes 0/1 1 

 nplut number of entries for plutonium bioassay 3 

 tyrs times after shot for Pu conc in urine 50.0 55.0 60.0 

 fiidos output 

 time of measurement 16.0 hours 

 sf scaling factor(10**14 fissions [per m**2, m**3]) 9.91 

 inventory of 150 fission products, 20 activation products, 20 actinides (ci/10**14 fissions) 

 1 2 3 4 5 6 7 8 9 10 

 0 1.877E-12 1.416E-07 1.364E-05 0.00 8.641E-12 0.00 0.00 0.00 3.988E-09 0.00 

 10 2.182E-17 0.00 9.683E-05 0.00 7.553E-21 1.281E-05 0.00 0.00 7.269E-08 2.611E-08 

 20 0.00 6.617E-04 9.581E-06 4.204E-04 1.341E-04 7.055E-04 0.00 8.153E-04 1.204E-12 7.725E-16 

 30 0.00 4.724E-29 1.710E-05 2.201E-07 0.00 8.585E-04 9.206E-04 8.147E-04 2.614E-10 3.730E-04 

 40 1.476E-12 2.934E-04 1.917E-21 5.058E-20 3.846E-27 3.876E-27 0.00 2.664E-05 2.659E-05 1.232E-17 

 50 0.00 0.00 3.285E-04 3.608E-04 9.357E-05 1.455E-06 1.455E-06 1.572E-13 0.00 1.919E-04 

 60 1.920E-04 1.032E-10 1.782E-05 3.540E-10 1.097E-07 1.498E-07 1.753E-08 5.651E-06 1.167E-07 7.036E-10 

 70 5.333E-12 8.269E-07 5.533E-05 3.153E-05 4.987E-08 1.740E-04 1.954E-04 2.804E-06 5.174E-14 0.00 

 80 0.00 2.850E-06 1.078E-14 2.532E-05 1.125E-04 8.147E-05 0.00 0.00 0.00 2.615E-04 

 90 2.805E-04 0.00 2.236E-08 9.889E-08 9.242E-04 0.00 0.00 4.052E-09 4.392E-07 1.441E-09 

 100 1.004E-07 7.917E-04 0.00 0.00 7.628E-13 2.737E-06 0.00 1.112E-07 1.050E-07 0.00 

 110 9.031E-11 1.220E-32 8.479E-06 0.00 8.245E-05 2.157E-05 1.271E-17 4.121E-04 2.995E-05 6.959E-29 

 120 1.157E-05 3.528E-22 4.850E-04 1.880E-05 2.962E-06 2.964E-06 4.147E-08 0.00 4.255E-04 2.409E-23 

 130 7.861E-14 0.00 2.837E-23 3.824E-05 1.841E-08 0.00 1.738E-10 9.906E-11 9.763E-05 8.098E-05 

 140 1.361E-09 7.610E-15 2.986E-05 4.795E-12 1.761E-08 1.010E-06 9.202E-11 8.733E-16 0.00 0.00 

 0 0.00 3.964E-04 0.00 0.00 0.00 0.00 0.00 8.272E-05 0.00 0.00 

 10 0.00 3.833E-06 0.00 1.024E-05 0.00 0.00 0.00 0.00 0.00 0.00 

 0 0.00 2.267E-20 2.618E-14 0.00 1.380E-12 4.830E-14 1.287E-05 1.379E-12 9.396E-06 7.872E-15 

 10 5.663E-06 9.479E-06 8.980E-10 6.897E-08 2.743E-12 8.779E-09 2.569E-14 0.00 0.00 0.00 

 acttot total activity(curies/10**14 fissions) 1.262E-02 

 total dose commitments in rem for intake at time = 16.0 hours 

 with duration time = 1.00 hours 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 7.932E-05 4.985E-04 2.835E-07 4.975E-05 6.279E-04 

 bone surf 2.785E-04 2.377E-04 7.352E-05 2.766E-02 2.825E-02 

 brain 5.391E-05 6.372E-05 1.823E-07 4.975E-05 1.676E-04 

 breast 6.611E-05 5.598E-04 2.557E-07 4.975E-05 6.760E-04 

 st wall 7.048E-04 2.948E-04 1.957E-06 4.975E-05 1.051E-03 

Figure C-7. Example Problem 6 - Residence Island.

C-18
 si wall 1.234E-03 9.354E-05 3.648E-06 4.975E-05 1.381E-03 

 uli wall 3.910E-03 1.250E-04 1.368E-05 4.975E-05 4.099E-03 

 lli wall 5.918E-03 1.740E-04 2.535E-05 4.975E-05 6.167E-03 

 kidneys 7.358E-05 2.103E-04 1.521E-06 1.180E-04 4.034E-04 

 liver 8.503E-05 4.542E-04 1.527E-05 6.080E-03 6.635E-03 

 et region 9.910E-03 2.965E-03 4.353E-05 2.768E-04 1.320E-02 

 lung 6.363E-03 3.953E-03 6.643E-05 6.099E-04 1.099E-02 

 muscle 7.982E-05 2.320E-04 2.587E-07 4.975E-05 3.618E-04 

 ovaries 2.097E-04 6.707E-05 1.416E-06 3.686E-04 6.468E-04 

 pancreas 8.349E-05 3.674E-04 2.907E-07 4.975E-05 5.010E-04 

 r marrow 1.926E-04 2.863E-04 3.076E-06 1.364E-03 1.846E-03 

 skin 4.490E-05 1.328E-04 1.851E-07 4.975E-05 2.276E-04 

 spleen 7.138E-05 3.948E-04 2.674E-07 4.975E-05 5.162E-04 

 testes 4.165E-05 2.479E-05 1.028E-06 3.870E-04 4.545E-04 

 thymus 9.302E-05 6.317E-04 3.041E-07 4.975E-05 7.748E-04 

 thyroid 1.698E-02 2.340E-04 2.110E-07 4.975E-05 1.726E-02 

 uterus 1.187E-04 5.176E-05 3.582E-07 4.975E-05 2.206E-04 

 ubld wall 3.721E-04 4.377E-05 5.846E-07 4.975E-05 4.662E-04 

 eff dose 2.485E-03 7.332E-04 1.258E-05 9.217E-04 4.153E-03 

 radionuclides contributing > 1% to effective dose equivalent 

 nuclide rem percent 

 sr-91 4.894E-05 1.2 

 y-92 5.403E-05 1.3 

 y-93 1.314E-04 3.2 

 zr-97 3.174E-04 7.6 

 mo-99 1.281E-04 3.1 

 rh-105 4.288E-05 1.0 

 te-131m 4.158E-05 1.0 

 i-131 2.367E-04 5.7 

 te-132 2.072E-04 5.0 

 i-133 5.126E-04 12.3 

 i-135 9.619E-05 2.3 

 ce-143 1.409E-04 3.4 

 na-24 5.340E-05 1.3 

 co-60 6.773E-04 16.3 

 pu-239 9.108E-04 21.9 

 pu239 fraction in urine from inhalation exposure uptake fraction=5.000E-02 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 2.08E-18 1.98E-18 1.88E-18 

 total of all measurements and exposures 

 total dose commitments in rem for all intakes by DCF set 

 

 

 Doses from Specified DCF File 

 DCF File Info: ICRP-72 Inhalation DCFs - Max dose from all particle sizes - 3-28-2006 

 fission products activation products actinides(g+b) actinides(a) total 

 adrenals 7.932E-05 4.985E-04 2.835E-07 4.975E-05 6.279E-04 

 bone surf 2.785E-04 2.377E-04 7.352E-05 2.766E-02 2.825E-02 

 brain 5.391E-05 6.372E-05 1.823E-07 4.975E-05 1.676E-04 

 breast 6.611E-05 5.598E-04 2.557E-07 4.975E-05 6.760E-04 

 st wall 7.048E-04 2.948E-04 1.957E-06 4.975E-05 1.051E-03 

 si wall 1.234E-03 9.354E-05 3.648E-06 4.975E-05 1.381E-03 

 uli wall 3.910E-03 1.250E-04 1.368E-05 4.975E-05 4.099E-03 

 lli wall 5.918E-03 1.740E-04 2.535E-05 4.975E-05 6.167E-03 

 kidneys 7.358E-05 2.103E-04 1.521E-06 1.180E-04 4.034E-04 

 liver 8.503E-05 4.542E-04 1.527E-05 6.080E-03 6.635E-03 

 et region 9.910E-03 2.965E-03 4.353E-05 2.768E-04 1.320E-02 

 lung 6.363E-03 3.953E-03 6.643E-05 6.099E-04 1.099E-02 

 muscle 7.982E-05 2.320E-04 2.587E-07 4.975E-05 3.618E-04 

 ovaries 2.097E-04 6.707E-05 1.416E-06 3.686E-04 6.468E-04 

 pancreas 8.349E-05 3.674E-04 2.907E-07 4.975E-05 5.010E-04 

 r marrow 1.926E-04 2.863E-04 3.076E-06 1.364E-03 1.846E-03 

 skin 4.490E-05 1.328E-04 1.851E-07 4.975E-05 2.276E-04 

 spleen 7.138E-05 3.948E-04 2.674E-07 4.975E-05 5.162E-04 

 testes 4.165E-05 2.479E-05 1.028E-06 3.870E-04 4.545E-04 

 thymus 9.302E-05 6.317E-04 3.041E-07 4.975E-05 7.748E-04 

Figure C-7. Example Problem 6 - Residence Island (continued).

C-19
 thyroid 1.698E-02 2.340E-04 2.110E-07 4.975E-05 1.726E-02 

 uterus 1.187E-04 5.176E-05 3.582E-07 4.975E-05 2.206E-04 

 ubld wall 3.721E-04 4.377E-05 5.846E-07 4.975E-05 4.662E-04 

 eff dose 2.485E-03 7.332E-04 1.258E-05 9.217E-04 4.153E-03 

 pu239 fraction in urine from all exposures 

 time after shot (yrs) 50. 55. 60. 

 conc (ci/day) or (ci/1.4l) 2.08E-18 1.98E-18 1.88E-18 

 end 

Figure C-7. Example Problem 6 - Residence Island (concluded). 

C-20
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