NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

MEMORANDUM

TO: INL Work Group 

FROM: SC&A, Inc.

DATE: July 14, 2016 

SUBJECT: Progress Report: SC&A’s Evaluation of Sr-90/Cs-137, FAP/Cs-137, and 

Actinides/Cs-137 Ratios Using ANL-W Measured Values in Relationship to 

Assigning Intakes

Executive Summary

In the National Institute for Occupational Safety and Health’s (NIOSH’s) SEC Petition 

Evaluation Report) – ANL-W Petition SEC-00224 of February 18, 2016 (NIOSH 2016), one of 

the major assumptions was that a bioassayed indicator radionuclide (strontium-90 [Sr-90] and/or 

cesium-137 [Cs-137]) can be used to assign dosimetric-significant fission activation product 

(FAP) and actinide (alpha emitter) intakes using the ratio method. This method requires that 

radionuclide ratios remain fairly constant for the various functions and locations, and over most 

of the operating history of the Argonne National Laboratory-West (ANL-W). One of the key 

cornerstones of the recommended ratio methodology is that the Sr-90/Cs-137 values be centered 

on unity (i.e., ratio values of 1.0). 

As SC&A outlined in a previous report concerning the Idaho National Laboratory (INL), 

SC&A’s Evaluation of Cs-137/Sr-90 Values and Actinides Using INL Waste Reports in 

Relationship to Assigning Intakes (SC&A 2016), SC&A found indications that the Sr-90/Cs-137, 

FAPs/Cs-137, and actinide/Cs-137 values from the INL data are, in many situations, 

significantly different than the ratio values recommended in ORAUT-OTIB-0054, Fission and 

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

Analyses (ORAUT 2015), and ORAUT-TKBS-0007-5, Idaho National Laboratory and Argonne 

National Laboratory – West – Occupational Internal Dose (ORAUT 2010), Tables 5-22 and 

5-23. Therefore, in view of this and ANL-W’s numerous types of reactors, experimental charter, 

and the various fuel handling methods, SC&A began a preliminary analysis of some of the 

available ANL-W air, liquid, solid, soil, and swipe data to obtain an indication of the validity of 

the ratio values recommended in ORAUT-OTIB-0054 and ORAUT-TKBS-0007-5, Tables 5-22 

and 5-23. 

SC&A searched the Site Research Database (SRBD), references listed in the National Institute 

for Occupational Safety and Health’s (NIOSH’s) evaluation report (ER) for ANL-W, NIOSH’s 

ANL-W ER references on the Advisory Board on Radiation and Worker Health (ABRWH) 

server and some NIOSH OCAS Claims Tracking System (NOCTS) claims for documents that 

could provide quantitative radionuclide data. During this search, SC&A located some ANL-W 

documents that contained quantitative Sr-90 and Cs-137 measurements performed on the same 

samples (some also contained FAP and actinide analyses in conjunction with the Cs-137 

analyses). These samples included air, soil, liquid and solid waste, swipes, reactor water, and 

particle collection. Several of these documents span a reasonable time period (1958–1993) and 

were from some of the major operational areas within ANL-W (e.g., Experimental Breeder 

Reactor-I (EBR-I), EBR-II, Boiling Water Reactor Experiment (BORAX), Hot Fuel 

Examination Facility (HFEF), and the ANL-W site in general). 
Memo – ANL-W FAP-Actinides to Cs Ratios 2 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Quantitative radionuclide data from these samples at the ANL-W facilities provide an indication 

of the potential ratio of the radionuclide intake exposures to workers and will help in determining 

if further investigation is needed. Therefore, these data were analyzed in detail to evaluate if 

there is a reasonably consistent relationship between the Sr-90/Cs-137 concentrations, and if 

these indicating radionuclides could be used to assign other radionuclide intakes, such as FAPs, 

for dose reconstruction (DR) purposes. In addition, quantitative actinide data in relationship to 

Cs-137 were analyzed when available.

Sr-90/Cs-137 

To date, SC&A has found that quantitative radionuclide data for ANL-W are not very plentiful. 

However, a total of 16 matched pairs of measured Sr-90 and Cs-137 activities were located and 

analyzed, spanning the period 1972–1989, for EBR-I, BORAX, and the ANL-W site in general.

Of these 16 matched pairs, 11 pairs (69%) contained Sr-90/Cs-137 values centered on unity, 

within a factor of 2 (i.e., Sr-90/Cs-137 = 0.5 to 2.0). The remaining Sr-90/Cs-137 values were 

outside this interval, with values ranging from 0.04 to 19. 

FAP/Cs-137 

A total of 14 matched pairs of measured Cs-137 and a FAP (cobalt-60 [Co-60], Cs-134, or 

cerium-144 [Ce-144]) activity were located and analyzed, spanning the period 1970–1995, for 

EBR-I, EBR-II, BORAX, and the ANL-W site in general. The measured FAP/Cs-137 values 

were compared to the FAP/Cs-137 values recommended in Table 7-3 of ORAUT-OTIB-0054 

(ORAUT 2015). A comparison ratio value centered on 1.0 would indicate agreement between 

the measured and recommended values; however, ratio values not centered on unity would 

indicate insufficient, or excessive, FAP intake assignments during DR. Of these 14 matched 

pairs, 2 pairs (14%) contained FAP/Cs-137 values centered on unity, within a factor of 2 (i.e., 

FAP/Cs-137 = 0.5 to 2.0). The remaining FAP/Cs-137 values were outside this interval, some 

ranging orders of magnitude away from unity. 

In addition, 98 matched pairs of measured Ce-144 and Cs-137 swipes and particle activity 

samples for the period 1972–1974 from the HFEF Air Cell and Argon Cell were located and 

analyzed. The measured Ce-144/Cs-137 values were compared to the Ce-144/Cs-137 values 

recommended in Table 7-3 of ORAUT-OTIB-0054 (ORAUT 2015), with one-year decay. Of 

these 98 matched pairs, 1 pair (1%) contained Ce-144/Cs-137 values centered on unity, within a 

factor of 2 (i.e., FAP/Cs-137 = 0.5 to 2.0). All the remaining Ce-144/Cs-137 values were less 

than 0.5, with the lowest being 0.004. 

Actinides/Cs-137 

A total of 17 matched pairs of measured Cs-137 and an actinide (americium-241 [Am-241], 

plutonium-238 [Pu-238], or Pu-239) activity during the period 1974–1993 were located and 

analyzed for EBR-I, BORAX, and the ANL-W site in general. The measured actinide/Cs-137 

values were compared to the actinide/Cs-137 values recommended in Table 5-23 of ORAUTTKBS-0007-5 (ORAUT 2010). Of these 17 matched pairs, 3 pairs (18%) contained 

actinide/Cs-137 values centered on unity, within a factor of 2 (i.e., actinide/Cs-137 = 0.5 to 2.0). 

The remaining actinide/Cs-137 values were outside this interval; ranging from 0.03 to 89. 
Memo – ANL-W FAP-Actinides to Cs Ratios 3 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Conclusions

These results indicate that while the ANL-W Sr-90/Cs-137 values were more centered around 

unity (69% of 16 pairs) than those for INL (33% of 251 pairs), the limited number of data points 

for ANL-W that have been located to date is not sufficient to provide for complete analysis for 

the time span and varied operations for the numerous facilities at ANL-W. Also, the FAP/Cs-137 

values and the actinide/Cs-137 values may not be sufficiently constant (or known) for assigning 

intakes, even in situations where it can be assumed that the FAP or actinide is tied to an 

indicating radionuclide, such as Cs-137. These preliminary results are indicative of a potential 

issue; however, only a very limited number of measured values have been located; additional 

quantitative data need to be located and analyzed to further evaluate the issue. 

Introduction and Background

NIOSH responded to the ANL-W SEC-00224 in an ER of February 18, 2016 (NIOSH 2016). In 

that ER, and also in the technical basis document (TBD) for ANL-W, ORAUT-TKBS-0007-5, 

NIOSH’s basis for assigning internal intakes/doses for most years and locations at the ANL-W 

(except those covered by NIOSH’s proposed Special Exposure Cohort [SEC], or claimants who

had specific radionuclide bioassays) relies on the important assumptions that (1) the 

Sr-90/Cs-137 values are approximately unity, (2) FAPs are directly tied by a known ratio to 

Sr-90 or Cs-137 (as per ORAUT-OTIB-0054), and (3) actinides are directly tied by a known 

ratio to Sr-90 or Cs-137 (as per Tables 5-22 and 5-23 of ORAUT-TKBS-0007-5). 

As SC&A outlined in a previous report concerning INL (SC&A 2016), SC&A found indications 

that the Sr-90/Cs-137, FAPs/Cs-137, and actinide/Cs-137 values from the INL data are, in many 

situations, significantly different than the ratio values recommended in ORAUT-OTIB-0054 and 

ORAUT-TKBS-0007-5, Tables 5-22 and 5-23. Therefore, in view of this and ANL-W’s 

numerous types of reactors, experimental charter, and the various fuel handling methods, SC&A 

began a preliminary analysis of some of the available ANL-W air, liquid, solid, soil, and swipe 

data to obtain an indication of the validity of the ratio values recommended in ORAUT-OTIB0054 and ORAUT-TKBS-0007-5, Tables 5-22 and 5-23. In this evaluation, relatively long-lived 

(half-life of approximately 1 year or more) radionuclides were selected for analyses, so that the 

relative ratios would not be significantly dependent upon variations in the time after production 

to time of exposure. 

SC&A searched the SRBD, references listed in NIOSH’s ER for ANL-W, NIOSH’s ANL-W ER 

references on the ABRWH server and some NOCTS claims for documents that could provide 

quantitative radionuclide data. During this search, SC&A located some ANL-W documents that 

contained quantitative Sr-90 and Cs-137 measurements performed on the same samples (some 

also contained FAP and actinide analyses in conjunction with the Cs-137 analyses). These 

samples included air, soil, liquid and solid waste, swipes, reactor water, and particle collection.

Several of these documents span a reasonable time period (1958–1993) and were from some of 

the major operational areas within ANL-W (e.g., EBR-I, EBR-II, BORAX, HFEF, and the 

ANL-W site in general). 

Quantitative radionuclide data from these samples at the ANL-W facilities provide an indication 

of the potential ratio of the radionuclide intake exposures to workers, and if further investigation 
Memo – ANL-W FAP-Actinides to Cs Ratios 4 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

is needed. Therefore, these data were analyzed in detail to evaluate if there is a reasonably 

consistent relationship between the Sr-90/Cs-137 concentrations, and if these indicating 

radionuclides could be used to assign other radionuclide intakes, such as FAPs, for DR purposes. 

In addition, quantitative actinide data in relationship to Cs-137 were analyzed when available.

The analyses in this report used Cs-137 as the main indicating radionuclide (i.e., xx/Cs-137 

ratios), because there were more matched pairs of data that contained Cs-137 results than Sr-90 

results.

Tables containing the source document SRDB reference numbers and the radionuclide data that 

were used in this evaluation are provided in Attachment A of this memo. The color of the 

symbols in the figures is correlated with the color of the numerical value of the data in the tables. 

Analyzes of these data are provided in the following sections. 

Sr-90/Cs-137 Values 

NIOSH’s ER and ORAUT-TKBS-0007-5 (ORAUT 2010) rely heavily on the use of ORAUTOTIB-0054 (ORAUT 2015) to assign FAP intakes using Sr-90 or Cs-137 as the indicating 

radionuclide for numerous other FAP radionuclides at ANL-W for most locations and time 

periods. An example of Table 7-3a from ORAUT-OTIB-0054 is provided here as Figure 1. As 

can be seen from this table, assignment of FAP intakes is dependent on the Sr-90/Cs-137 value 

being approximately 1.0. 

Figure 1. Table 7-3a. FAP-to-Sr-90 or -Cs-137 Ratios for ATR-1 (ORAUT-OTIB-0054) 

To date, SC&A has found that quantitative radionuclide data for ANL-W are not very plentiful. 

However, a total of 16 matched pairs of measured Sr-90 and Cs-137 activities were located and 

analyzed, spanning the period 1972–1989, for EBR-I, BORAX, and the ANL-W site in general.

Of these 16 matched pairs, 11 pairs (69%) contained Sr-90/Cs-137 values centered on unity, 

within a factor of 2 (i.e., Sr-90/Cs-137 = 0.5 to 2.0). The remaining Sr-90/Cs-137 values were 

outside this interval, with values ranging from 0.04 to 19. The results of this analysis are 

summarized in Table A-1 of Attachment A and illustrated here in Figure 2. 
Memo – ANL-W FAP-Actinides to Cs Ratios 5 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Figure 2. Sr-90/Cs-137 Values for 16 Data Pairs from ANL-W Documents

FAP/Cs-137 Values

A total of 14 matched pairs of measured Cs-137 and a FAP (Co-60, Cs-134, or Ce-144) activity 

were located and analyzed; spanning the period 1970–1995 for EBR-I, EBR-II, BORAX, and the 

ANL-W site in general. The measured FAP/Cs values were compared to the FAP/Cs-137 values 

recommended in Table 7-3 of ORAUT-OTIB-0054 (ORAUT 2015), with one-year decay, which 

would likely be representative of the time from production to worker exposure for these samples.

A comparison ratio value centered on 1.0 would indicate agreement between the measured and 

recommended values; however, ratio values not centered on unity would indicate insufficient, or 

excessive, FAP intake assignments during dose reconstruction. Of these 14 matched pairs, 

2 pairs (14%) contained FAP/Cs-137 values centered on unity, within a factor of 2 (i.e., 

FAP/Cs-137 = 0.5 to 2.0). The remaining FAP/Cs-137 values were outside this interval, some 

ranging orders of magnitude away from unity. The results of this analysis are summarized in 

Tables A-2, A-3, and A-4 of Attachment A and illustrated here in Figure 3. 

ANL-W, EBR-I, & BORAX 

Measured Sr-90/Cs-137 (OTIB-54 lists a ratio of ~1)

Air, Reactor Water, Soil, Liquid & Solid Waste 1955-1995

0.0

0.1

1.0

10.0

100.0

1955 1960 1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

Sr-90/Cs-137

Sr/Cs [<0.5] Sr/Cs [0.5 to 2.0] Sr/Cs [>2.0]
Memo – ANL-W FAP-Actinides to Cs Ratios 6 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Figure 3. FAP/Cs-137 Values for 14 Data Pairs from ANL-W Documents

In addition, 98 matched pairs of measured Ce-144 and Cs-137 swipes and particle activity 

samples for the period 1972–1974 from the HFEF Air Cell and Argon Cell were located and 

analyzed. The measured Ce-144/Cs-137 values were compared to the Ce-144/Cs-137 values 

recommended in Table 7-3 of ORAUT-OTIB-0054 (ORAUT 2015), with one-year decay. A 

comparison ratio value centered on 1.0 would indicate agreement between the measured and 

recommended values; however, ratio values not centered on unity would indicate insufficient, or 

excessive, Ce-144 intake assignments during dose reconstruction. Of these 98 matched pairs, 

1 pair (1%) contained Ce-144/Cs-137 values centered on unity, within a factor of 2 (i.e., 

FAP/Cs-137 = 0.5 to 2.0). All the remaining Ce-144/Cs-137 values were less than 0.5, with the 

lowest being 0.004. The results of this analysis are summarized in Table A-5 of Attachment A 

and illustrated here in Figure 4. 

ANL-W, EBR-I, EBR-II, & BORAX

 Measured FAP/Cs-137 Compared to OTIB-54 Ratios

Air, Smears, Liquid & Solid Waste 1965-1995

0.0

0.1

1.0

10.0

100.0

1,000.0

10,000.0

100,000.0

1965 1970 1975 1980 1985 1990 1995

Recorded Data Point

(Meas)/(OTIB-54) ratio

Co60/Cs137 [>2.0] Cs134/Cs137 [0.5 to 2.0] Ce144/Cs-137 [<0.5]
Memo – ANL-W FAP-Actinides to Cs Ratios 7 SC&A – July 14, 2016 

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the Privacy Act 5 USC §552a and has been cleared for distribution.

Figure 4. Ce-144/Cs-137 Values for 98 Data Pairs from ANL-W HFEF Documents

Actinides/Cs-137 Values

A total of 17 matched pairs of measured Cs-137 and an actinide (Am-241, Pu-238, or Pu-239) 

activity during the period 1974–1993 were located and analyzed for EBR-I, BORAX, and the 

ANL-W site in general. The measured actinide/Cs-137 values were compared to the 

actinide/Cs-137 values recommended in Table 5-23 of ORAUT-TKBS-0007-5 (ORAUT 2010). 

Table 5-23 is reproduced here as Figure 5. 

ANL-W HFEF Argon Cell & Air Cell

Measured Ce-144/Cs-137 Compared to OTIB-54 Ratio

Swipes and Particle Samples 1972-1974

0.00

0.01

0.10

1.00

10.00

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53

Recorded Data Point (98 total data pairs during 1972-1974)

(Meas)/(OTIB-54) ratio

Ar cell swipes_Ce144/Cs137 [0.5 to 2.0] Ar cell swipes_Ce144/Cs-137 [<0.5]

Ar cell particles_Ce144/Cs137 [<0.5] Air cell swipes_Ce144/Cs137 [<0.5]
Memo – ANL-W FAP-Actinides to Cs Ratios 8 SC&A – July 14, 2016 

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Figure 5. Table 5-23, Actinide-to-Cs-137 Ratios (ORAUT-TKBS-0007-5) 

A comparison ratio value centered on 1.0 would indicate agreement between the measured and 

recommended values; however, ratio values not centered on unity would indicate insufficient, or 

excessive, actinide intake assignments during dose reconstruction. Of these 17 matched pairs, 

3 pairs (18%) contained actinide/Cs-137 values centered on unity, within a factor of 2 (i.e., 

actinide/Cs-137 = 0.5 to 2.0). The remaining actinide/Cs-137 values were outside this interval, 

ranging from 0.03 to 89. The results of this analysis are summarized in Tables A-6, A-7, and A-8 

of Attachment A and illustrated here in Figure 6. 
Memo – ANL-W FAP-Actinides to Cs Ratios 9 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Figure 6. Actinide/Cs-137 Values for 17 Data Pairs from ANL-W Documents

Summary and Conclusions

This investigation indicates that from the limited measured data points analyzed to date:

• The ANL-W Sr-90/Cs-137 values were more centered around unity (69% of 16 pairs) 

than those for INL (33% of 251 pairs), but that the limited number of data points for 

ANL-W that have been located to date are not sufficient to provide for complete analysis 

for the time span and varied operations for the numerous facilities at ANL-W.

• The FAP/Cs-137 values (as required by ORAUT-OTIB-0054 for assigning FAP intakes) 

may not be sufficiently constant (or known) for assigning intakes, even in situations 

where it can be assumed that the FAP is tied to an indicating radionuclide, such as 

Cs-137. 

• The actinide/Cs-137 values (as required by ORAUT-TKBS-0007-5, Table 5-23, for 

assigning actinide intakes) may not be sufficiently constant (or known) for assigning 

actinide intakes, even in situations where it can be assumed that the actinide is tied to an 

indicating radionuclide, such as Cs-137. 

These preliminary results are indicative of a potential issue; however, only a very limited number 

of measured values have been located; additional quantitative radionuclide data need to be 

located and analyzed to further evaluate the issue.

ANL-W, EBR-I, & BORAX

Measured Actinide/Cs-137 Compared to Table 5-23 Ratio

Soil & Solid Waste 1970-1995

0.0

0.1

1.0

10.0

100.0

1970 1975 1980 1985 1990 1995

Recorded Data Point

(Meas)/(Table 5-23) ratio

Am241/Cs [0.5 to 2.0] Am241/Cs [>2.0] Pu238/Cs [<0.5]

Pu239/Cs [<0.5] Pu239/Cs [0.5 to 2.0] Pu239/Cs [>2.0]
Memo – ANL-W FAP-Actinides to Cs Ratios 10 SC&A – July 14, 2016 

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References

NIOSH 2016. SEC Petition Evaluation Report – ANL-W Petition SEC-00224 of February 18, 

2016, National Institute for Occupational Safety and Health, Division of Compensation Analysis 

and Support, Cincinnati, Ohio. February 18, 2016. 

ORAUT 2009. MS Excel workbook, INEL-Actinide Ratios, Revision 0, Oak Ridge Associated 

Universities Team, Oak Ridge Tennessee. December 18, 2009. [SRDB Ref. ID 77440] 

ORAUT 2010. Idaho National Laboratory and Argonne National Laboratory – West 

Occupational Internal Dose, ORAUT-TKBS-0007-5, Revision 03, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. March 2, 2010. 

ORAUT 2015. Fission and Activation Product Assignment for Internal Dose-Related Gross Beta 

and Gross Gamma Analyses, ORAUT-OTIB-0054, Revision 03, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. February 6, 2015.

SC&A 2016. SC&A’s Evaluation of Cs-137/Sr-90 Values and Actinides Using INL Waste 

Reports in Relationship to Assigning Intakes, SC&A, Inc., Vienna, Virginia, and Saliant, Inc., 

Jefferson, Maryland. June 24, 2016. 
Memo – ANL-W FAP-Actinides to Cs Ratios 11 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Attachment A: Documents and Data Used in Evaluation 

Table A-1. Summary of Data from SRBD Documents for Sr-90/Cs-137 Values

SRDB

Ref. ID PDF #

Time 

period Area

Type of 

sample

Measured 

Sr-90

T1/2=29y

activity

Measured 

Cs-137

T1/2=30y

activity Units

(Sr-90/

Cs-137)

140037 89 1973 ANL liq waste 5.80E-07 1.58E-05 uCi/ml 0.04

140039 118 1974 ANL solid waste 1.48E+02 7.876 Ci 18.78

140040 153 1975 ANL solid waste 3.98E+01 3.98E+01 Ci 1.00

118841 163 1978 ANL solid waste 8.84E+01 1.16E+02 Ci 0.76

87191 190 1985 ANL solid waste 1.84E+01 1.88E+01 Ci 0.98

87191 192 1985 ANL solid waste 4.4 3.4 Ci 1.29

136493 152 1993 ANL solid waste 1.188 6.30E-01 Ci 1.88

83153 9 1978 ANL-EBR-I soil 0.57 1.10 pCi/g 0.52

83153 9 1978 ANL-EBR-I soil 0.86 1.30 pCi/g 0.66

83153 9 1978 ANL-EBR-I soil 0.57 1.07 pCi/g 0.53

85427 7 1972 ANL-EBR-I air 2.00E-15 3.50E-15 uCi/ml 0.57

118841 163 1978 ANL solid waste 8.84E+01 1.16E+02 Ci 0.762

118841 165 1978 ANL stored waste 1.00E+02 1.95E+02 Ci 0.513

27049 16 1958 BORAX IV Rx water 420 1.10E+04 dpm/ml 0.038

27049 16 1958 BORAX IV Rx water 484 1.20E+04 dpm/ml 0.040

83007 33&34 1980 BORAX I soil 2.5 7.0 pCi/g 0.357

Table A-2. Summary of Data from SRBD Documents for Co-60/Cs-137 Values

SRDB

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Measured

Cs-137

activity Units

Measured

Co-60 

T1/2=5.3y 

activity

(Co-60/

Cs-137)

OTIB-54

(Co-60/

Cs-137)

ratio

Co-60/ 

Cs-137 

(Meas/ 

OTIB-54)

87585 18 1968 ANL-EBR-II liq waste 8.8 % act 25.5 2.90E+00 1.83E-04 15,835

118841 163 1978 ANL solid waste 1.16E+02 Ci 1.47E+03 1.27E+01 1.83E-04 69,437

118841 165 1978 ANL-Borax stored waste 1.95E+02 Ci 2.95E+02 1.51E+00 1.83E-04 8,271

83008 7 1989 ANL-Borax smears 4.59E-04 uCi/sample 1.25E-05 2.72E-02 1.83E-04 149

83008 8 1989 ANL-Borax smears 1.85E-05 uCi/sample 2.62E-06 1.42E-01 1.83E-04 774

83008 9 1989 ANL-Borax smears 6.33E-05 uCi/sample 6.86E-06 1.08E-01 1.83E-04 592

83008 10 1989 ANL-Borax smears 2.71E-04 uCi/sample 1.90E-05 7.00E-02 1.83E-04 382

83008 11 1989 ANL-Borax smears 4.34E-05 uCi/sample 4.95E-05 1.14E+00 1.83E-04 6,233

Table A-3. Summary of Data from SRBD Documents for Cs-134/Cs-137 Values

SRDB

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Measured

Cs-137

activity Units

Measured

Cs-134

T1/2=2.3y

activity

(Cs-134/

Cs-137)

OTIB54 (Cs134/

Cs-137)

ratio

Cs-134/ 

Cs-137 

(Meas/ 

OTIB-54)

118841 163 1978 ANL solid waste 1.16E+02 Ci 8.57E+01 7.39E-01 0.546 1.35

118841 165 1978 ANL-Borax stored waste 1.95E+02 Ci 5.32E+01 2.73E-01 0.546 0.50
Memo – ANL-W FAP-Actinides to Cs Ratios 12 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

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Table A-4. Summary of Data from SRBD Documents for Ce-144/Cs-137 Values 

SRDB

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Measured

Ce-144

activity Units

Measured

Ce-144

T1/2=282d

activity

(Ce-144/

Cs-137)

OTIB-54 

(Ce-144/ 

Cs-137) 

ratio

Ce-144/ 

Cs-137

(Meas/ 

OTIB-54)

87585 18 1968 ANL-EBR-II liq waste 8.8 % act 20.0 2.27E+00 12.3 0.18

85427 7 1972 ANL-EBR-I air 2.00E-15 uCi/ml 1.60E-14 4.57E+00 12.3 0.37

118841 163 1978 ANL solid waste 1.16E+02 Ci 8.64E+01 7.45E-01 12.3 0.06

118841 165 1978 ANL-Borax stored waste 1.95E+02 Ci 1.63E+02 8.34E-01 12.3 0.07

Table A-5. Summary of Data from SRBD Documents for HFEF Ce-144/Cs-137 Values 

SRDB 

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Recorded 

(Cs-137/ 

Ce-144)

(Ce-144/ 

Cs-137)

OTIB-54 

(Ce-144/ 

Cs-137) 

ratio

Ce-144/

Cs-137

(Meas/ 

OTIB-54)

80575 41 1974 HFEF Ar cell swipe 0.06 16.67 12.3 1.36

80575 40 1972 HFEF Ar cell swipe 2.00 0.50 12.3 0.04

80575 40 1972 HFEF Ar cell swipe 0.70 1.43 12.3 0.12

80575 40 1972 HFEF Ar cell swipe 0.90 1.11 12.3 0.09

80575 40 1972 HFEF Ar cell swipe 14.70 0.07 12.3 0.01

80575 40 1972 HFEF Ar cell swipe 5.30 0.19 12.3 0.02

80575 40 1972 HFEF Ar cell swipe 1.30 0.77 12.3 0.06

80575 40 1973 HFEF Ar cell swipe 3.40 0.29 12.3 0.02

80575 40 1973 HFEF Ar cell swipe 5.90 0.17 12.3 0.01

80575 40 1973 HFEF Ar cell swipe 8.20 0.12 12.3 0.01

80575 40 1973 HFEF Ar cell swipe 5.50 0.18 12.3 0.01

80575 40 1973 HFEF Ar cell swipe 2.80 0.36 12.3 0.03

80575 40 1973 HFEF Ar cell swipe 2.70 0.37 12.3 0.03

80575 40 1973 HFEF Ar cell swipe 3.10 0.32 12.3 0.03

80575 40 1973 HFEF Ar cell swipe 3.30 0.30 12.3 0.02

80575 40 1973 HFEF Ar cell swipe 1.50 0.67 12.3 0.05

80575 40 1973 HFEF Ar cell swipe 1.70 0.59 12.3 0.05

80575 40 1973 HFEF Ar cell swipe 2.40 0.42 12.3 0.03

80575 40 1973 HFEF Ar cell swipe 18.30 0.05 12.3 0.004

80575 40 1973 HFEF Ar cell swipe 1.00 1.00 12.3 0.08

80575 40 1973 HFEF Ar cell swipe 1.70 0.59 12.3 0.05

80575 40 1973 HFEF Ar cell swipe 1.20 0.83 12.3 0.07

80575 40 1973 HFEF Ar cell swipe 1.50 0.67 12.3 0.05

80575 40 1973 HFEF Ar cell swipe 1.30 0.77 12.3 0.06

80575 41 1973 HFEF Ar cell swipe 1.40 0.71 12.3 0.06

80575 41 1973 HFEF Ar cell swipe 5.20 0.19 12.3 0.02

80575 41 1973 HFEF Ar cell swipe 1.10 0.91 12.3 0.07

80575 41 1973 HFEF Ar cell swipe 1.10 0.91 12.3 0.07

80575 41 1973 HFEF Ar cell swipe 1.40 0.71 12.3 0.06

80575 41 1973 HFEF Ar cell swipe 0.90 1.11 12.3 0.09

80575 41 1973 HFEF Ar cell swipe 1.60 0.63 12.3 0.05

80575 41 1973 HFEF Ar cell swipe 0.70 1.43 12.3 0.12

80575 41 1973 HFEF Ar cell swipe 1.00 1.00 12.3 0.08

80575 41 1973 HFEF Ar cell swipe 1.20 0.83 12.3 0.07

80575 41 1973 HFEF Ar cell swipe 1.60 0.63 12.3 0.05
Memo – ANL-W FAP-Actinides to Cs Ratios 13 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

SRDB 

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Recorded 

(Cs-137/ 

Ce-144)

(Ce-144/ 

Cs-137)

OTIB-54 

(Ce-144/ 

Cs-137) 

ratio

Ce-144/

Cs-137

(Meas/ 

OTIB-54)

80575 41 1973 HFEF Ar cell swipe 1.00 1.00 12.3 0.08

80575 41 1973 HFEF Ar cell swipe 1.30 0.77 12.3 0.06

80575 41 1973 HFEF Ar cell swipe 3.20 0.31 12.3 0.03

80575 41 1973 HFEF Ar cell swipe 2.60 0.38 12.3 0.03

80575 41 1973 HFEF Ar cell swipe 5.90 0.17 12.3 0.01

80575 41 1973 HFEF Ar cell swipe 5.30 0.19 12.3 0.02

80575 41 1974 HFEF Ar cell swipe 1.60 0.63 12.3 0.05

80575 41 1974 HFEF Ar cell swipe 0.20 5.00 12.3 0.41

80575 41 1974 HFEF Ar cell swipe 1.10 0.91 12.3 0.07

80575 41 1974 HFEF Ar cell swipe 0.80 1.25 12.3 0.10

80575 41 1974 HFEF Ar cell swipe 2.60 0.38 12.3 0.03

80575 41 1974 HFEF Ar cell swipe 2.30 0.43 12.3 0.04

80575 41 1974 HFEF Ar cell swipe 0.80 1.25 12.3 0.10

80575 41 1974 HFEF Ar cell swipe 1.30 0.77 12.3 0.06

80575 41 1974 HFEF Ar cell swipe 3.20 0.31 12.3 0.03

80575 41 1974 HFEF Ar cell swipe 3.30 0.30 12.3 0.02

80575 41 1974 HFEF Ar cell swipe 1.50 0.67 12.3 0.05

80575 42 1973 HFEF Ar cell particle 2.00 0.50 12.3 0.04

80575 42 1973 HFEF Ar cell particle 2.00 0.50 12.3 0.04

80575 42 1973 HFEF Ar cell particle 1.20 0.83 12.3 0.07

80575 42 1973 HFEF Ar cell particle 5.30 0.19 12.3 0.02

80575 42 1973 HFEF Ar cell particle 0.30 3.33 12.3 0.27

80575 42 1973 HFEF Ar cell particle 1.00 1.00 12.3 0.08

80575 42 1973 HFEF Ar cell particle 0.30 3.33 12.3 0.27

80575 42 1973 HFEF Ar cell particle 0.50 2.00 12.3 0.16

80575 42 1973 HFEF Ar cell particle 6.80 0.15 12.3 0.01

80575 42 1973 HFEF Ar cell particle 2.70 0.37 12.3 0.03

80575 42 1973 HFEF Ar cell particle 0.40 2.50 12.3 0.20

80575 42 1973 HFEF Ar cell particle 2.50 0.40 12.3 0.03

80575 42 1973 HFEF Ar cell particle 2.90 0.34 12.3 0.03

80575 42 1973 HFEF Ar cell particle 7.80 0.13 12.3 0.01

80575 42 1973 HFEF Ar cell particle 1.10 0.91 12.3 0.07

80575 42 1973 HFEF Ar cell particle 2.50 0.40 12.3 0.03

80575 42 1973 HFEF Ar cell particle 8.00 0.13 12.3 0.01

80575 42 1973 HFEF Ar cell particle 3.30 0.30 12.3 0.02

80575 42 1973 HFEF Ar cell particle 0.90 1.11 12.3 0.09

80575 42 1973 HFEF Ar cell particle 13.80 0.07 12.3 0.01

80575 42 1973 HFEF Ar cell particle 10.30 0.10 12.3 0.01

80575 42 1973 HFEF Ar cell particle 2.70 0.37 12.3 0.03

80575 42 1972 HFEF Air cell swipe 2.30 0.43 12.3 0.04

80575 42 1972 HFEF Air cell swipe 0.70 1.43 12.3 0.12

80575 42 1972 HFEF Air cell swipe 1.50 0.67 12.3 0.05

80575 42 1972 HFEF Air cell swipe 1.80 0.56 12.3 0.05

80575 42 1972 HFEF Air cell swipe 0.60 1.67 12.3 0.14

80575 42 1973 HFEF Air cell swipe 2.60 0.38 12.3 0.03

80575 42 1973 HFEF Air cell swipe 0.60 1.67 12.3 0.14

80575 42 1973 HFEF Air cell swipe 3.30 0.30 12.3 0.02

80575 42 1973 HFEF Air cell swipe 0.30 3.33 12.3 0.27

80575 42 1973 HFEF Air cell swipe 1.90 0.53 12.3 0.04
Memo – ANL-W FAP-Actinides to Cs Ratios 14 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

SRDB 

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Recorded 

(Cs-137/ 

Ce-144)

(Ce-144/ 

Cs-137)

OTIB-54 

(Ce-144/ 

Cs-137) 

ratio

Ce-144/

Cs-137

(Meas/ 

OTIB-54)

80575 42 1973 HFEF Air cell swipe 2.00 0.50 12.3 0.04

80575 42 1973 HFEF Air cell swipe 3.10 0.32 12.3 0.03

80575 42 1973 HFEF Air cell swipe 1.90 0.53 12.3 0.04

80575 42 1973 HFEF Air cell swipe 2.00 0.50 12.3 0.04

80575 42 1973 HFEF Air cell swipe 1.30 0.77 12.3 0.06

80575 42 1973 HFEF Air cell swipe 0.80 1.25 12.3 0.10

80575 42 1973 HFEF Air cell swipe 0.50 2.00 12.3 0.16

80575 42 1973 HFEF Air cell swipe 1.30 0.77 12.3 0.06

80575 42 1973 HFEF Air cell swipe 1.00 1.00 12.3 0.08

80575 42 1973 HFEF Air cell swipe 0.90 1.11 12.3 0.09

80575 42 1973 HFEF Air cell swipe 0.70 1.43 12.3 0.12

80575 42 1973 HFEF Air cell swipe 0.80 1.25 12.3 0.10

80575 42 1973 HFEF Air cell swipe 1.20 0.83 12.3 0.07

80575 42 1973 HFEF Air cell swipe 0.80 1.25 12.3 0.10

Table A-6. Summary of Data from SRBD Documents for Am-241/Cs-137 Values 

SRDB 

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Measured

Cs-137

activity Units

Measured

Am-241

T1/2=433y

activity

(Am-241/

Cs-137)

OTIB-54

(Am-241/

Cs-137)

ratio

Am-241/

Cs-137

(Meas/ 

Table 5-23)

136493 152 1993 ANL solid waste 6.30E-01 Ci 1.63E-04 2.59E-04 1.30E-04 1.99

83153 9 1978 ANL-EBR-I soil 1.10 pCi/g 0.009 8.18E-03 1.30E-04 62.9

83153 9 1978 ANL-EBR-I soil 1.30 pCi/g 0.015 1.15E-02 1.30E-04 88.8

83153 9 1978 ANL-EBR-I soil 1.07 pCi/g 0.009 8.41E-03 1.30E-04 64.7

Table A-7. Summary of Data from SRBD Documents for Pu-238/Cs-137 Values 

SRDB 

Ref. ID

PDF 

#

Time 

period Area

Type of 

sample

Measured

Cs-137 

activity Units

Measured

Pu-238 

T1/2=88y 

activity

(Pu-238/ 

Cs-137)

OTIB-54 

(Pu-238/ 

Cs-137) 

ratio

Pu-238/

Cs-137

(Meas/ 

Table 5-23)

83153 9 1978 ANL-EBR-I soil 1.10 pCi/g 0.0017 1.55E-03 1.40E-02 0.11

83153 9 1978 ANL-EBR-I soil 1.30 pCi/g 0.0025 1.92E-03 1.40E-02 0.14

83153 9 1978 ANL-EBR-I soil 1.07 pCi/g 0.0041 3.83E-03 1.40E-02 0.27
Memo – ANL-W FAP-Actinides to Cs Ratios 15 SC&A – July 14, 2016 

NOTICE: This document has been reviewed to identify and redact any information that is protected by 

the Privacy Act 5 USC §552a and has been cleared for distribution.

Table A-8. Summary of Data from SRBD Documents for Pu-239/Cs-137 Values 

SRDB 

Ref. ID PDF #

Time 

period Area

Type of 

sample

Measured 

Cs-137 

activity Units

Measured 

Pu-239 

T1/2=2.4E4y 

activity

(Pu-239/ 

Cs-137)

OTIB-54 

(Pu-239/ 

Cs-137) 

ratio

Pu-239/

Cs-137

(Meas/ 

Table 5-23)

140039 118 1974 ANL solid waste 7.876 Ci 1.04E+00 1.32E-01 3.40E-03 38.84

140040 153 1975 ANL solid waste 3.98E+01 Ci 7.34E+00 1.84E-01 3.40E-03 54.17

87191 190 1985 ANL solid waste 1.88E+01 Ci 1.09E-02 5.79E-04 3.40E-03 0.17

87191 192 1985 ANL solid waste 3.4 Ci 1.61E-01 4.73E-02 3.40E-03 13.92

83153 9 1978 ANL-0EBR-I soil 1.10 pCi/g 0.022 2.00E-02 3.40E-03 5.88

83153 9 1978 ANL-EBR-I soil 1.30 pCi/g 0.019 1.46E-02 3.40E-03 4.30

83153 9 1978 ANL-EBR-I soil 1.07 pCi/g 0.015 1.40E-02 3.40E-03 4.12

118841 163 1978 ANL solid waste 1.16E+02 Ci 1.19E-02 1.02E-04 3.40E-03 0.03

118841 165 1978 ANL stored waste 1.95E+02 Ci 1.07E+00 5.49E-03 3.40E-03 1.61

83007 34&35 1980 BORAX I soil 7.0 pCi/g 0.021 3.00E-03 3.40E-03 0.88