Page 1 of 33

DOE Review Release 09/26/2023

Dose Estimation from Intakes of Exotic 

Radionuclides at the Los Alamos Neutron 

Science Center, 1996 to 2005

ORAUT-RPRT-0107 Rev. 00

Effective Date: 09/15/2023

Supersedes: None

Subject Expert(s): Thomas R. LaBone

Document Owner 

Approval: Signature on File

Thomas R. LaBone, Document Owner

Approval Date: 09/14/2023

Concurrence: Signature on File

Pat McCloskey, Objective 4 Manager

Concurrence Date: 09/14/2023

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 09/14/2023

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 09/15/2023

FOR DOCUMENTS MARKED AS A TOTAL REWRITE OR REVISION,

REPLACE THE PRIOR REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.

New Total Rewrite Revision
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 2 of 33

 

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

09/15/2023 00 New report to address concerns about the ability to reconstruct Los 

Alamos Neutron Science Center worker doses from “exotic” 

radionuclides. Incorporates formal internal and NIOSH review 

comments. Training is not required. Initiated by Pat McCloskey and 

authored by Thomas R. LaBone.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 3 of 33

 

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 4

1.0 Introduction .............................................................................................................................. 5

2.0 Reference Radionuclide Mixture and Indicator......................................................................... 5

2.1 Radionuclide Mixtures in Accelerator Components....................................................... 6

2.2 Dosimetrically Significant Radionuclides in Mark-I1L Tungsten Target ....................... 11

3.0 Example Committed Organ Dose Calculation ........................................................................ 12

4.0 Summary ............................................................................................................................... 13

References ........................................................................................................................................ 14

ATTACHMENT A ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE 

SOLUBILITY CATEGORIES........................................................................... 16

ATTACHMENT B TABLES FROM WHICH THE BAR PLOTS IN FIGURES 2-1 THROUGH 

2-7 WERE CONSTRUCTED........................................................................... 31

LIST OF TABLES

TABLE TITLE PAGE

2-1 Number of nuclides in targets................................................................................................... 7

2-2 Dosimetrically significant Mark-I1L nuclides with ICRP Publication 68 organ DCFs ............... 12

A-1 All nuclides in Mark-I1L target assigned to three solubility categories with absorption 

types V (vapor), F, M, or S ..................................................................................................... 16

B-1 Dosimetrically significant nuclides in Mark-I1L ....................................................................... 32

B-2 Dosimetrically significant nuclides in beam stop..................................................................... 32

B-3 Dosimetrically significant nuclides in beam window................................................................ 32

B-4 Dosimetrically significant nuclides in Insert 1.......................................................................... 32

B-5 Dosimetrically significant nuclides in Insert 2.......................................................................... 32

B-6 Dosimetrically significant nuclides in Shielding 1.................................................................... 32

B-7 Dosimetrically significant nuclides in Shielding 2.................................................................... 33

LIST OF FIGURES

FIGURE TITLE PAGE

2-1 Mark I1L tungsten target .......................................................................................................... 8

2-2 Beam stop................................................................................................................................ 8

2-3 Beam window........................................................................................................................... 9

2-4 Insert 1..................................................................................................................................... 9

2-5 Insert 2...................................................................................................................................10

2-6 Shielding 1 .............................................................................................................................10

2-7 Shielding 2 .............................................................................................................................11
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 4 of 33

ACRONYMS AND ABBREVIATIONS

CED committed effective dose

d day

DCF dose conversion factor

DOE U.S. Department of Energy

F fast (absorption type)

ICRP International Commission on Radiological Protection

LANL Los Alamos National Laboratory

LANSCE Los Alamos Neutron Science Center

M moderate (absorption type)

MDA minimum detectable amount

mrem millirem

nCi nanocurie

NCRP National Council on Radiological Protection and Measurements

NIOSH National Institute for Occupational Safety and Health

OBT organically bound tritium

ORAU Oak Ridge Associated Universities

ORAUT ORAU Team

ppm parts per million

S slow (absorption type)

SRDB Ref ID Site Research Database Reference Identification (number)

V vapor
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1.0 INTRODUCTION

In Los Alamos National Laboratory (LANL) work group discussions, concerns have been raised about 

the group’s ability to assess doses to Los Alamos Neutron Science Center (LANSCE) workers 

delivered by intakes of “exotic” radionuclides.

1 In this document, exotic radionuclides are defined as

activation and spallation products generated directly or indirectly by the accelerator proton beam for 

which bioassay results are not available for dose reconstruction.

2 The question addressed here is how 

to bound the potential dose to workers at LANSCE from intakes of radionuclides that were not 

adequately measured by whole body counting (i.e., exotic radionuclides). 

1 For example: concern about spallation products from accelerator [National Institute for Occupational Safety and Health

(NIOSH) 2017, p. 80]; how to monitor for exotics [NIOSH 2017 p. 57]; and issues in monitoring for short-lived 

radionuclides [NIOSH 2018, p. 68]. 2 In a LANL Work Group discussion [NIOSH 2018, p. 6] it was suggested that “exotics” are radionuclides for which 

“NIOSH lacked the sufficient information necessary to complete individual dose reconstructions with sufficient accuracy.” 

Here that definition is defined so that it focuses on the lack of bioassay results for a radionuclide being the perceived 

cause of the inability to reconstruct dose.

The strategy used to answer this question is similar to that in ORAUT-OTIB-0054, Fission and 

Activation Product Assignment for Internal Dose-Related Gross Beta and Gross Gamma Analyses 

[Oak Ridge Associated Universities (ORAU) Team (ORAUT) 2015]. The proof-of-principle calculations 

presented here (1) identify a reference radionuclide mixture that contains exotics and (2) identify an 

appropriate indicator in the mixture (i.e., a radionuclide that was monitored in routine bioassay of 

LANSCE workers). The radionuclide mixtures in seven different accelerator components are 

calculated in Section 2.1. Subsequently, the indicator radionuclide and the reference radionuclide 

mixture are selected. The number of radionuclides in the reference mixture can be quite large, making 

dose calculations unwieldy. Thus, in Section 2.2, the mixture is simplified by removing dosimetrically 

insignificant radionuclides using committed effective dose (CED) dose conversion factors (DCFs) for 

three versions of the reference mixture that have different solubilities in the respiratory tract. The final 

products of the source term analysis are lists of radionuclides and the relative quantities of activity 

(Table 2-2 in Section 2.2). Intakes of the indicator radionuclide are calculated using standard dose 

reconstruction methods, from which the intakes of the exotics in the mixture are calculated by looking 

at the relative abundance of the indicator to each exotic. Example missed committed organ doses are 

calculated in Section 3.0 to illustrate how to apply this method. All calculations [ORAUT 2023a] were 

performed with the statistical computing software R. 

2.0 REFERENCE RADIONUCLIDE MIXTURE AND INDICATOR

In CN-LANSCE-LFO-07-002 [Kelsey 2007a, p. 16–81], LANL calculated the composition of various 

components of the accelerator under typical operational parameters (e.g., beam current and length of 

exposure). The goal of the analysis was to identify a bounding radionuclide mixture to calculate dose 

to the maximally exposed offsite individual resulting from the maximum credible incident. In that 

report, the mixture of radionuclides at the end of bombardment for nine different components of the 

accelerator were reported:

1. Concrete, 

2. Uranium shielding, 

3. Two beam inserts,

4. Two shields,
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 6 of 33

 

5. A beam window,

6. A beam stop, and

7. A tungsten spallation target.

The beam stop and tungsten target were expected to be the primary components of interest because 

there are no significant activation and spallation products produced in the depleted uranium shielding 

[ORAUT 2022a]. In the analysis, a loss of coolant accident involving an irradiated Mark-I1L tungsten 

target was selected as the design basis accident for the LANSCE facility. An updated Mark-I1L 

radionuclide inventory presented in CN-LANSCE-LFO-07-014 subsequently provided by LANL 

[Kelsey 2007b; ORAUT 2022b] was considered by the LANL scientists as more representative of 

actual accelerator operating conditions during the period of interest. The inventory presented for the 

tungsten target in Appendix 3 of CN-LANSCE-LFO-07-014 is used here as the reference mixture. 

LANL scientists confirmed that this radionuclide mixture for the Mark-I1L target would be bounding for 

all of LANSCE including areas where isotope production took place (A Area) and the Weapons 

Neutron Research Facility [ORAUT 2023b]. In Section 2.1, summaries for the radionuclide mixtures in 

accelerator components are given to show that, of all the mixtures considered, the tungsten target

would deliver the largest internal dose. Radionuclides produced by neutron activation of elements 

present in ambient air and coolant water, like 7

Be, 11C, 13N, and 41Ar [National Council on Radiological 

Protection and Measurements (NCRP) 2003, Table 6.5], are frequently detected by stack and 

workplace air monitoring. These radionuclides are not considered here because they are 

dosimetrically insignificant in comparison with the inventory of the tungsten target.

Ideally, the indicator radionuclide should be a component of the mixture that is readily detected and 

quantified by standard bioassay methods while having a high activity fraction in the mixture. Using 

these criteria, 60Co was chosen as the indicator radionuclide. Using standard dose reconstruction 

methods, the intake of the 60Co is calculated from the in vivo bioassay and the intakes of the other 

radionuclides in the mixture are calculated from the activity ratio of the components to the 60Co. 

2.1 RADIONUCLIDE MIXTURES IN ACCELERATOR COMPONENTS

The radionuclide mixtures in LANSCE components were extracted from Appendix 3 of CN-LANSCELFO-07-014 [Kelsey 2007b]. The number of radionuclides in each component considered for dose 

assessments were reduced by applying the following successive criteria to radionuclides reported for 

the mixture:

1. Target must have 60Co listed as a significant component by activity since it is the indicator 

radionuclide.

3 Thus, all targets other than depleted uranium (which has no 60Co) and concrete 

(which has ~2 ppm 60Co by activity) are considered. Both depleted uranium and concrete are 

structural/shielding materials, and there is no plausible mechanism for releasing contamination 

from these materials into the workplace [ORAUT 2022a, p. 8].

3 The next best choice for an indicator radionuclide is 22Na, but it is less desirable as an indicator because, as will be 

seen, the 148Gd/22Na activity ratio is much higher than the 148Gd/60Co activity ratio.

2. All radionuclides in the target that do not have an International Commission on Radiological 

Protection (ICRP) Publication 68 [ICRP 1995] DCF are removed. The original number of 

radionuclides in each target and the number that have ICRP Publication 68 DCF4 are given in 

Table 2-1. 

4 ICRP Publication 68 does not provide DCFs for noble gases and radionuclides with a half-life of less than 10 minutes. 

The tungsten target had eight additional radionuclides that were not in ICRP Publication 68, reportedly because of large 

uncertainty associated with their decay schemes.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 7 of 33

 

Table 2-1. Number of nuclides in 

targets.a

Target N0 N

Mark-I1L 156 136

Beam stop 27 24

Beam window 27 24

Insert 1 22 19

Insert 2 23 20

Shielding 1 26 23

Shielding 2 21 18

a. N0 = number from ICRP [1995]; N = number 

from ICRP [1995] having DCF.

The number of radionuclides in each component and the proportion of dose delivered by the 

radionuclides are shown in the bar plots in Figures 2-1 to 2-7 (the Attachment B tables contain the 

data for those figures). Radionuclides in the component that deliver more than 1% of the total dose 

are given their own bar in the bar plots while the rest are combined under “Other.” Note that this is to 

facilitate construction of the bar plot and that all the radionuclides are retained for dose calculations. 

The DCF given in each plot is the CED delivered by the radionuclide mixture in the component for 

each nCi of 60Co inhaled. Note that the DCF for the mixture was calculated using the largest DCF for 

each radionuclide. For example, if the DCF for Type S of a given radionuclide was higher than the 

DCF for Type M of the radionuclide, then the DCF for Type S was used. The factor X, which is used to 

select the target that gives the highest dose, is how much the dose increases over that expected from 

an intake of 1 nCi of pure Type S 60Co. The number over “Other” is the proportion of the total dose 

delivered by all the radionuclides not specifically named.

Cobalt-60 is the primary dose contributor for all components except the Mark-I1L tungsten target 

(Figure 2-1). This target is of particular interest because the major contributor to the CED is the alpha 

emitter 148Gd, which is a spallation product of tungsten. Gadolinium-148 is known as the radionuclide 

of primary internal dosimetry concern for the tungsten targets because of its 75-year half-life [Kelley 

2004]. A complete listing of the 136 nuclides for the tungsten target is given in Table A-1 

(Attachment A). Based on the plots in Figures 2-1 to 2-7 and the likelihood of individuals being 

exposed to material from each target, the Mark-I1L tungsten target is the most appropriate for 

bounding doses to workers from intakes of exotic radionuclides at LANSCE. Note that for the plots in 

Figures 2-1 to 2-7, N is the number of radionuclides in the target, DCF is the CED in millirem from the 

mixture for every nanocurie of inhaled 60Co, and X is the factor by which the dose increases in the 

mixture in comparison with pure 60Co.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 8 of 33

 

Figure 2-1. Mark-I1L tungsten target (data in Table B-1). 

Figure 2-2. Beam stop (data in Table B-2). 
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 9 of 33

 

Figure 2-3. Beam window (data in Table B-3). 

Figure 2-4. Insert 1 (data in Table B-4). 
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 10 of 33

 

Figure 2-5. Insert 2 (data in Table B-5).

Figure 2-6. Shielding 1 (data in Table B-6). 
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 11 of 33

 

Figure 2-7. Shielding 2 (data in Table B-7). 

2.2 DOSIMETRICALLY SIGNIFICANT RADIONUCLIDES IN MARK-I1L TUNGSTEN TARGET

To remove radionuclides in the tungsten target that do not have significant dosimetric impact, three

solubility groups are created: soluble, moderate, and insoluble. For each of the 136 radionuclides in 

the Mark-I1L tungsten target, the ICRP Publication 68 absorption type (F, M, or S) that best agrees 

with the solubility group is assigned. This is essentially the same procedure used in ORAUT-OTIB0054 [ORAUT 2015], with the possible exception of how vapors (V) are handled.

5 The complete list of 

136 radionuclides is given in Table A-1 (Attachment A). Next, select significant radionuclides for the 

Mark-I1L target in each of the three solubility categories based on committed organ dose:

5 For radionuclides with multiple types of vapors, use the one with the highest DCF. In particular, use the organically 

bound tritium (OBT) DCF for tritium.

1. For each of the 26 organs, calculate the relative dose from all 136 radionuclides.

2. Retain radionuclides that contribute at least 1% of the dose to any of the 26 organs.

Finally, take the union of the radionuclides in the three lists, which gives the 13 dosimetrically 

significant radionuclides shown in Table 2-2. These are the same criteria used in ORAUT-OTIB-0054

to select dosimetrically significant radionuclides. Maximum committed organ DCF for adrenals, bone 

surface, and lung are provided in Table 2-2 for use in the next section.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 12 of 33

 

Table 2-2. Dosimetrically significant Mark-I1L nuclides with ICRP Publication 68 

organ DCFs (mrem/nCi of nuclide).a

i

b Nuclide Activityc

DCF

adrenal

DCF

bone surface

DCF

lung

1 Cd-113m 0.0581 0.07400 0.07400 0.34410

2 Co-60 0.1713 0.04070 0.01813 0.35520

3 Fe-55 0.1127 0.00096 0.00666 0.00096

4 Gd-148 0.0022 0.00481 3,700.0000 21.83000

5 H-3 0.3278 0.00015 0.00015 0.00015

6 Hf-172 0.0456 0.10730 3.29300 0.15170

7 Hg-194 0.0003 0.17760 0.14430 0.18130

8 Lu-172 0.0461 0.00081 0.00278 0.02664

9 Lu-173 0.0319 0.00185 0.09250 0.03515

10 Na-22 0.0039 0.00629 0.01147 0.00481

11 Ni-63 0.0121 0.00629 0.00629 0.01036

12 Ta-179 0.1516 0.00044 0.00063 0.00666

13 Tl-204 0.0363 0.00118 0.00118 0.00130

a. Source: ICRP [1995].

b. See the equations below for the use of i. 

c. Note that the activity sums to 1.

3.0 EXAMPLE COMMITTED ORGAN DOSE CALCULATION

In in vivo counts performed in 1996 to 2005 at LANL, 60Co was specifically reported only if it was 

identified by a peak search. Out of 330 whole body counts performed in 1996 to 2005, 60Co was 

identified in only one instance [ORAUT 2023a]. Counts on the LANL whole body counter where no 

60Co is reported are interpreted as being less than the minimum detectable amount (MDA) of 0.83 nCi 

for 60Co [Archuleta 2022]. In this example, the MDA for 60Co will be used to calculate the missed dose 

from a <MDA result.

Assuming a constant chronic intake of Type S 60Co for 1 year, a 60Co body burden of MDA/2 at the 

end of the chronic intake implies a total intake IS of 10.7 nCi (intake rate of 0.0293 nCi/d). Using the 

relative activities Ai of the radionuclides in the target and the committed organ DCF in Table 2-2, the 

50-year committed organ doses from the intake of the mixture are:

(3-1)

13

lung S lung,

1 2

i

i 8.66 mrem

i

A H I DCF = A

  =   =

  ∑

(3-2) 13

bs S bs,

1 2

i

i 508 mrem i

A H I DCF = A

  =   =

  ∑

(3-3)

13

adrenals S adrenals,

1 2

i

i 1.04 mrem

i

A H I DCF = A

  =   =

  ∑

where

A2 = activity of 60Co in the mixture.

Next, assuming a constant chronic intake of Type M 60Co for 1 year, a 60Co body burden of MDA/2 at 

the end of the chronic intake implies a total intake IM of 14.3 nCi (intake rate of 0.0392 nCi/d). Using 
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 13 of 33

 

the relative activities Ai of the radionuclides in the target and the committed organ DCF in Table 2-2, 

the 50-year committed organ doses from the intake of the moderately soluble mixture are:

(3-4)

13

lung lung,

1

M

2

i

i 11.6 mrem

i

A H I DCF = A

  =   =

  ∑

(3-5)

3

M

1

bs bs,

1 2

i

i 679 mrem

i

A H I DCF = A

  =   =

  ∑

(3-6)

13

adrenals adrenals,

1

M

2

i

i 1.39 mrem

i

A H I DCF = A

  =   =

  ∑

Note that different absorption types of 60Co were used to evaluate the bioassay data but the same 

maximum DCFs were used in both cases. In practice, the annual doses would be required for each 

organ, but this example shows how the calculations can be performed. 

4.0 SUMMARY

The question addressed here is how to bound the potential dose to workers at LANSCE from intakes

of radionuclides not adequately measured by whole body counting. This proof-of-principle calculation: 

1. Specifies a reference source that defines the relative amounts of all dosimetrically significant 

radionuclides in the Mark-I1L tungsten target, which is bounding for exposures of workers; 

2. Specifies 60Co as the indicator radionuclide in the source for whole body counting; 

3. Uses standard dose reconstruction procedures to estimate the intake of 60Co from whole body

count results reported by LANL; 

4. Uses the estimated 60Co intake and the reference source to estimate the intakes of all 

radionuclides in the reference source; and

5. Assigns committed organ doses from the intake of the radionuclide mixture.

This approach accounts for the dose from all radionuclides with a half-life of greater than 10 minutes, 

a restriction imposed by the availability of DCFs in ICRP Publication 68 [ICRP 1995]. In general, the 

missed 50-year committed organ doses associated with a <MDA result for 60Co on an annual in vivo 

count are less than approximately 10 mrem except for bone surfaces doses, which are about 50 times 

higher. The implementation of the method for an actual dose reconstruction requires annual organ 

doses, which is a more complex calculation that might require the use of a software tool.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 14 of 33

 

REFERENCES

Archuleta S [2022]. LANL partial response to data request LANL FY22-006 data needs radionuclides 

in vivo count results and LANSCE stack monitoring data for 1996 through 2005. Letter to J.L. Jung, 

U.S. Department of Energy, National Nuclear Security Administration. Los Alamos National 

Laboratory, Los Alamos, NM: Triad National Security. RP-22-099, September 20. [SRDB Ref ID: 

193707]

ICRP [1995]. ICRP 68 - Dose coefficients for intakes of radionuclides by workers. ICRP Publication 

68. Ann ICRP 24(4). [SRDB Ref ID: 22731]

Kelley KC [2004]. Gadolinium-148 and other spallation production cross section measurements for 

accelerator target facilities. Dissertation. Atlanta, GA: Georgia Institute of Technology. March 17. 

[SRDB Ref ID: 196439]

Kelsey C [2007a]. Bounding radionuclide inventory and accident consequence calculations for the 1L 

target. Los Alamos National Laboratory, Los Alamos, NM: Los Alamos National Security. 

CN-LANSCE-LFO-07-002. October 30. [SRDB Ref ID: 192061]

Kelsey C [2007b]. Area A east radionuclide inventory – November 30, 2007. Los Alamos National 

Laboratory, Los Alamos, NM: Los Alamos National Security. CN-LANSCE-LFO-07-014. November 

30. [SRDB Ref ID: 197909] 

NCRP [2003]. NCRP 144 - Radiation protection for particle accelerator facilities. Bethesda, MD: 

National Council on Radiation Protection and Measurements. NCRP Report 144. December 31. 

[SRDB Ref ID: 115764]

NIOSH [2017]. U.S. Department of Health and Human Services Centers for Disease Control National 

Institute for Occupational Safety and Health Advisory Board on Radiation and Worker Health Los 

Alamos National Laboratory Work Group (LANL). Transcript. Washington, DC: U.S. Department of 

Health and Human Services, Centers for Disease Control and Prevention, National Institute for 

Occupational Safety and Health, Advisory Board on Radiation and Worker Health. August 15. [SRDB 

Ref ID: 174238]

NIOSH [2018]. U.S. Department of Health and Human Services Centers for Disease Control National 

Institute for Occupational Safety and Health Advisory Board on Radiation and Worker Health Los 

Alamos National Laboratory Work Group. Transcript. Washington, DC: U.S. Department of Health and 

Human Services, Centers for Disease Control and Prevention, National Institute for Occupational 

Safety and Health, Advisory Board on Radiation and Worker Health. November 29. [SRDB Ref ID: 

184934]

ORAUT [2015]. Fission and activation product assignment for internal dose-related gross beta and 

gross gamma analyses. Oak Ridge, TN: Oak Ridge Associated Universities Team. ORAUT-OTIB0054 Rev. 04, August 27. [SRDB Ref ID: 146884]

ORAUT [2022a]. Documented communication SEC-00109 with [redacted] and [redacted] on ability to 

perform dose reconstruction for Los Alamos National Laboratory and LANSCE/TA-53 employees. Oak 

Ridge, TN: Oak Ridge Associated Universities Team. August 2. [SRDB Ref ID: 194720]

ORAUT [2022b]. Documented communication SEC-00109 with [redacted] on development of 

implementable methodology for dose reconstruction at Los Alamos National Laboratory. Oak Ridge, 

TN: Oak Ridge Associated Universities Team. June 21. [SRDB Ref ID: 194721]
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ORAUT [2023a]. ORAUT-RPRT-0107 Rev. 00 support files. Zip file. Oak Ridge, TN: Oak Ridge 

Associated Universities Team. May 17. [SRDB Ref ID: 197521]

ORAUT [2023b]. LANL interviews March 14, 2023. Oak Ridge, TN: Oak Ridge Associated 

Universities Team. March 21. [SRDB Ref ID: 196584]
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ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

Table A-1. All nuclides in Mark-I1L target assigned to three solubility categories with absorption types

V (vapor), F, M, or S. In the case where a radionuclide has multiple types (e.g., multiple vapors), the 

most restrictive one is used.

Nuclide Half-life (d) Soluble Moderate Insoluble

H-3 4.510837E+03 V (OBT) V (OBT) V (OBT)

Be-7 5.330000E+01 M M S

Be-10 5.844000E+08 M M S

C-11 1.415280E−02 V V V

C-14 2.092883E+06 V V V

F-18 7.622920E−02 F M S

Na-22 9.503805E+02 F F F

Na-24 6.250000E−01 F F F

Mg-28 8.712500E−01 F M M

Al-26 2.615190E+08 F M M

Si-31 1.092361E−01 F M S

Si-32 1.643625E+05 F M S

P-32 1.429000E+01 F M M

P-33 2.540000E+01 F M M

S-35 8.744000E+01 V F M

Cl-36 1.099403E+08 F M M

Cl-38 2.584030E−02 F M M

Cl-39 3.861110E−02 F M M

K-40 4.675200E+11 F F F

K-42 5.150000E−01 F F F

K-43 9.416667E−01 F F F

K-44 1.536810E−02 F F F

K-45 1.388890E−02 F F F

Ca-41 5.113500E+07 M M M

Ca-45 1.630000E+02 M M M

Ca-47 4.530000E+00 M M M

Sc-43 1.621250E−01 S S S

Sc-44 1.636250E−01 S S S

Sc-44m 2.441667E+00 S S S

Sc-46 8.383000E+01 S S S

Sc-47 3.351000E+00 S S S

Sc-48 1.820833E+00 S S S

Sc-49 3.986110E−02 S S S

Ti-44 1.727633E+04 F M S

Ti-45 1.283333E−01 F M S

V-47 2.263890E−02 F M M

V-48 1.623800E+01 F M M

V-49 3.300000E+02 F M M

Cr-48 9.566667E−01 F M S

Cr-49 2.922920E−02 F M S

Cr-51 2.770400E+01 F M S

Mn-51 3.208330E−02 F M M

Mn-52 5.591000E+00 F M M

Mn-52m 1.465280E−02 F M M

Mn-53 1.351425E+09 F M M

Mn-54 3.125000E+02 F M M

Mn-56 1.074375E−01 F M M

Fe-52 3.447917E−01 F M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 17 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Fe-55 9.861750E+02 F M M

Fe-59 4.452900E+01 F M M

Fe-60 3.652500E+07 F M M

Co-55 7.308333E−01 M M S

Co-56 7.876000E+01 M M S

Co-57 2.709000E+02 M M S

Co-58 7.080000E+01 M M S

Co-58m 3.812500E−01 M M S

Co-60 1.925233E+03 M M S

Co-60m 7.270800E−03 M M S

Co-61 6.875000E−02 M M S

Co-62m 9.659700E−03 M M S

Ni-56 6.100000E+00 V F M

Ni-57 1.503333E+00 V F M

Ni-59 2.739375E+07 V F M

Ni-63 3.506400E+04 V F M

Ni-65 1.050000E−01 V F M

Ni-66 2.275000E+00 V F M

Cu-60 1.611110E−02 F M S

Cu-61 1.420000E−01 F M S

Cu-64 5.292083E−01 F M S

Cu-67 2.577500E+00 F M S

Zn-62 3.858333E−01 S S S

Zn-63 2.645830E−02 S S S

Zn-65 2.439000E+02 S S S

Zn-69 3.958330E−02 S S S

Zn-69m 5.733333E−01 S S S

Zn-71m 1.633333E−01 S S S

Zn-72 1.937500E+00 S S S

Ga-65 1.055560E−02 F M M

Ga-66 3.916667E−01 F M M

Ga-67 3.260833E+00 F M M

Ga-68 4.722220E−02 F M M

Ga-70 1.468750E−02 F M M

Ga-72 5.875000E−01 F M M

Ga-73 2.045833E−01 F M M

Ge-66 9.458330E−02 F M M

Ge-67 1.298610E−02 F M M

Ge-68 2.880000E+02 F M M

Ge-69 1.627083E+00 F M M

Ge-71 1.180000E+01 F M M

Ge-75 5.748610E−02 F M M

Ge-77 4.708333E−01 F M M

Ge-78 6.041670E−02 F M M

As-69 1.055560E−02 M M M

As-70 3.652780E−02 M M M

As-71 2.700000E+00 M M M

As-72 1.083333E+00 M M M

As-73 8.030000E+01 M M M

As-74 1.776000E+01 M M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 18 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

As-76 1.096667E+00 M M M

As-77 1.616667E+00 M M M

As-78 6.298610E−02 M M M

Se-70 2.847220E−02 F M M

Se-73 2.979167E−01 F M M

Se-73m 2.708330E−02 F M M

Se-75 1.198000E+02 F M M

Se-79 2.374125E+07 F M M

Se-81 1.284720E−02 F M M

Se-81m 3.975690E−02 F M M

Se-83 1.562500E−02 F M M

Br-74 1.756940E−02 F M M

Br-74m 2.881940E−02 F M M

Br-75 6.805560E−02 F M M

Br-76 6.750000E−01 F M M

Br-77 2.333333E+00 F M M

Br-80 1.208330E−02 F M M

Br-80m 1.841667E−01 F M M

Br-82 1.470833E+00 F M M

Br-83 9.958330E−02 F M M

Br-84 2.208330E−02 F M M

Rb-79 1.590280E−02 F F F

Rb-81 1.908333E−01 F F F

Rb-81m 2.222220E−02 F F F

Rb-82m 2.583333E−01 F F F

Rb-83 8.620000E+01 F F F

Rb-84 3.277000E+01 F F F

Rb-86 1.866000E+01 F F F

Rb-87 1.716675E+13 F F F

Rb-88 1.236110E−02 F F F

Rb-89 1.055560E−02 F F F

Sr-80 6.944440E−02 F F S

Sr-81 1.770830E−02 F F S

Sr-82 2.500000E+01 F F S

Sr-83 1.350000E+00 F F S

Sr-85 6.484000E+01 F F S

Sr-85m 4.826390E−02 F F S

Sr-87m 1.168750E−01 F F S

Sr-89 5.050000E+01 F F S

Sr-90 1.063608E+04 F F S

Sr-91 3.958333E−01 F F S

Sr-92 1.129167E−01 F F S

Y-86 6.141667E−01 M M S

Y-86m 3.333330E−02 M M S

Y-87 3.345833E+00 M M S

Y-88 1.066400E+02 M M S

Y-90 2.666667E+00 M M S

Y-90m 1.329167E−01 M M S

Y-91 5.851000E+01 M M S

Y-91m 3.452080E−02 M M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 19 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Y-92 1.475000E−01 M M S

Y-93 4.208333E−01 M M S

Y-94 1.326390E−02 M M S

Y-95 7.430600E−03 M M S

Zr-86 6.875000E−01 F M S

Zr-88 8.340000E+01 F M S

Zr-89 3.267917E+00 F M S

Zr-93 5.588325E+08 F M S

Zr-95 6.398000E+01 F M S

Zr-97 7.041667E−01 F M S

Nb-88 9.930600E−03 M M S

Nb-89 8.472220E−02 M M S

Nb-89m 4.583330E−02 M M S

Nb-90 6.083333E−01 M M S

Nb-93m 4.967400E+03 M M S

Nb-94 7.414575E+06 M M S

Nb-95 3.515000E+01 M M S

Nb-95m 3.608333E+00 M M S

Nb-96 9.729167E−01 M M S

Nb-97 5.006940E−02 M M S

Nb-98 3.576390E−02 M M S

Mo-90 2.362500E−01 F F S

Mo-93 1.278375E+06 F F S

Mo-93m 2.854167E−01 F F S

Mo-99 2.750000E+00 F F S

Mo-101 1.015280E−02 F F S

Tc-93 1.145833E−01 F M M

Tc-93m 3.020830E−02 F M M

Tc-94 2.034722E−01 F M M

Tc-94m 3.611110E−02 F M M

Tc-95 8.333333E−01 F M M

Tc-95m 6.100000E+01 F M M

Tc-96 4.280000E+00 F M M

Tc-96m 3.576390E−02 F M M

Tc-97 9.496500E+08 F M M

Tc-97m 8.700000E+01 F M M

Tc-98 1.534050E+09 F M M

Tc-99 7.779825E+07 F M M

Tc-99m 2.508333E−01 F M M

Tc-101 9.861100E−03 F M M

Tc-104 1.263890E−02 F M M

Ru-94 3.597220E−02 V F M

Ru-97 2.900000E+00 V F M

Ru-103 3.928000E+01 V F M

Ru-105 1.850000E−01 V F M

Ru-106 3.682000E+02 V F M

Rh-99 1.600000E+01 F M S

Rh-99m 1.958333E−01 F M S

Rh-100 8.666667E−01 F M S

Rh-101 1.168800E+03 F M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 20 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Rh-101m 4.340000E+00 F M S

Rh-102m 1.059225E+03 F M S

Rh-102 2.070000E+02 F M S

Rh-103m 3.897220E−02 F M S

Rh-105 1.473333E+00 F M S

Rh-106m 9.166670E−02 F M S

Rh-107 1.506940E−02 F M S

Pd-100 3.630000E+00 F M S

Pd-101 3.445833E−01 F M S

Pd-103 1.696000E+01 F M S

Pd-107 2.374125E+09 F M S

Pd-109 5.594583E−01 F M S

Ag-102 8.958300E−03 F M S

Ag-103 4.562500E−02 F M S

Ag-104 4.805560E−02 F M S

Ag-104m 2.326390E−02 F M S

Ag-105 4.100000E+01 F M S

Ag-106 1.663890E−02 F M S

Ag-106m 8.410000E+00 F M S

Ag-108m 4.638675E+04 F M S

Ag-110m 2.499000E+02 F M S

Ag-111 7.450000E+00 F M S

Ag-112 1.300000E−01 F M S

Ag-115 1.388890E−02 F M S

Cd-104 4.006940E−02 F M S

Cd-107 2.704167E−01 F M S

Cd-109 4.640000E+02 F M S

Cd-113 3.396825E+18 F M S

Cd-113m 4.967400E+03 F M S

Cd-115 2.227500E+00 F M S

Cd-115m 4.460000E+01 F M S

Cd-117 1.037500E−01 F M S

Cd-117m 1.400000E−01 F M S

In-109 1.750000E−01 F M M

In-110 2.041667E−01 F M M

In-110m 4.798610E−02 F M M

In-111 2.830000E+00 F M M

In-112 1.000000E−02 F M M

In-113m 6.908330E−02 F M M

In-114m 4.951000E+01 F M M

In-115 1.862775E+18 F M M

In-115m 1.869167E−01 F M M

In-116m 3.760420E−02 F M M

In-117 3.041670E−02 F M M

In-117m 8.090280E−02 F M M

In-119m 1.250000E−02 F M M

Sn-110 1.666667E−01 F M M

Sn-111 2.451390E−02 F M M

Sn-113 1.151000E+02 F M M

Sn-117m 1.361000E+01 F M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 21 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Sn-119m 2.930000E+02 F M M

Sn-121 1.127500E+00 F M M

Sn-121m 2.008875E+04 F M M

Sn-123 1.292000E+02 F M M

Sn-123m 2.783330E−02 F M M

Sn-125 9.640000E+00 F M M

Sn-126 3.652500E+07 F M M

Sn-127 8.750000E−02 F M M

Sn-128 4.104170E−02 F M M

Sb-115 2.208330E−02 F M M

Sb-116 1.097220E−02 F M M

Sb-116m 4.187500E−02 F M M

Sb-117 1.166667E−01 F M M

Sb-118m 2.083333E−01 F M M

Sb-119 1.587500E+00 F M M

Sb-120m 5.760000E+00 F M M

Sb-120 1.103470E−02 F M M

Sb-122 2.700000E+00 F M M

Sb-124 6.020000E+01 F M M

Sb-124n 1.402780E−02 F M M

Sb-125 1.011742E+03 F M M

Sb-126 1.240000E+01 F M M

Sb-126m 1.319440E−02 F M M

Sb-127 3.850000E+00 F M M

Sb-128 3.754167E−01 F M M

Sb-128m 7.222200E−03 F M M

Sb-129 1.800000E−01 F M M

Sb-130 2.777780E−02 F M M

Sb-131 1.597220E−02 F M M

Te-116 1.037500E−01 V F M

Te-121 1.700000E+01 V F M

Te-121m 1.540000E+02 V F M

Te-123 3.652500E+15 V F M

Te-123m 1.197000E+02 V F M

Te-125m 5.800000E+01 V F M

Te-127 3.895833E−01 V F M

Te-127m 1.090000E+02 V F M

Te-129 4.833330E−02 V F M

Te-129m 3.360000E+01 V F M

Te-131 1.736110E−02 V F M

Te-131m 1.250000E+00 V F M

Te-132 3.258333E+00 V F M

Te-133 8.645800E−03 V F M

Te-133m 3.847220E−02 V F M

Te-134 2.902780E−02 V F M

I-120 5.625000E−02 V F F

I-120m 3.680560E−02 V F F

I-121 8.833330E−02 V F F

I-123 5.500000E−01 V F F

I-124 4.180000E+00 V F F
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 22 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

I-125 6.014000E+01 V F F

I-126 1.302000E+01 V F F

I-128 1.735420E−02 V F F

I-129 5.734425E+09 V F F

I-130 5.150000E−01 V F F

I-131 8.040000E+00 V F F

I-132 9.583330E−02 V F F

I-132m 5.805560E−02 V F F

I-133 8.666667E−01 V F F

I-134 3.652780E−02 V F F

I-135 2.754167E−01 V F F

Cs-125 3.125000E−02 F F F

Cs-127 2.604167E−01 F F F

Cs-129 1.335833E+00 F F F

Cs-130 2.076390E−02 F F F

Cs-131 9.690000E+00 F F F

Cs-132 6.475000E+00 F F F

Cs-134 7.531455E+02 F F F

Cs-134m 1.208333E−01 F F F

Cs-135 8.400750E+08 F F F

Cs-135m 3.680560E−02 F F F

Cs-136 1.310000E+01 F F F

Cs-137 1.095750E+04 F F F

Cs-138 2.236110E−02 F F F

Ba-126 6.701390E−02 F F F

Ba-128 2.430000E+00 F F F

Ba-131 1.180000E+01 F F F

Ba-131m 1.013890E−02 F F F

Ba-133 3.922785E+03 F F F

Ba-133m 1.620833E+00 F F F

Ba-135m 1.195833E+00 F F F

Ba-139 5.743060E−02 F F F

Ba-140 1.274000E+01 F F F

Ba-141 1.268750E−02 F F F

Ba-142 7.361100E−03 F F F

La-131 4.097220E−02 F M M

La-132 2.000000E−01 F M M

La-135 8.125000E−01 F M M

La-137 2.191500E+07 F M M

La-138 4.930875E+13 F M M

La-140 1.678000E+00 F M M

La-141 1.637500E−01 F M M

La-142 6.423610E−02 F M M

La-143 9.881900E−03 F M M

Ce-134 3.000000E+00 M M S

Ce-135 7.333333E−01 M M S

Ce-137 3.750000E−01 M M S

Ce-137m 1.433333E+00 M M S

Ce-139 1.376600E+02 M M S

Ce-141 3.250100E+01 M M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 23 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Ce-143 1.375000E+00 M M S

Ce-144 2.843000E+02 M M S

Pr-136 9.097200E−03 M M S

Pr-137 5.319440E−02 M M S

Pr-138m 8.750000E−02 M M S

Pr-139 1.879167E−01 M M S

Pr-142 7.970833E−01 M M S

Pr-142m 1.013890E−02 M M S

Pr-143 1.356000E+01 M M S

Pr-144 1.200000E−02 M M S

Pr-145 2.491667E−01 M M S

Pr-147 9.444400E−03 M M S

Nd-136 3.517360E−02 M M S

Nd-138 2.100000E−01 M M S

Nd-139 2.062500E−02 M M S

Nd-139m 2.291667E−01 M M S

Nd-141 1.037500E−01 M M S

Nd-147 1.098000E+01 M M S

Nd-149 7.208330E−02 M M S

Nd-151 8.638900E−03 M M S

Pm-141 1.451390E−02 M M S

Pm-143 2.650000E+02 M M S

Pm-144 3.630000E+02 M M S

Pm-145 6.464925E+03 M M S

Pm-146 2.020000E+03 M M S

Pm-147 9.581969E+02 M M S

Pm-148 5.370000E+00 M M S

Pm-148m 4.130000E+01 M M S

Pm-149 2.211667E+00 M M S

Pm-150 1.116667E−01 M M S

Pm-151 1.183333E+00 M M S

Sm-141 7.083300E−03 M M M

Sm-141m 1.569440E−02 M M M

Sm-142 5.034030E−02 M M M

Sm-145 3.400000E+02 M M M

Sm-146 3.762075E+10 M M M

Sm-147 3.871650E+13 M M M

Sm-151 3.287250E+04 M M M

Sm-153 1.945833E+00 M M M

Sm-155 1.534720E−02 M M M

Sm-156 3.916667E−01 M M M

Eu-145 5.940000E+00 M M M

Eu-146 4.610000E+00 M M M

Eu-147 2.400000E+01 M M M

Eu-148 5.450000E+01 M M M

Eu-149 9.310000E+01 M M M

Eu-150 1.249155E+04 M M M

Eu-150m 5.258333E−01 M M M

Eu-152 4.868783E+03 M M M

Eu-152m 3.883333E−01 M M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 24 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Eu-154 3.214200E+03 M M M

Eu-155 1.811640E+03 M M M

Eu-156 1.519000E+01 M M M

Eu-157 6.312500E−01 M M M

Eu-158 3.187500E−02 M M M

Gd-145 1.590280E−02 F M M

Gd-146 4.830000E+01 F M M

Gd-147 1.587500E+00 F M M

Gd-148 3.396825E+04 F M M

Gd-149 9.400000E+00 F M M

Gd-151 1.200000E+02 F M M

Gd-152 3.944700E+16 F M M

Gd-153 2.420000E+02 F M M

Gd-159 7.733333E−01 F M M

Tb-147 6.875000E−02 M M M

Tb-149 1.729167E−01 M M M

Tb-150 1.362500E−01 M M M

Tb-151 7.333333E−01 M M M

Tb-153 2.340000E+00 M M M

Tb-154 8.916667E−01 M M M

Tb-155 5.320000E+00 M M M

Tb-156 5.340000E+00 M M M

Tb-156n 2.083333E−01 M M M

Tb-156m 1.016667E+00 M M M

Tb-157 5.478750E+04 M M M

Tb-158 5.478750E+04 M M M

Tb-160 7.230000E+01 M M M

Tb-161 6.910000E+00 M M M

Dy-155 4.166667E−01 M M M

Dy-157 3.375000E−01 M M M

Dy-159 1.444000E+02 M M M

Dy-165 9.725000E−02 M M M

Dy-166 3.400000E+00 M M M

Ho-155 3.333330E−02 M M M

Ho-157 8.750000E−03 M M M

Ho-159 2.291670E−02 M M M

Ho-161 1.041667E−01 M M M

Ho-162 1.041670E−02 M M M

Ho-162m 4.722220E−02 M M M

Ho-164 2.013890E−02 M M M

Ho-164m 2.604170E−02 M M M

Ho-166 1.116667E+00 M M M

Ho-166m 4.383000E+05 M M M

Ho-167 1.291667E−01 M M M

Er-161 1.350000E−01 M M M

Er-165 4.316667E−01 M M M

Er-169 9.300000E+00 M M M

Er-171 3.133333E−01 M M M

Er-172 2.054167E+00 M M M

Tm-162 1.506940E−02 M M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 25 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Tm-166 3.208333E−01 M M M

Tm-167 9.240000E+00 M M M

Tm-170 1.286000E+02 M M M

Tm-171 7.012800E+02 M M M

Tm-172 2.650000E+00 M M M

Tm-173 3.433333E−01 M M M

Tm-175 1.055560E−02 M M M

Yb-162 1.312500E−02 M M S

Yb-166 2.362500E+00 M M S

Yb-167 1.215280E−02 M M S

Yb-169 3.201000E+01 M M S

Yb-175 4.190000E+00 M M S

Yb-177 7.916670E−02 M M S

Yb-178 5.138890E−02 M M S

Lu-169 1.419167E+00 M M S

Lu-170 2.000000E+00 M M S

Lu-171 8.220000E+00 M M S

Lu-172 6.700000E+00 M M S

Lu-173 5.003925E+02 M M S

Lu-174 1.208977E+03 M M S

Lu-174m 1.420000E+02 M M S

Lu-176 1.314900E+13 M M S

Lu-176m 1.533333E−01 M M S

Lu-177 6.710000E+00 M M S

Lu-177m 1.609000E+02 M M S

Lu-178 1.972220E−02 M M S

Lu-178m 1.576390E−02 M M S

Lu-179 1.912500E−01 M M S

Hf-170 6.670833E−01 F M M

Hf-172 6.830175E+02 F M M

Hf-173 1.000000E+00 F M M

Hf-175 7.000000E+01 F M M

Hf-177m 3.569440E−02 F M M

Hf-178m 1.132275E+04 F M M

Hf-179m 2.510000E+01 F M M

Hf-180m 2.291667E−01 F M M

Hf-181 4.240000E+01 F M M

Hf-182 3.287250E+09 F M M

Hf-182m 4.270830E−02 F M M

Hf-183 4.444440E−02 F M M

Hf-184 1.716667E−01 F M M

Ta-172 2.555560E−02 M M S

Ta-173 1.520833E−01 M M S

Ta-174 5.000000E−02 M M S

Ta-175 4.375000E−01 M M S

Ta-176 3.366667E−01 M M S

Ta-177 2.358333E+00 M M S

Ta-178m 9.166670E−02 M M S

Ta-179 6.649000E+02 M M S

Ta-180m 3.652500E+15 M M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 26 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Ta-180 3.375000E−01 M M S

Ta-182 1.150000E+02 M M S

Ta-182m 1.100000E−02 M M S

Ta-183 5.100000E+00 M M S

Ta-184 3.625000E−01 M M S

Ta-185 3.402780E−02 M M S

Ta-186 7.291700E−03 M M S

W-176 9.583330E−02 F F F

W-177 9.375000E−02 F F F

W-178 2.170000E+01 F F F

W-179 2.604170E−02 F F F

W-181 1.212000E+02 F F F

W-185 7.510000E+01 F F F

W-187 9.958333E−01 F F F

W-188 6.940000E+01 F F F

Re-177 9.722200E−03 F M M

Re-178 9.166700E−03 F M M

Re-181 8.333333E−01 F M M

Re-182 2.666667E+00 F M M

Re-182m 5.291667E−01 F M M

Re-184 3.800000E+01 F M M

Re-184m 1.650000E+02 F M M

Re-186 3.776667E+00 F M M

Re-186m 7.305000E+07 F M M

Re-187 1.826250E+13 F M M

Re-188 7.075000E−01 F M M

Re-188m 1.291670E−02 F M M

Re-189 1.012500E+00 F M M

Os-180 1.527780E−02 F M S

Os-181 7.291670E−02 F M S

Os-182 9.166667E−01 F M S

Os-185 9.400000E+01 F M S

Os-189m 2.500000E−01 F M S

Os-191 1.540000E+01 F M S

Os-191m 5.429167E−01 F M S

Os-193 1.250000E+00 F M S

Os-194 2.191500E+03 F M S

Ir-182 1.041670E−02 F M S

Ir-184 1.258333E−01 F M S

Ir-185 5.833333E−01 F M S

Ir-186 6.583333E−01 F M S

Ir-186m 7.291670E−02 F M S

Ir-187 4.375000E−01 F M S

Ir-188 1.729167E+00 F M S

Ir-189 1.330000E+01 F M S

Ir-190 1.210000E+01 F M S

Ir-190n 1.291667E−01 F M S

Ir-190m 5.000000E−02 F M S

Ir-192 7.402000E+01 F M S

Ir-192n 8.802525E+04 F M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 27 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Ir-193m 1.190000E+01 F M S

Ir-194 7.979167E−01 F M S

Ir-194m 1.710000E+02 F M S

Ir-195 1.041667E−01 F M S

Ir-195m 1.583333E−01 F M S

Pt-186 8.333330E−02 F F F

Pt-188 1.020000E+01 F F F

Pt-189 4.529167E−01 F F F

Pt-191 2.800000E+00 F F F

Pt-193 1.826250E+04 F F F

Pt-193m 4.330000E+00 F F F

Pt-195m 4.020000E+00 F F F

Pt-197 7.625000E−01 F F F

Pt-197m 6.555560E−02 F F F

Pt-199 2.138890E−02 F F F

Pt-200 5.208333E−01 F F F

Au-193 7.354167E−01 F M S

Au-194 1.645833E+00 F M S

Au-195 1.830000E+02 F M S

Au-198 2.696000E+00 F M S

Au-198m 2.300000E+00 F M S

Au-199 3.139000E+00 F M S

Au-200 3.361110E−02 F M S

Au-200m 7.791667E−01 F M S

Au-201 1.833330E−02 F M S

Hg-193 1.458333E−01 V F M

Hg-193m 4.625000E−01 V F M

Hg-194 9.496500E+04 V F M

Hg-195 4.125000E−01 V F M

Hg-195m 1.733333E+00 V F M

Hg-197 2.670833E+00 V F M

Hg-197m 9.916667E−01 V F M

Hg-199m 2.958330E−02 V F M

Hg-203 4.660000E+01 V F M

Tl-194 2.291670E−02 F F F

Tl-194m 2.277780E−02 F F F

Tl-195 4.833330E−02 F F F

Tl-197 1.183333E−01 F F F

Tl-198 2.208333E−01 F F F

Tl-198m 7.791670E−02 F F F

Tl-199 3.091667E−01 F F F

Tl-200 1.087500E+00 F F F

Tl-201 3.044000E+00 F F F

Tl-202 1.223000E+01 F F F

Tl-204 1.380280E+03 F F F

Pb-195m 1.097220E−02 F F F

Pb-198 1.000000E−01 F F F

Pb-199 6.250000E−02 F F F

Pb-200 8.958333E−01 F F F

Pb-201 3.916667E−01 F F F
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 28 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Pb-202 1.095750E+08 F F F

Pb-202m 1.508333E−01 F F F

Pb-203 2.168750E+00 F F F

Pb-205 5.223075E+09 F F F

Pb-209 1.355417E−01 F F F

Pb-210 8.145075E+03 F F F

Pb-211 2.506940E−02 F F F

Pb-212 4.433333E−01 F F F

Pb-214 1.861110E−02 F F F

Bi-200 2.527780E−02 F M M

Bi-201 7.500000E−02 F M M

Bi-202 6.958330E−02 F M M

Bi-203 4.900000E−01 F M M

Bi-205 1.531000E+01 F M M

Bi-206 6.243000E+00 F M M

Bi-207 1.387950E+04 F M M

Bi-210 5.012000E+00 F M M

Bi-210m 1.095750E+09 F M M

Bi-212 4.204860E−02 F M M

Bi-213 3.170140E−02 F M M

Bi-214 1.381940E−02 F M M

Po-203 2.548610E−02 F M M

Po-205 7.500000E−02 F M M

Po-207 2.430556E−01 F M M

Po-210 1.383800E+02 F M M

At-207 7.500000E−02 F M M

At-211 3.005833E−01 F M M

Fr-222 1.000000E−02 F F F

Fr-223 1.513890E−02 F F F

Ra-223 1.143400E+01 M M M

Ra-224 3.660000E+00 M M M

Ra-225 1.480000E+01 M M M

Ra-226 5.844000E+05 M M M

Ra-227 2.930560E−02 M M M

Ra-228 2.100188E+03 M M M

Ac-224 1.208333E−01 F M S

Ac-225 1.000000E+01 F M S

Ac-226 1.208333E+00 F M S

Ac-227 7.952588E+03 F M S

Ac-228 2.554167E−01 F M S

Th-226 2.145830E−02 M M S

Th-227 1.871800E+01 M M S

Th-228 6.987598E+02 M M S

Th-229 2.680935E+06 M M S

Th-230 2.812425E+07 M M S

Th-231 1.063333E+00 M M S

Th-232 5.131763E+12 M M S

Th-234 2.410000E+01 M M S

Pa-227 2.659720E−02 M M S

Pa-228 9.166667E−01 M M S
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 29 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Pa-230 1.740000E+01 M M S

Pa-231 1.196559E+07 M M S

Pa-232 1.310000E+00 M M S

Pa-233 2.700000E+01 M M S

Pa-234 2.791667E−01 M M S

U-230 2.080000E+01 F M S

U-231 4.200000E+00 F M S

U-232 2.629800E+04 F M S

U-233 5.789213E+07 F M S

U-234 8.930363E+07 F M S

U-235 2.570630E+11 F M S

U-236 8.552329E+09 F M S

U-237 6.750000E+00 F M S

U-238 1.631937E+12 F M S

U-239 1.634720E−02 F M S

U-240 5.875000E−01 F M S

Np-232 1.020830E−02 M M M

Np-233 2.513890E−02 M M M

Np-234 4.400000E+00 M M M

Np-235 3.961000E+02 M M M

Np-236 4.200375E+07 M M M

Np-236m 9.375000E−01 M M M

Np-237 7.816350E+08 M M M

Np-238 2.117000E+00 M M M

Np-239 2.355000E+00 M M M

Np-240 4.513890E−02 M M M

Pu-234 3.666667E−01 M M S

Pu-235 1.756940E−02 M M S

Pu-236 1.041328E+03 M M S

Pu-237 4.530000E+01 M M S

Pu-238 3.204703E+04 M M S

Pu-239 8.789741E+06 M M S

Pu-240 2.387639E+06 M M S

Pu-241 5.259600E+03 M M S

Pu-242 1.374436E+08 M M S

Pu-243 2.065000E−01 M M S

Pu-244 3.016965E+10 M M S

Pu-245 4.375000E−01 M M S

Pu-246 1.085000E+01 M M S

Am-237 5.069440E−02 M M M

Am-238 6.805560E−02 M M M

Am-239 4.958333E−01 M M M

Am-240 2.116667E+00 M M M

Am-241 1.578610E+05 M M M

Am-242 6.675000E−01 M M M

Am-242m 5.551800E+04 M M M

Am-243 2.695545E+06 M M M

Am-244 4.208333E−01 M M M

Am-244m 1.805560E−02 M M M

Am-245 8.541670E−02 M M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 30 of 33

ATTACHMENT A 

ALL NUCLIDES IN MARK-I1L TARGET ASSIGNED TO THREE SOLUBILITY CATEGORIES

(continued)

Nuclide Half-life (d) Soluble Moderate Insoluble

Am-246 2.708330E−02 M M M

Am-246m 1.736110E−02 M M M

Cm-238 1.000000E−01 M M M

Cm-240 2.700000E+01 M M M

Cm-241 3.280000E+01 M M M

Cm-242 1.628000E+02 M M M

Cm-243 1.040963E+04 M M M

Cm-244 6.614677E+03 M M M

Cm-245 3.104625E+06 M M M

Cm-246 1.727633E+06 M M M

Cm-247 5.697900E+09 M M M

Cm-248 1.238198E+08 M M M

Cm-249 4.454860E−02 M M M

Cm-250 2.520225E+06 M M M

Bk-245 4.940000E+00 M M M

Bk-246 1.830000E+00 M M M

Bk-247 5.040450E+05 M M M

Bk-249 3.200000E+02 M M M

Bk-250 1.342500E−01 M M M

Cf-244 1.347220E−02 M M M

Cf-246 1.487500E+00 M M M

Cf-248 3.335000E+02 M M M

Cf-249 1.280566E+05 M M M

Cf-250 4.777470E+03 M M M

Cf-251 3.279945E+05 M M M

Cf-252 9.635295E+02 M M M

Cf-253 1.781000E+01 M M M

Cf-254 6.050000E+01 M M M

Es-250m 8.750000E−02 M M M

Es-251 1.375000E+00 M M M

Es-253 2.047000E+01 M M M

Es-254 2.757000E+02 M M M

Es-254m 1.637500E+00 M M M

Fm-252 9.458333E−01 M M M

Fm-253 3.000000E+00 M M M

Fm-254 1.350000E−01 M M M

Fm-255 8.362500E−01 M M M

Fm-257 1.005000E+02 M M M

Md-257 2.166667E−01 M M M

Md-258 5.500000E+01 M M M
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 31 of 33

 

ATTACHMENT B 

TABLES FROM WHICH THE BAR PLOTS IN FIGURES 2-1 THROUGH 2-7 WERE 

CONSTRUCTED

LIST OF TABLES

TABLE TITLE PAGE

B-1 Dosimetrically significant nuclides in Mark-I1L ....................................................................... 32

B-2 Dosimetrically significant nuclides in beam stop..................................................................... 32

B-3 Dosimetrically significant nuclides in beam window................................................................ 32

B-4 Dosimetrically significant nuclides in Insert 1.......................................................................... 32

B-5 Dosimetrically significant nuclides in Insert 2.......................................................................... 32

B-6 Dosimetrically significant nuclides in Shielding 1.................................................................... 32

B-7 Dosimetrically significant nuclides in Shielding 2.................................................................... 33
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 32 of 33

ATTACHMENT B 

TABLES FROM WHICH THE BAR PLOTS IN FIGURES 2-1 THROUGH 2-7 WERE 

CONSTRUCTED (continued)

Table B-1. Dosimetrically significant nuclides in Mark-I1L. 

Nuclide Proportion of dosea

Gd-148 0.8367640

Cd-113m 0.0977961

Co-60 0.0376775

Hf-172 0.0218392

Other (132) 0.0059230

a. The proportion of the total DCF attributable to each radionuclide.

Table B-2. Dosimetrically significant nuclides in beam stop.

Nuclide Proportion of dosea

Co-60 0.8699270

Ni-63 0.0929931

Fe-55 0.0193571

Ti-44 0.0154296

Other (20) 0.0022930

a. The proportion of the total DCF attributable to each radionuclide.

Table B-3. Dosimetrically significant nuclides in beam window. 

Nuclide Proportion of dosea

Co-60 0.5537620

Fe-55 0.2043030

Ti-44 0.1970990

Na-22 0.0165377

H-3 0.0113393

Other (19) 0.0169600

a. The proportion of the total DCF attributable to each radionuclide.

Table B-4. Dosimetrically significant nuclides in Insert 1.

Nuclide Proportion of dosea

Co-60 0.8451750

Fe-55 0.1418230

Ti-44 0.0122323

Other (16) 0.0007693

a. The proportion of the total DCF attributable to each radionuclide.

Table B-5. Dosimetrically significant nuclides in Insert 2.

Nuclide Proportion of dosea

Co-60 0.758114

Fe-55 0.235100

Other (18) 0.006786

a. The proportion of the total DCF attributable to each radionuclide.

Table B-6. Dosimetrically significant nuclides in Shielding 1.

Nuclide Proportion of dosea

Co-60 0.729635

Fe-55 0.262729

Other (21) 0.007637

a. The proportion of the total DCF attributable to each radionuclide.
Document No. ORAUT-RPRT-0107 Revision No. 00 Effective Date: 09/15/2023 Page 33 of 33

ATTACHMENT B 

TABLES FROM WHICH THE BAR PLOTS IN FIGURES 2-1 THROUGH 2-7 WERE 

CONSTRUCTED (continued)

Table B-7. Dosimetrically significant nuclides in Shielding 2.

Nuclide Proportion of dosea

Co-60 0.864343

Fe-55 0.134063

Other (16) 0.001594

a. The proportion of the total DCF attributable to each radionuclide.