ORAU Team

Dose Reconstruction Project for NIOSH

Technical Basis Document for the Los Alamos National 

Laboratory – Occupational Environmental Dose

Document Number:

ORAUT-TKBS-0010-4

Effective Date: 10/08/2004

Revision No.: 00

Controlled Copy No.: ______

Page 1 of 96

Subject Experts: Joel I. Cehn and Laura McDowell-Boyer 

Document Owner

Approval: Signature on File Date: 10/04/2004

Jack E. Buddenbaum, TBD Team Leader

Approval: Signature on File Date: 10/05/2004

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Date: 10/05/2004

Richard E. Toohey, Project Director

Approval: Signature on File Date: 10/08/2004

James W. Neton, Associate Director for Science

Supersedes:

None

TABLE OF CONTENTS 

Section Page

Record of Issue/Revisions ......................................................................................................................6

Acronyms and Abbreviations ..................................................................................................................7

4.1 Introduction ................................................................................................................................. 8

4.2 Internal Exposure from Onsite Atmospheric Radionuclide Concentrations ................................8

4.2.1 Onsite Releases to Air ..........................................................................................................8

4.2.1.1 Emissions Data ............................................................................................................9

4.2.1.1.1 Episodic Releases ...............................................................................................9

4.2.1.1.2 Bayo Canyon Releases .......................................................................................9

4.2.1.2 Radionuclides of Significance ....................................................................................11

4.2.1.3 Estimation of Air Concentrations ................................................................................12

4.2.1.4 Estimation of Occupational Intakes ............................................................................13

4.2.1.4.1 Pre-1971 Intakes ...............................................................................................14

4.2.1.4.2 Post-1970 Intakes .............................................................................................14

4.2.2 Resuspension .....................................................................................................................14

4.3 External Exposure .....................................................................................................................15

4.3.1 Ambient Radiation ...............................................................................................................15

4.3.2 Release of Noble Gases .....................................................................................................18

4.3.2.1 Omega Reactors TA-2 ...............................................................................................19

4.3.2.2 Los Alamos Neutron Science Center (TA-53)............................................................19

4.4 Uncertainty ................................................................................................................................22

References ...........................................................................................................................................23

Glossary................................................................................................................................................25
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Attachments 4A, 4B, 4C. 4D Tables of Source Emissions, Screening Results and Air 

Concentrations ....................................................................................................................52
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LIST OF TABLES 

Table Page

4-1 Estimated annual average intakes of 241Am, 3H, 239Pu, and 234U for TA-2 ..........................26

4-2 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 234U, MFP, and P/VAP 

for TA-3 ...............................................................................................................................27

4-3 Estimated annual average intakes of 241Am, 3H, Pu, and U for TA-5 ..................................28

4-4 Estimated annual average intakes of 241Am, 3H, 239Pu, and 234U for TA-6 ..........................29

4-5 Estimated annual intakes of 3H for TA-9 .............................................................................30

4-6 Estimated annual average intakes of 3H for TA-11 .............................................................30

4-7 Estimated annual average intakes of 241Am, 3H, Pu, and U for TA-15................................31

4-8 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, and 234U for TA-16..................32

4-9 Estimated annual average intakes of 234U for TA-18 ..........................................................32

4-10 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 234U, and MFP for TA21 ........................................................................................................................................33

4-11 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, and 234U for TA-33 .................34

4-12 Estimated annual average intakes of 241Am, 3H, 239Pu, 234U, MFP, and P/VAP for 

TA-35 ..................................................................................................................................35

4-13 Estimated annual average intakes of 241Am, 3H, 239Pu, and 234U for TA-36 ........................36

4-14 Estimated annual average intakes of 3H, 239Pu, and 234U for TA-39 ...................................36

4-15 Estimated annual average intakes of 3H, 239Pu, and 234U for TA-41 ...................................37

4-16 Estimated annual average intakes of 241Am, 3H, 239Pu, and 234U for TA-43 ........................38

4-17 Estimated annual average intakes of 234U for TA-46 ..........................................................39

4-18 Estimated annual average intakes of 241Am, 239Pu, 234U, MFP, and P/VAP for TA48 ........................................................................................................................................40

4-19 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, and 234U for TA-49 .................41

4-20 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 232Th, 234U, and MFP 

for TA-50 .............................................................................................................................42

4-21 Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 234U, and P/VAP for 

TA-53 ..................................................................................................................................43

4-22 Estimated annual average intakes of 241Am, 3H, 239Pu, and 234U for TA-54 ........................44

4-23 Estimated annual average and maximum intakes of 241Am, 3H, 239Pu, 232Th, and 

234U for TA-55......................................................................................................................45

4-24 Estimated air concentrations from resuspension ................................................................45

4-25 Area badge data - Annual TLD/film results .........................................................................46

4-26 Estimated annual deposition of 140La and doses from radioactive lanthanum 

experiments ........................................................................................................................47

4-27 Estimated average external doses from 41Ar released from TA-2 .......................................48

4-28 Estimated average external doses from gaseous/mixed activation products 

released from TA-53 ...........................................................................................................49

4-29 Estimated average external doses from gaseous/mixed activation products 

released from TA-21 and TA-72 .........................................................................................50

4-30 Estimated annual site wide maximum intakes of all radionuclides ......................................51

4A-1 Estimated source emissions from TA-1 ..............................................................................54

4A-2 Estimated source emissions from TA-2 ..............................................................................54

4A-3 Estimated source emissions from TA-3 ..............................................................................55

4A-4 Estimated source emissions from TA-9 ..............................................................................56

4A-4 Estimated source emissions from TA-10 ............................................................................56

4A-6 Estimated source emissions from TA-15 ............................................................................57

4A-7 Estimated source emissions from TA-16 ............................................................................58

4A-8 Estimated source emissions from TA-18 ............................................................................58
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4A-9 Estimated source emissions from TA-21 ............................................................................59

4A-10 Estimated source emissions from TA-33 ............................................................................60

4A-11 Estimated source emissions from TA-35 ............................................................................61

4A-12 Estimated source emissions from TA-36 ............................................................................62

4A-13 Estimated source emissions from TA-39 ............................................................................62

4A-14 Estimated source emissions from TA-41 ............................................................................63

4A-15 Estimated source emissions from TA-42 ............................................................................63

4A-16 Estimated source emissions from TA-43 ............................................................................64

4A-17 Estimated source emissions from TA-46 ............................................................................64

4A-18 Estimated source emissions from TA-48 ............................................................................65

4A-19 Estimated source emissions from TA-50 ............................................................................66

4A-20 Estimated source emissions from TA-53 ............................................................................67

4A-21 Estimated source emissions from TA-54 ............................................................................68

4A-22 Estimated source emissions from TA-55 ............................................................................69

4B-1 Data and results of screening analysis for potential contributors to inhalation 

dose ....................................................................................................................................71

4C-1 Estimated average air concentrations for 239Pu for TA-1 ....................................................72

4C-2 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-2 ...........................72

4C-3 Estimated average air concentrations for 241Am, 3H, 131I, Pu, 232Th, U, MFP, and 

P/VAP for TA-3 ...................................................................................................................73

4C-4 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-5 ...........................74

4C-5 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-6 ...........................75

4C-6 Estimated average air concentrations for 3H for TA-9 .........................................................76

4C-7 Estimated average air concentrations for U for TA-10........................................................77

4C-8 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-11 .........................77

4C-9 Estimated average air concentrations for 241Am. 3H, Pu, 232Th, and U for TA-15 ...............78

4C-10 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-16...................79

4C-11 Estimated average estimated air concentrations for U for TA-18 .......................................80

4C-12 Estimated average air concentrations for 241Am, 3H, 131I, Pu, U, and MFP for TA21 ........................................................................................................................................81

4C-13 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-33...................82

4C-14 Estimated average air concentrations for 241Am, 3H, Pu, U, MFP, and P/VAP for 

TA-35 ..................................................................................................................................83

4C-15 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-36 .........................84

4C-16 Estimated average air concentrations for 3H, Pu, and U for TA-39.....................................85

4C-17 Estimated average air concentrations for 3H, Pu, and U for TA-41.....................................86

4C-18 Estimated average air concentrations for Pu for TA-42 ......................................................87

4C-19 Estimated average air concentrations for 241Am , 3H, Pu, and U for TA-43 ........................87

4C-20 Estimated average air concentrations for U for TA-46........................................................88

4C-21 Estimated average air concentrations for 241Am , Pu, U, MFP, and P/VAP for TA48 ........................................................................................................................................89

4C-22 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-49...................90

4C-23 Estimated average air concentrations for 241Am, 3H, 131I, Pu, 232Th, U, and MFP 

for TA-50 .............................................................................................................................91

4C-24 Estimated average air concentrations for 241Am, 3H, 131I, Pu, U, and P/VAP for 

TA-53 ..................................................................................................................................92

4C-25 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-54 .........................93

4C-26 Estimated average air concentrations for 241Am, 3H, Pu, 232Th, and U for TA-55 ...............94

4D-1 Estimated average annual air concentrations of 41Ar for TA-2 ............................................95

4D-2 Estimated average annual air concentrations of gaseous/mixed activation 

products for TA-53, TA-21, and TA-72................................................................................96
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LIST OF FIGURES 

Table Page

4-1 Offsite, perimeter, and onsite LANL AIRNET locations ...............................................................10

4-2 Offsite, perimeter, and onsite LANL TLD locations ......................................................................17

4-3 Average wind rose for five LANL meteorological stations ............................................................21
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 RECORD OF ISSUE/REVISIONS 

ISSUE 

AUTHORIZATION 

DATE

EFFECTIVE 

DATE

REV. 

NO. DESCRIPTION

Draft 04/20/2004 00-A New technical basis document for the Los Alamos 

National Laboratory – Occupational 

Environmental Dose. Initiated by Jack E. 

Buddenbaum.

Draft 08/10/2004 00-B Incorporates internal and NIOSH review 

comments. Initiated by Jack E. Buddenbaum.

Draft 09/15/2004 00-C Incorporates additional internal and NIOSH review 

comments. Initiated by Jack E. Buddenbaum.

Draft 09/29/2004 00-D Incorporated additional NIOSH review comments. 

Initiated by Jack E. Buddenbaum.

10/08/2004 10/08/2004 00 First approved issue. Initiated by Jack E. 

Buddenbaum.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 7 of 96

ACRONYMS AND ABBREVIATIONS 

avg average 

Bq Becquerel 

Ci curie 

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000 

hr hour

km kilometer 

LANL Los Alamos National Laboratory 

LANSCE Los Alamos Neutron Science Center 

LASL Los Alamos Scientific Laboratory 

m meter 

max maximum 

MFP mixed fission products 

mrem millirem 

NIOSH National Institute for Occupational Safety and Health 

P/VAP particulate and vapor activation products 

pCi picocurie 

s second 

SPD site profile document 

Sv sievert 

TA technical area 

TBD technical basis document 

TLD thermoluminescent dosimeter 

U.S.C. United States Code 

yr year 

μCi microcurie 
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4.1 INTRODUCTION 

Occupational environmental exposure refers to exposures received by workers outside facilities at Los 

Alamos National Laboratory (LANL) from elevated ambient radiation, from facility effluents to the 

environment, and from resuspension of radionuclides in soils. Effluents can result in internal and 

external exposures by inhalation of airborne radionuclides and by submersion in an effluent, 

respectively. This technical basis document (TBD) provides estimated annual intakes for inhalation 

exposure and estimated doses as a result of submersion and ambient exposure at LANL. 

As discussed in Part 2 of the LANL Site Profile Document (SPD, ORAU pending), operations at Los 

Alamos have occurred in land divisions called technical areas (TAs). Table 2-1 of Part 2 lists each 

designated TA with information on the types of radionuclides present at some time during operations 

there. Activities that have occurred at LANL since operations began in 1943 have been highly 

variable on the site and over time. This TBD addresses occupational environmental exposure by 

considering available source term information that has been compiled for some of the TAs, as well as 

results of published environmental measurements for a larger number of TAs. 

This analysis recognized that effluents from a particular LANL TA would have the greatest impact on 

workers in that TA, but that such effluents could affect workers present in nearby TAs. A 

comprehensive site-wide atmospheric model for predicting onsite worker exposures resulting from the 

highly variable releases of radionuclides to the air would be useful to evaluating these impacts, but 

LANL has not developed such a model. This TBD relies to a great extent on environmental 

measurements (i.e., air monitoring data) in estimating worker exposures, and to a lesser extent on 

source term emission estimates. Environmental measurements do not distinguish the source of 

emissions and, therefore, will reflect air concentrations from nearby as well as more distant sources. 

The emissions estimates are useful in filling in some gaps in measurement data, and are critical to 

estimating exposures before the start of comprehensive and routine measurement data reports. 

TBDs and SPDs are general working documents that provide guidance concerning the preparation of 

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist the National Institute for Occupational Safety and Health (NIOSH) in the completion of the 

individual work required for each dose reconstruction. 

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act of 2000 [EEOICPA; 42 U.S.C. § 7384l (5) and (12)]. 

4.2 INTERNAL EXPOSURE FROM ONSITE ATMOSPHERIC RADIONUCLIDE 

CONCENTRATIONS 

4.2.1 Onsite Releases to Air

In Part 2 of the LANL SPD, Table 2-1 lists LANL TAs and potential sources of radioactive materials 

that are or were present at some time at each TA. Enriched and depleted uranium, as well as 

plutonium isotopes, are commonly listed sources. Due to the many different types of applied research 

conducted at LANL, Table 2-1 also lists tritium, noble gases, fission and activation products. 

LANL has reported effluents for many of the TAs from 1971 to 1995. In recent years, the reporting of 

air emissions has been by stack or vent. It is not possible to ascertain at this point how 
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comprehensive the reporting of effluents is. Estimates of emissions from the Omega Reactors (TA-2), 

for example, have not been obtained. Furthermore, LANL has not assessed the exact location of 

releases in relation to potential receptors in a TA. 

An ambient, air-monitoring program at LANL began as early as 1958 with a single station on the roof 

of the Administration Building in TA-3. In the late 1960s and early 1970s, a network of about 25 

stations was put into operation. At present, about 60 stations conduct continuous air sampling. About 

20 of the presently operational stations are on the site, with the remainder being offsite or perimeter 

stations. Figure 4-1 shows the location of active on- and off-site monitoring stations. Historical results 

of the AIRNET monitoring network through the year 2000 are available on the LANL website (web 

address http://www.lanl.gov/orgs/rres/maq/AirConc_AllData.htm#LOS), and annual environmental 

surveillance reports summarize yearly results. However, many TAs have unreported results and data 

are missing for some radionuclides and some years, or there have not been data to report due to 

changing conditions at LANL over time. Unless it is provided in the claimnant files, locations of the air 

monitoring stations in relation to a specific worker’s location(s) in a TA are not well known. 

Due to the lack of comprehensiveness of both effluent and air monitoring data, the approach to 

estimating worker intakes of radionuclides from air due to emissions from LANL’s TAs relied on a 

combination of the effluent and air monitoring data in this TBD. Because air monitoring data in a TA 

include concentrations due to effluents from that TA and resuspension of previously deposited 

radionuclides and effluents from nearby TAs, this analysis preferred these data in estimating air 

concentrations and ultimately worker intakes. The analysis used emissions data in filling some of the 

acknowledged gaps in monitoring data. 

4.2.1.1 Emissions Data 

Tables 4A-1 through 4A-22 in Attachment 4A to this TBD list emissions data. The tables list source 

emissions data by year and TA. If effluents were reported by stack or building vent (recent years), the 

tables sum effluents from the stacks and vents in each TA. For earlier years (1945 to 1971), the 

effluent releases reported in this document rely on data from the Center for Disease Control and 

Prevention’s Los Alamos Historical Document Retrieval and Assessment project (ENSR 2002), 

including unpublished data.

4.2.1.1.1 Episodic Releases 

LANL reported accidental releases of tritium and plutonium in the 1970s. Before that time, LANL 

noted some accidental releases (for example, a fire at TA-21 in July 1957), but accurate release 

estimates were not available (ENSR 2002). There were two tritium releases from TA-3 and one from 

TA-33. There was also a plutonium release from TA-21 in October 1970 (ENSR 2002). The 

emissions estimates (Tables 4A-1 through 4A-22 in Attachment 4A) include these and other episodic 

releases for which data were available along with routine stack releases for those years. The intake 

estimates are the same whether based on an assumed release period of one year or if releases 

occurred over some fraction of one year. 

4.2.1.1.2 Bayo Canyon Releases 

Experiments conducted in TA-10, Bayo Canyon, involved detonation of explosives around radioactive 

materials. These detonations dispersed materials, principally 140La, to the atmosphere and could 

have caused exposure to LANL employees. The dominant dose pathway would have been exposure 

to gamma radiation from 140La deposited on the ground. Internal exposure to 140La via inhalation was 

insignificant based on the screening analysis (Section 4.2.1.2). 
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Figure 4-1. Offsite, perimeter, and onsite LANL AIRNET locations (from LANL 2002, p. 167). 
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4.2.1.2 Radionuclides of Significance 

Before describing how this analysis estimated air concentrations in the TAs from emissions and 

monitoring data, it is important to focus the analysis on radionuclides potentially significant to dose. 

The basis for selection of radionuclides for estimating air concentrations was screening calculations to 

estimate which radionuclides listed as effluents were unlikely to contribute more than one millirem to a 

worker’s effective 50-year committed dose during one year or more than 10 mrem to the organ with 

the highest 50-year committed dose factor. Because the assumptions in screening overestimate 

potential exposures, it is believed these criteria will correctly eliminate insignificant radionuclides from 

further concern.

The screening analysis (see Table 4B-1 of Attachment 4B) evaluated the potential inhalation dose 

associated with the maximum annual reported emission of each radionuclide in the data in Tables 4A1 through 4A-22. This analysis calculated inhalation dose for each radionuclide by estimating 

maximum air concentrations using a screening-level dispersion model (NCRP 1996). An annual 

inhalation rate of 3,400 m3/yr was assumed, corresponding to continuous moderate activity (1.7 m3/hr) 

over a 2,000-hr workyear. The maximum effective and organ dose factors for each radionuclide are 

from International Commission on Radiological Protection (ICRP) Publication 68 (ICRP 2001, from the 

CD1 compilation). 

The NCRP (1996) screening model adopted for these calculations is a simple dispersion model that 

accounts for potential increases in exposure due to building wake effects for close-in receptors (i.e., 

those less than 100 m from the source location). A calculated generic dispersion factor represents 

the ratio of air concentration (χ) to emission rate (Q) for any radionuclide: 

χ/Q = f/( u h k) s/m3 Eq. 4-1 

where: 

χ = concentration at receptor (Ci/m3) 

Q = stack or building vent release rate (Ci/s) 

f = wind frequency 

u = wind speed (m/s) 

h = height of effluent release (m) 

k = constant (m) 

Values used for the independent factors f and k correspond to defaults provided in NCRP (1996), 

such that f is assumed equal to 0.25 (the maximum frequency for any compass point), and k is 1 m. 

The calculation assumed site-specific values for u (2.2 m/s, LANL average for 2002 and 2003) and h 

(10 m, average LANL building height). The assumption that the building height was equivalent to the 

effluent release height was because releases were generally from small stacks or vents on the roofs. 

The calculated dispersion factor was 0.0036 s/m3. 

If the results of these maximum dose calculations indicated annual 50-year committed doses less 

than 10-5 Sv (1 millirem), this analysis assumed that the radionuclide was insignificant in comparison 

to other potential contributors to dose. The analysis indicated that the relatively significant 

radionuclides for which intakes should be evaluated were 3H, 131I, 232Th, 234U, 238U, 238Pu, and 239Pu 

and the groups of radionuclides specified as mixed fission products (MFP) and particulate and vapor 

activation products (P/VAP). Although there were indications that 241Am was at concentrations below 

concern based on the available effluent information, this radionuclide was included with the others 

due to the concern that emissions might have been under-reported. Americium-241 is often emitted 
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in certain plutonium operations at a fairly significant level in relation to plutonium isotopes, yet many of 

the early years in which plutonium appeared to be emitted in significant amounts did not show any 

241Am emissions, which is an issue that needs further consideration. 

4.2.1.3 Estimation of Air Concentrations 

Air monitoring data, when available, formed the basis for estimates of air concentrations at each TA. 

For some areas, especially TA-21 and TA-54, more than one monitoring station was active during 

many years. In this case, the analysis averaged concentrations over all stations in the TA. For years 

and locations when monitoring data were not available, the analysis based an estimate on the 

relationship between source emission rate and air concentration for years when data were available. 

Air concentration data from before 1970 were not available for this analysis. For some TAs, air 

concentration data were not available for any year or for many of the years since 1970. Therefore, a 

method had to be devised to provide reasonable estimates of air concentrations for those years and 

TAs. For other instances, LANL reportedly discontinued analysis in some years for selected 

radionuclides that were deemed insignificant. 

For TA-3 and TA-21, both ambient air-monitoring data and release estimates for plutonium were 

available for several years of interest. Based on the relationship between plutonium air 

concentrations and releases for these TAs, a ratioing method was developed for estimating 

concentrations in other TAs where effluent estimates are available, but ambient air-monitoring data 

are absent. This method involved calculating the average ratio of plutonium air concentration to the 

estimated emission rate over all years for which both quantities were available. For TA-3, this 

average ratio (representing 14 years of data) was calculated to be 2.2 × 10-12 pCi/m3 per pCi/yr 

released. The maximum ratio calculated for that period was 2.9 × 10-11 pCi/m3 per pCi/yr released. A 

regression analysis gave a correlation coefficient (r) of 0.93, indicating a strong correlation between 

source emission rate and measured air concentrations for TA-3. For TA-21, this average ratio 

(representing 25 years of data) was also calculated to be 2.2 × 10-12 pCi/m3 per pCi/yr released. The 

maximum ratio for TA-21 was 1.4 × 10-11 pCi/m3 per pCi/yr released. A regression analysis of the 

TA-21 data gave a correlation coefficient (r) of 0.65 for the TA-21 ratios, indicating a moderate 

correlation. 

While this ratioing method requires the assumption that dispersion at all TAs is similar to that in TA-21 

and TA-3, that same assumption would be required of a simplistic model such as the one used for 

screening. Therefore, the ratioing method provides a reasonable estimate of average air 

concentrations at the LANL TAs for years in which monitoring results were not available. Because the 

average ratio tends to reflect the strong influence of one or two high ratios during the periods 

represented, this method provides a reasonable estimation of concentrations that would result in a 

value more claimant-favorable than a more in-depth modeling effort might produce. 

This ratio of plutonium air concentration to plutonium source emission rate, with units of years per 

cubic meter, was used to estimate air concentrations of all radionuclides at TAs for years in which 

ambient monitoring data were not available. The reason for not developing separate ratios for other 

radionuclides is that monitoring data tended to be more limited for most other radionuclides (with the 

exception of 3H). The justification for applying the plutonium ratios to other radionuclides was in the 

ratios calculated for other radionuclides when monitoring data were available. For 3H, the average of 

88 calculated ratios of measured air concentration to source emission rate was 1.7 × 10-12 yr/m3, with 

a maximum ratio of 3.8 × 10-11 yr/m3. For uranium, the average of 13 calculated ratios of measured 

air concentration to source emission rate was 2.3 × 10-12 yr/m3, with a maximum ratio of 1.9 × 10-11

yr/m3. The ratios for 3H and uranium, are very similar to those calculated for plutonium; therefore, the 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 13 of 96

plutonium values can reasonably be applied for estimating air concentrations for all radionuclides of 

significance. 

Tables 4C-1 to 4C-26 in Attachment 4C list estimated average air concentrations for selected TAs. 

The selected TAs correspond to those for which either monitoring data were available or source 

emissions were listed in Tables 4A-1 through 4A-22. To summarize, when monitoring data were 

available, average air concentrations represent annual measured results from AIRNET monitoring 

stations (LANL 2003). In the absence of monitoring data, the tables list estimated air concentrations 

that correspond to the ratioing method described above, using the ratios developed for plutonium. 

Footnotes to the tables indicate when the ratioing method was applied. 

In years prior to 1992, the monitoring data did not report concentrations of uranium in an isotopespecific manner. That is, the data reported concentrations as mass of uranium element per unit 

volume. In this case, the analysis made an assumption regarding the isotopic makeup of the uranium 

to convert to units of radioactivity. Assuming the mass concentration of uranium corresponds to the 

isotopic makeup of enriched uranium, which exhibits a higher specific activity than depleted or natural 

uranium due largely to the increase in the amount of 234U present (DOE 2001), the activity 

concentration of uranium was maximized. Assuming an isotopic ratio, in atom percent, of 

0.02%:2.96%:97.02% for 234U:235U:238U, the specific activity of enriched uranium (activity of uranium 

per mass) is 1.55 × 10-6 Ci/g. Using this specific activity to convert uranium mass concentration to 

activity concentration does not in itself assign an isotopic ratio to the uranium. However, once this 

conversion is made, the approach is to assume all uranium activity is 234U, because the dose factor for 

234U is slightly higher than those for 235U and 238U. Thus, Tables 4C-1 through 4C-26 report all 

uranium activity as 234U.

The air monitoring data listed concentrations of plutonium isotopes separately for 238Pu and 239Pu. 

Rather than track the concentrations separately, there was a decision to add activities for both 

isotopes and report them as 239Pu, which has a slightly higher dose coefficient. Thus, Tables 4C-1 

through 4C-26 report all plutonium as 239Pu.

Tables 4C-1 through 4C-26 sometimes list the categories MFP and P/VAP, corresponding 

respectively to mixed fission products and particulate/vapor activation products. These are not 

measured categories, but are present only when emissions data specified these groupings. The table 

below lists information on the constituents of these groupings. For simplicity, the analysis selected 

the constituent with the highest dose factor as the radionuclide representing these groupings, as listed 

below. 

Isotope grouping Isotopes

Isotope with maximum 

inhalation dose factora

MFP (mixed fission products) Predominantly Sr-90, Cs-137 Sr-90

P/VAP (particulate and vapor 

activation products)b

As-73, As-74, Br-76, B.-77r, Br-82, Ga-68, 

Ge-68, Hg-193, Hg-195m, Hg-197, Se-75

Ge-68 (class W)

a. Based on Federal Guidance Report No. 11 dose factors (Eckerman, Wolbarst, and Richardson, 1988). 

b. Based on LANL (2000). 

4.2.1.4 Estimation of Occupational Intakes 

The following discussion addresses estimation of two different sets of occupational intakes: the pre1971 intakes, when air monitoring data are not available in a consistent format (i.e., preannual 

environmental reports), and post-1970, when monitoring data became more consistently available. 
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4.2.1.4.1 Pre-1971 Intakes

Prior to 1971, air monitoring data for most TAs were not available, and estimates of occupational 

intakes must rely on emissions data provided by LANL. The emissions data listed in Tables 4A-1 

through 4A-22 of Attachment 4A indicate several years in which potentially significant releases, and 

thus intakes, might have occurred prior to 1971. In particular, early plutonium releases at TA-1 are 

high in relation to those in other years, and there are two years of very high 232Th releases (TA-15, 

1967-1968). The fact of these apparently high releases surrounded by years of either zero releases, 

or at least missing emissions information, suggests that more investigation into the accuracy of the 

reported releases and completeness of the emissions data is necessary before intakes during the pre1971 years can be addressed adequately. Therefore, estimated worker intakes in this revision of the 

TBD are restricted to post-1970 years. Efforts are currently in progress for developing pre-1971 

intakes that can be presented in a future revision of this TBD. 

4.2.1.4.2 Post-1970 Intakes

Using the average air concentrations from Tables 4C-1 to 4C-26 of Attachment 4C, this analysis 

estimated annual inhalation intakes in Bq/yr for each radionuclide and TA in the years after 1970 by 

assuming a breathing rate of 2,400 m3/yr, based on an occupancy of 2,000 hr/yr. Tables 4-1 to 4-23 

list the annual intakes for each TA by year. Table 4-30 lists site-wide maximum intakes, representing 

the yearly maximum of all averages across the LANL, for each radionuclide. If worker location during 

the period of employment is not accurately known, dose reconstructors can use the sitewide 

maximum to estimate intake for the years of interest. 

Even from the post-1970 monitoring and emissions data, intake values for all radionuclides for every 

year are not available for many of the TAs. In cases where only a few years of data were missing for 

a given radionuclide, but the trend indicated that operations had probably not changed, this analysis 

made an estimate based on data in other years. The footnotes of Tables 4-1 through 4-23 indicate 

the bases for this type of estimates. If there was no clearly established trend, such estimates could 

not be made. Some of the gaps might exist because previous measurements indicated further yearly 

monitoring for a particular radionuclide was not warranted based on previous low-level measurements 

or estimates. Further, some TAs probably were not in operation at the time of the data gap. Until 

further research provides explanations for these gaps in knowledge, there can be no recommendation 

other than those provided in the tables. 

Section 4.2.1.3 describes specific representative isotopes for the MFP and P/VAP groupings, which 

are listed in the footnotes of tables containing these designations. To calculate doses associated with 

these groupings, dose reconstructors should use the dose factor for the representative radionuclide 

specified. 

Information on solubility and particle sizes was not available for the radionuclides listed in Tables 4-1 

to 4-23. Therefore, reconstructions should assume that all activity intakes in Tables 4-1 to 4-23 are 

respirable and should make selections of solubility designations to maximize calculated dose to the 

organ of interest in the absence of relevant solubility data. 

4.2.2 Resuspension

Resuspension of radionuclides from contaminated soil was and is a potential source of internal dose 

to workers at LANL since the beginning of operations. A work area in which radionuclide emissions 

took place is a potential area of exposure to resuspended radionuclides deposited on the soil. The 

radionuclide emissions listed in Tables 4A-1 through 4A-22 do not include contributions from 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 15 of 96

resuspended soil. For recently contaminated soil, resuspension is generally more important than for 

soil with older contamination because erosion and downward migration of radionuclides from the 

upper soil layers diminish the source term over time. In Section 4.2.1, measured concentrations of 

radionuclides are the basis for the estimates of intake in the listed TAs; these estimates include 

resuspended radionuclides at those TAs. 

A more comprehensive consideration of resuspension is an area of ongoing work for this TBD, and is 

not complete at this time. There are probably areas susceptible to resuspension that the air 

monitoring network that exists today does not represent adequately. The following discussion 

provides details that are important to this ongoing effort. 

In its early years of operation, LANL discharged liquid effluents from TA-1, TA-21, and TA-50 

(formerly TA-35 and TA-45) to Acid/Pueblo, Los Alamos, and Mortandad Canyons. These canyon 

areas became contaminated with radionuclides. Due to the extent of soil contamination, these areas 

pose the greatest potential for significant historical intake from resuspension, particularly if recently 

contaminated soil was exposed to wind erosion or excavation activities. In addition, experiments with 

radioactive lanthanum in Bayo Canyon (TA-10) led to contamination of soil at that work area. The 

canyon areas are presently not part of work areas in any TA. LANL had decommissioned the TA-10 

worksite by 1963, at which time it had cleaned up surface debris and excavated contaminated waste 

disposal facilities (LASL 1979). With the exception of TA-10, TA-21, and TA-50, TAs at LANL 

received minor contamination, if any (Kennedy and Purtymun 1971a). Nevertheless, if workers spent 

significant time in these canyons in areas where air monitoring was not conducted, dose 

reconstructions should consider intakes and exposures from resuspension. 

LANL has investigated resuspension in Acid, Pueblo, and Bayo Canyons (Ferenbaugh et al. 1982; 

LASL 1979). Table 4-24 lists estimated air concentrations of selected radionuclides in the canyons for 

conditions during the 1970s. For Mortandad and Los Alamos Canyons, information on soil 

contamination levels is available for estimating resuspension (Purtymun et al. 1980); this study 

indicated that plutonium isotopes, 137Cs, and 90Sr were found in soil during the 1970s at levels in 

excess of those expected due to fallout. Estimates of air concentrations require the application of a 

resuspension factor to the measured levels. Assuming a resuspension factor of 1 × 10-9/m (LASL 

1979; Kennedy and Purtymun 1971b; Purtymun et al. 1980), Table 4-24 lists estimated air 

concentrations for these areas. Additional work should focus on developing a historical air 

concentration due to resuspension, taking into account that a constant resuspension factor over time 

is unlikely to be appropriate. 

4.3 EXTERNAL EXPOSURE 

4.3.1 Ambient Radiation

Thirty-plus years of environmental monitoring reports (for example, LASL 1959, 1960) contain 

measured ambient gamma radiation levels. Figure 4-2 shows the network of TLDs currently in use at 

LANL for this purpose. Table 4-25 lists data for TA-3, TA-18, TA-53, and TA-54. TA-36 reported 

elevated exposures from experiments at TA-18 for several years. All of these areas recorded gamma 

doses above natural background (terrestrial and cosmic) radiation. Results are cumulative mrem/year 

based on 8760 hours. A conversion factor is provided with Table 4-25 to convert these values to a 

2080 hr-based annual dose. It is noted that TLD results demonstrate the gamma-shine influence on 

other monitoring stations from TA-18’s critical assembly experiments. LANL environmental TLD data 

is represented by a log-normal distribution. Site-wide maximum and geometric mean values are also 

presented and are based on results from these four TAs. LANL annual reports also present a site 
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background dose and are presented in Table 4-25 as the reported value. If no background is given, a 

10-yr average of reported site background is presented. 

Data are available only from 1965. Reports from 1959 and 1960 indicate that 100 area badges were 

in use at LANL and in the Los Alamos area, however, attempts to locate these data have been 

unsuccessful. Reports from those years state that 100 area badges (film) were used in 1959 and 

1960, and gave
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 17 of 96

Figure 4-2. Offsite, perimeter, and onsite LANL TLD locations (from LANL 2002, p. 81). 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 18 of 96

1-year results of "less than 0.5 rem/yr" (LASL 1959, 1960). Reports indicate that elevated gamma 

levels occurred in the early years of TA-2 activities (ENSR 2002). Area badge data (pre-1971) from 

TA-2 (see Section 4.3.2), TA-3, and TA-18 would be useful in estimating dose to unmonitored workers 

for those years.

A special survey found elevated ambient radiation in Acid Canyon, which LANL used from 1951 to 

1964 for liquid waste discharge from TA-45. LANL remediated the contaminated parts of Acid 

Canyon in 1967. Radiation data from before that time were not available. Data that are available 

indicate that in 1978 two areas of the canyon still exhibited elevated gamma dose rates. The areas 

are characterized by steep cliffs and were not routine work locations. Nevertheless, if workers spent 

significant time in these areas, exposures are possible. The above-background dose rates reported 

by LANL for 1978 were 1.1 μrem/hr on average with a maximum of 50 μrem/hr (Ferenbaugh et al. 

1982). Before remediation in 1967, dose rates in the canyon could have been an order of magnitude 

higher. 

The annual site wide maximum ambient radiation dose rates are given in Table 4-30, along with the 

side wide maximum intakes. These dose rates may be used in the event worker location during the 

period of employment is not accurately known. 

Bayo Canyon Releases 

Experiments from 1944 to 1962 in TA-10, Bayo Canyon, involved detonation of explosives around 

radioactive materials. These detonations dispersed materials, principally 140La, to the atmosphere 

and could have caused exposure to LANL workers. LANL has studied the impacts of these 

experiments extensively (Courtwright et al. 1996). Although the focus was on impacts off the LANL 

site, the Courtwright et al. analysis examined a receptor at the town site (TA-0). These results are 

applicable to LANL workers in TA-0, TA-2, TA-21, TA-35, TA-41, TA-43, TA-48, TA-53, TA-60, and 

TA-61 to the extent that these TAs were occupied during the years of the tests. 

Exposures are weighted by direction from TA-10. The prevailing wind direction is from Bayo Canyon 

to the west and north (that is, away from the laboratory). On average, the wind carried 140La to the 

east (TA-0) and to the southeast (TA-2, etc.) about 3% of the time, so no adjustment for wind 

frequency is necessary. The distance to the receptor at TA-0 is 2.9 km, which is less than distances 

to the other TAs. An adjustment for distance is not possible from the available information. 

Therefore, impacts calculated by LANL for TA-0 apply to nearby TAs. More distant TAs would have 

impacts at least 1 order of magnitude smaller. 

Table 4-26 lists doses to the receptor at TA-0 calculated for 1945 to 1960 by Kraig (1997). The 

dominant dose pathway would be exposure to gamma radiation from 140La deposited on the ground. 

Other pathways such as inhalation and other radionuclides are much less important (Kraig 1997). In 

addition to dose, Table 4-26 lists the annual average deposition calculated from the available 

information. 

4.3.2 Release of Noble Gases

TA-2 (nuclear reactor area) and TA-53 [Los Alamos Neutron Science Center (LANSCE) accelerator] 

have a history of noble gas releases. The following paragraphs describe the estimation of external 

dose resulting from these releases. 
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4.3.2.1 Omega Reactors TA-2 

The Omega reactors in TA-2 were in operation from 1944 to 1992, and during that time emitted 

predominantly noble gases. LANL did not routinely measure effluents from the Omega reactors 

(LOPO, HYPO, Omega West), predominantly noble gases, until 1967. After that time, LANL 

monitored 41Ar emissions until the reactors ceased operation. In 1973, LANL reported 133Xe and 135Xe 

emissions, but at a combined rate less than that of 41Ar. Because dose coefficients for xenon isotopes 

are 3 to 5 times less than those for 41Ar, estimated doses for xenon isotopes are insignificant in 

relation to the 41Ar doses. 

Only 41Ar is listed consistently in the source emissions for this TA. The annual average air 

concentrations of 41Ar listed in Table 4D-1 of Attachment 4D for TA-2 were calculated using 

screening-level models in NCRP (1996). Because there was no mention of a stack associated with 

TA-2 in the early years, this analysis assumed that releases and receptors were at essentially the 

same height for all years. 

To calculate average annual air concentrations using the emissions data in Table 4A-2, this analysis 

used the following model (NCRP 1996, p. 12): 

χ/Q = f B / u (s/m3), Eq. 4-2 

where: 

χ = concentration at receptor (Ci/m3) 

Q = stack or building vent release rate (Ci/s) 

f = wind frequency 

B = Gaussian plume model diffusion factor modified for building wake effects (1/m2) 

u = wind speed (m/s) 

The value for the independent factor f corresponds to the default of 0.25 (the maximum frequency for 

any compass point) provided in NCRP (1996), and the site-specific value for u is 2.2 m/s, equivalent 

to the LANL average for 2002 and 2003. The value for B of 2 × 10-4 is from Figure 2.3 in NCRP 

(1996) for a distance of 500 m. This is the average distance a receptor was assumed to be from the 

release point. This B value was the largest value for this receptor distance provided for any projected 

cross-sectional frontal area (AG) of the building influencing air flow. The resultant average χ/Q was 

2.3 × 10-5 s/m3. 

The analysis calculated average annual doses corresponding to these concentrations assuming an 

individual was exposed to this air concentration for 2,000 hr/yr. The analysis used dose coefficients 

for skin and whole body from the Federal Guidance Report No. 12 (Eckerman and Ryman 1993). The 

dose coefficient for skin dose is 3.74 × 10-6 mrem- per μCi-s-m-3 (1.01 × 10-13 Sv per Bq-s-m-3) and for 

whole body is 2.41 × 10-6 mrem per μCi -/s- /m-3 (6.50 × 10-14 Sv per Bq-s-m-3). For pre-1967 years, 

exposures to noble gases in TA-2 could be estimated from area badge data (which has not been 

located as of this writing) or by assuming that the annual dose for 2,000-hr/yr exposure is the peak 

average annual doses in Table 4-27. 

4.3.2.2 Los Alamos Neutron Science Center (TA-53) 

The large, high-current accelerator at TA-53 began operation in 1976. Since then, this facility 

released megacurie quantities of activation products annually through the exhaust stack. In addition 

to 41Ar, the accelerator stack released significant activities of 11C, 13N, and 15O. While not noble 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 20 of 96

gases, these three nuclides have extremely short half-lives and cause radiation exposure more like 

noble gases than long-lived particulates. Therefore, this discussion considers emissions for all these 

radionuclides. 

After 1981, emissions were often reported as gaseous/mixed activation products without 

differentiating the radionuclides represented in that category. Submersion dose coefficients for the 

four radionuclides( 11C, 13N, 15O, and 41Ar) are less than or equal to the skin dose factor for 15O 

(1.04 × 10-13 Sv/Bq, or 3.85 × 10-6 mrem/μCi) or the whole-body dose factor for 41Ar (6.50 × 10-14

Sv/Bq, or 2.41 × 10-6 mrem/μCi) according to Federal Guidance Report No. 11 (Eckerman, Wolbarst, 

and Richardson 1988). Therefore, this analysis simplified the calculations by assuming that the 

composite emissions activity reported for all four radionuclides was equal to that for 15O alone when 

calculating skin dose, and for 41Ar alone when calculating whole-body dose. 

In estimating air concentrations resulting from the LANSCE stack, the analysis considered three work 

locations: TA-53, TA-21, and TA-72. TA-53 was the location where the accelerator operated. The 

two nearby locations were the east end of TA-21 (DP East; 2,000 m south-southeast of TA-53) and 

the west end of TA-72 (on East Jemez Road; 700 m south-southeast of TA-53). An average wind 

rose for each of five meteorological stations at LANL, discussed in the 1999 Site-Wide Environmental 

Impact Statement for LANL (DOE 1999), indicates that the predominant wind directions from TA-53 

are to the north and northeast (Figure 4-3). 

For TA-53, this analysis used the same approach adopted for TA-2 to estimate average air 

concentrations. Again, this assumed no stack release and resulted in an average χ/Q of 2.3 × 10-5

s/m3 (receptor 500 m from the emission point). 

Bowen (1987) modeled dispersion from the LANSCE stack using Gaussian equations. However, the 

calculations were for a receptor at the site boundary (East Gate) rather than for onsite work locations. 

The East Gate is approximately 800 m east of TA-53. The dispersion factor arising from this 

modeling effort was adjusted for this work to apply to TA-21 and TA-72 in developing average annual 

concentrations. The adjustment was based on distances from TA-53, and differential wind 

frequencies were ignored. Wind frequencies, as measured at the East Gate, indicate that frequencies 

toward both TA-21 and TA-72 are 3%, consistent with Figure 4-3. The wind frequency toward the 

public receptor is 13%. Therefore, the assumption that wind frequency is 13% (i.e., not adjusting the 

dispersion factor based on wind frequencies) is a claimant-favorable approach. 

The χ/Q calculated for the East Gate receptor (800 m from TA-53) by Bowen (1987) was 3.8 × 10-6 

s/m3. Because TA-72 is approximately the same distance (700 m) from TA-53 as the East Gate, this 

χ/Q was used to estimate average annual air concentrations at this location. This value of χ/Q was 

adjusted to account for the increased distance that TA-21 is from TA-53 (2,000 m) by multiplying the 

χ/Q for the East Gate by a factor of one-third. The factor of one-third was derived by comparing the 

Gaussian plume model diffusion factor, P, reported in NCRP (1996, Figure 2.2) for a 30-m stack and 

the two different distances (800 m and 2,000 m). The resultant estimate of χ/Q is approximately 

1.3 × 10-6 s/m3. This information is summarized below. 

Receptor

Dist./dir.

from TA-53

Average X/Q

(s/m3)

East Gate 800m / East 3.8 E-06

TA-21 2,000m / SSE 1.3 E-06

TA-72 700m / SSE 3.8 E-06
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Figure 4-3. Average wind rose for five LANL meteorological stations (DOE 1999). 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 22 of 96

Table 4D-2 of Attachment 4D lists the results of these calculations for TA-53, TA-21 and TA-72.

This analysis calculated estimates of external dose (skin and whole body) from LANSCE emissions 

for TA-53, TA-21, and TA-72. The estimated doses in Tables 4-28 and 4-29 are based on average 

annual air concentrations in TA-53, TA-21, and TA-72 from Table 4D-2. The concentrations at TA-53 

assumed a ground-level release. Therefore, the air concentration estimates for TA-53 account for the 

fact that a percentage of the emissions from that location were diffuse, rather than from the 30-m 

stack. 

4.4 UNCERTAINTY 

As discussed in previous sections, estimates of annual intakes employed conservative assumptions 

when information was lacking. Due to the lack of information on particle size and solubility, this 

analysis compensated for the uncertainty of these elements by assuming that all effluents were in the 

respirable size range and selected solubility based on the highest dose rate. 

Effluent data for years around 1971 and later have an estimated uncertainty of ±20%. However, data 

from earlier years are much less accurate because of less reliable measurement technology and less 

stringent reporting requirements. 

The accuracy of the area badge data is also about ±20%. However, subtracting background from 

these measurements adds more uncertainty, due to the variability and selection of background 

information. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 23 of 96

REFERENCES 

Bowen, B. M., 1987, Measurement and Modeling of External Radiation during 1984 from LAMPF 

Atmospheric Emissions, LA-10766-MS, Los Alamos National Laboratory, Los Alamos, New 

Mexico. 

DOE (U. S. Department of Energy), 1999, Site-Wide Environmental Impact Statement for Continued 

Operation of the Los Alamos National Laboratory, Volume I, Main Report, DOE/EIS-0238, 

Albuquerque Operations Office, Albuquerque, New Mexico. 

DOE (U. S. Department of Energy), 2001, Guide of Good Practices for Occupational Radiological 

Protection in Uranium Facilities, Standard DOE-STD-1136-2000, kChange Notice No. 3, 

Washington, D.C., December.

Courtwright, C. C., J. F. Dummer, and J. C. Taschner, 1996, The Bayo Canyon/Radioactive 

Lanthanum (RaLa) Program, LA-13044-H, Los Alamos National Laboratory, Los Alamos, New 

Mexico. 

Eckerman, K. F., and J. C. Ryman, 1993, External Exposure to Radionuclides in Air; Water; and Soil, 

Federal Guidance Report No. 12, EPA-402-R-93-81, 

http://homer.ornl.gov/VLAB/FedGR12.html, U.S. Environmental Protection Agency, 

Washington, D.C. 

Eckerman, K. F., A. B. Wolbarst, and A. C. B. Richardson, 1988, Limiting Values of Radionuclide 

Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and 

Ingestion, Federal Guidance Report No. 11, EPA-5201/1-88-020,

http://homer.ornl.gov/VLAB/FedGR11.html, U.S. Environmental Protection Agency, 

Washington, D.C. 

ENSR, 2002, A Summary of Historical Operations at Los Alamos National Laboratory and Associated 

Off-Site Releases of Radionuclides and Other Toxic Materials, Draft Report, Los Alamos 

Historical Document Retrieval and Assessment Project, Centers for Disease Control and 

Prevention, National Center for Environmental Health. 

Ferenbaugh R. W., W. R. Hansen, A. K. Stoker, and T. E. Buhl, 1982, Environmental Analysis of 

Acid/Middle Pueblo Canyon, LA-9409-MS, Los Alamos National Laboratory, Los Alamos, New 

Mexico. 

ICRP (International Commission on Radiological Protection), 2001, ICRP CD1: Database of Dose 

Coefficients: Worker and Members of the Public, Elsevier B.V. 

Kennedy and W. D. Purtymun, 1971a, Plutonium and Strontium in Soil in the Los Alamos, Espanola 

and Santa Fe, NM Areas, LA-4562, Los Alamos Scientific Laboratory, Los Alamos, New 

Mexico. 

Kennedy and W. D. Purtymun, 1971b, Plutonium and Strontium in Soil Near Technical Area 21, 

LA-4563, Los Alamos Scientific Laboratory, Los Alamos, New Mexico.

Kraig, D. H., 1997, “Dose Reconstruction for Weapons Experiments Involving 140La at Los Alamos 

National Laboratory, 1944–1962,” Health Physics, volume 73, number 4. 
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LANL (Los Alamos National Laboratory), 2000, Environmental Surveillance at Los Alamos during 

2000, LA-13861-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. 

LANL (Los Alamos National Laboratory), 2002, Environmental Surveillance at Los Alamos during 

2002, LA-14085-ENV, Los Alamos National Laboratory, Los Alamos, New Mexico. 

LANL (Los Alamos National Laboratory), 2003, update of LANL AIRNET website, Meteorology and Air 

Quality Group, Los Alamos, New Mexico. 

http://www.lanl.gov/orgs/rres/maq/AirConc_AllData.htm#LOS; downloaded October 8, 2003. 

LASL (Los Alamos Scientific Laboratory), 1959, Los Alamos Environmental Monitoring Program, 1959 

Summary Report, Los Alamos, New Mexico. Unpublished. 

LASL (Los Alamos Scientific Laboratory), 1960, Los Alamos Environmental Monitoring Program, 1960 

Summary, Los Alamos, New Mexico. Unpublished. 

LASL (Los Alamos Scientific Laboratory), 1972, Environmental Surveillance at Los Alamos During 

1972, Environmental Studies Group, Los Alamos, New Mexico. 

LASL (Los Alamos Scientific Laboratory), 1973, Environmental Surveillance at Los Alamos During 

1973, Environmental Studies Group, LA-5586, Los Alamos, New Mexico. 

LASL (Los Alamos Scientific Laboratory), 1979, Formerly Utilized MED/AEC Sites Remedial Action 

Program; Radiological Survey of the Bayo Canyon, DOE/EV-0005/15, Los Alamos, New 

Mexico. 

NCRP (National Council on Radiation Protection and Measurements), 1996, Screening Models for 

Releases of Radionuclides to Atmosphere, Surface Water, and Ground, NCRP Report 123 I, 

Bethesda, Maryland. 

ORAU (Oak Ridge Associated Universities), pending, Technical Basis Document for the Los Alamos 

National Laboratory – Site Description, ORAUT-TKBS-0010-2, Oak Ridge, Tennessee. 

Purtymun, W. D., A. K. Stoker, and R. Peters, 1980, Radioactivity in Soils and Sediments in and 

Adjacent to the Los Alamos Area, 1974-1977, LA-8234-MS, Los Alamos Scientific Laboratory, 

Los Alamos, New Mexico. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 25 of 96

GLOSSARY 

Ambient gamma radiation 

Refers to the external dose rate due to penetrating gamma radiation in the outside air 

environment. Includes gamma radiation from natural cosmic and terrestrial sources, 

as well as man-made sources. 

Noble gases

Here, referring to radioactive isotopes of noble gases, such as 41Ar, 133Xe, and 135Xe. 

Radioactive noble gases are chemically-inert gases of the Helium Group (Group 8A in 

the periodic table of elements), and pose an external hazard only.

Resuspension

A process by which small particulates (generally of soil, which may have radionuclides 

attached) are eroded by wind resulting in an air concentration of “resuspended” 

particles and/or radioactivity. Referred to as “re”-suspension as there exists a cyclical 

process of suspension, deposition, resuspension, and redeposition. However, the 

initial suspension process is generally included in this term, if the initial contaminating 

event did not result from deposition of airborne material. 

Technical Area (TA) 

A land division within Los Alamos National Laboratory in which operations take, or 

have taken, place. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 26 of 96

Table 4-1. Estimated annual average intakes of 

241Am, 3H, 239Pu, and 234U for TA-2 (Bq/yr).a

Year 241Am 3H

b 239Pu 234U

1971 2.4E+03c4.4E-04c4.5E-03c

1972 2.4E+03c4.4E-04c4.5E-03c

1973 2.4E+03c4.4E-04c4.5E-03c

1974 2.4E+03c4.4E-04c4.5E-03c

1975 2.4E+03c4.4E-04c4.5E-03c

1976 2.4E+03c4.4E-04c4.5E-03c

1977 2.4E+03c4.4E-04c4.5E-03c

1978 2.4E+03c4.4E-04c4.5E-03c

1979 2.4E+03c4.4E-04c4.5E-03c

1980 2.4E+03c4.4E-04c4.5E-03c

1981 2.4E+03c4.4E-04c4.5E-03c

1982 2.4E+03c4.4E-04c4.5E-03c

1983 2.4E+03c4.4E-04c4.5E-03c

1984 2.4E+03c4.4E-04c4.5E-03c

1985 2.4E+03c4.4E-04c4.5E-03c

1986 2.4E+03c4.4E-04c4.5E-03c

1987 3.6E+03 8.9E-05 4.7E-03

1988 1.0E+04 2.0E-03 6.3E-03

1989 3.0E+03 2.0E-04 8.9E-03

1990 1.5E+03 1.2E-04 3.2E-03

1991 6.9E+02 4.4E-05 6.6E-03

1992 5.7E+02 1.3E-04 3.3E-03

1993 3.3E+02 5.7E-04 2.4E-03

1994 5.6E+02 2.8E-04 1.5E-03

1995 4.6E-04 4.5E+02 5.5E-04 3.7E-03

1996 5.2E+02d3.1E-04d3.5E-03d

1997 5.2E+02d3.1E-04d3.5E-03d

1998 5.2E+02d3.1E-04d3.5E-03d

1999 5.2E+02d3.1E-04

d

3.5E-03d

2000 0.0E+00 2.4E+02 1.3E-04 1.6E-03

2001 2.4E+02e1.3E-04e1.6E-03e

2002 2.4E+02e1.3E-04e1.6E-03e

2003 2.4E+02e1.3E-04e1.6E-03e

a. Calculated from estimated air concentrations in Table 

4C-2, assuming an inhalation rate of 2,400 m3/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no 

data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion 

dose. 

c. Estimated from average of values from 1987 through 

1995.

d. Estimated from average of values from 1991 through 

1995.

e. Assumed to be the same as value in 2000. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 27 of 96

Table 4-2. Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 232Th, 234U, MFP, 

and P/VAP for TA-3 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 232Th 234U MFPc P/VAPd

1971 8.90E+07 2.7E+04 8.9E-01 2.5E-02 2.3E-02

1972 2.8E-03 4.80E+07 4.4E+03 1.4E+00 1.2E-02 6.9E-03

1973 6.2E-04 4.7E+03 8.3E-01 1.2E-02 3.0E-03 1.4E-02 2.5E+00

1974 9.2E-01 2.9E-01 3.9E-02 6.7E-02

1975 2.20E+07 6.4E+03 2.7E-01 8.2E-02 3.8E-02 3.6E-02

1976 5.9E-02 7.7E-03 7.1E-02 8.1E-02

1977 4.00E+08 1.2E+05 1.7E-02 6.5E-03 6.6E-02 9.4E-02

1978 9.98E+07 2.9E+04 1.6E-02 1.1E-02 3.6E-02 7.9E-02

1979 3.02E+09 8.8E+05 3.1E-02 2.1E-01 5.1E-02 9.2E-02

1980 4.55E+06 1.3E+03 1.8E-02 1.4E-01 3.0E-02 8.3E-02

1981 8.99E+08 2.6E+05 8.6E-03 7.7E-03 4.6E-02 3.4E-02

1982 1.94E+09 5.7E+05 1.5E-01 1.5E-02 6.3E-02 1.5E-02

1983 2.28E+09 6.7E+05 1.6E-02 1.7E-02 3.5E-02 3.3E-03

1984 1.78E+09 5.2E+05 1.4E-02 2.2E-02 4.2E-02 8.1E-03

1985 2.12E+09 6.2E+05 2.9E-02 3.8E-02 6.7E-02 6.8E-03

1986 1.23E+09 3.6E+05 7.4E-03 3.8E-02 1.2E-01 9.4E-03

1987 8.51E+08 2.5E+05 1.3E-02 1.7E-01 4.2E-03

1988 8.35E+09 2.4E+06 1.0E-02 9.8E-02 5.8E-03

1989 2.91E+08 8.5E+04 7.6E-03 7.1E-02 7.5E-03

1990 4.96E+08 1.3E+05 4.2E-03 3.8E-02 7.6E-03

1991 1.3E-04 2.05E+08 2.0E+03 1.1E-04 8.2E-03 2.8E-03

1992 2.8E-04 1.15E+08 3.6E+03 2.2E-04 3.2E-03 1.6E-03

1993 1.7E-03 7.63E+07 7.1E+02 4.9E-03 1.3E-03 1.2E-03

1994 5.2E-04 5.38E+07 2.7E+02 2.8E-04 3.3E-03 7.5E-03

1995 1.3E-03 2.25E+06 8.0E+02 2.6E-04 1.8E-03 1.8E-01

1996 1.3E-04 1.7E+02 2.4E-04 3.2E-05 2.1E-03

1997 2.2E-04 4.8E+02 2.4E-04 7.4E-05 1.5E-03

1998 3.1E-04 3.6E+02 3.6E-05 8.2E-05 1.3E-03

1999 2.0E-04 3.6E+02 2.4E-04 4.3E-05 1.7E-03

2000 0.0E+00 3.2E+02 2.3E-04 2.5E-05 2.7E-03

2001 0.0E+00 4.1E+02 5.3E-05 2.7E-05 2.4E-03

2002 1.5E-04e3.4E+02e1.6E-04e5.0E-05e1.9E-03

2003 1.5E-04e3.9E+02e1.6E-04e5.0E-05e1.9E-03e

a. Calculated from estimated air concentrations in Table 4C-3, assuming an inhalation rate of 2,400 m3/yr 

(and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

d. P/VAP = Particulate/vapor activation products; claimant-favorable to assume all is 68Ge, Class W. 

e. Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 28 of 96

Table 4-3. Estimated annual average intakes of 

241Am, 3H, 239Pu, and 234U for TA-5 (Bq/yr).a 

Year 241Am 3H

b 239Pu 234U

1971

1972

1973 1.4E+04 1.7E-03 4.1E-02

1974 1.1E+04 2.2E-03 1.4E-02

1975 2.3E+04 1.9E-03 9.9E-03

1976 1.6E+04 4.4E-04 8.4E-03

1977 7.6E+03 1.9E-03 1.1E-02

1978 2.1E+03 2.6E-03 8.4E-03

1979 2.0E+03 7.5E-04 1.1E-02

1980 2.3E+03 8.9E-05 7.7E-03

1981 5.9E+02 5.4E-04 5.8E-03

1982 3.3E+03 1.3E-04 5.8E-03

1983 2.3E+03 2.8E-04 6.6E-03

1984 2.4E+03 1.2E-04 5.1E-03

1985 1.7E+03 0.0E+00 4.5E-03

1986 1.3E+03 8.9E-05 3.7E-03

1987 2.6E+03 1.8E-05 5.4E-03

1988 2.0E+03 1.8E-05 9.7E-03

1989 4.7E+02 3.6E-05 1.1E-02

1990 4.3E+02 1.6E-04 4.4E-03

1991 4.9E+02 6.2E-05 7.6E-03

1992 1.2E-04 5.9E+02 7.1E-05 3.0E-03

1993 3.5E+02 1.3E-04 3.1E-03

1994 2.0E+02 1.1E-04 3.1E-03

1995 3.0E-04 3.2E+02 3.9E-04 4.2E-03

1996 2.2E-04 1.5E+02 1.1E-04 5.0E-03

1997 2.1E-04 7.3E+02 4.4E-05 2.2E-03

1998 1.8E-04 4.4E+03 8.9E-05 2.1E-03

1999 3.2E-04 2.9E+02 1.8E-05 1.9E-03

2000 2.7E-05 3.6E+02 1.8E-04 4.8E-03

2001 0.0E+00 5.6E+02 0.0E+00 3.0E-03

2002 1.5E-04c1.3E+03c6.6E-05c2.8E-03c

2003 1.5E-04c1.3E+03c6.6E-05c2.8E-03c

a. Calculated from estimated air concentrations in Table 4C4, assuming an inhalation rate of 2,400 m3

/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data 

are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion 

dose. 

c. Estimated from average of corresponding values for 1997-

2001.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 29 of 96

Table 4-4. Estimated annual average intakes of 241Am, 

3H, 239Pu, and 234U for TA-6 (Bq/yr).a 

Year 241Am 3H

b 239Pu 234U

1971 4.8E+03 3.6E-03 3.3E-02

1972 3.9E+03 1.3E-02 8.3E-03

1973

1974 2.1E+03 2.3E-03 6.9E-03

1975 9.8E-04 2.9E+03 4.8E-03 3.7E-03

1976 3.3E+03 3.5E-04 8.1E-03

1977 2.7E-05 3.3E+03 1.5E-03 2.3E-02

1978 2.7E-05 6.7E+02 2.4E-03 9.9E-03

1979 0.0E+00 3.7E+02 2.9E-04 4.5E-03

1980 8.9E-06 5.1E+02 2.3E-04 3.9E-03

1981 4.0E-03 8.9E+02 5.1E-04 4.4E-03

1982 1.8E-05 1.5E+03 1.1E-04 4.3E-03

1983 1.5E+03 1.1E-04 4.7E-03

1984 5.9E+02 1.1E-04 2.8E-03

1985 1.1E+03 1.7E-04 5.3E-03

1986 2.8E-04 4.8E+02 1.1E-04 5.1E-03

1987 1.3E-04 1.5E+03 5.3E-05 5.5E-03

1988 5.7E-04 1.3E+03 6.2E-05 7.2E-03

1989 2.5E-04 3.1E+02 4.1E-04 9.0E-03

1990 1.4E-04 1.9E+02 1.9E-04 6.4E-03

1991 8.0E-05 2.1E+02 8.9E-05 7.4E-03

1992 4.0E-04 3.6E+02 1.5E-04 2.4E-03

1993 1.3E-04 4.4E+02 2.0E-04 2.0E-03

1994 3.6E-04 1.7E+02 7.1E-05 2.5E-03

1995 5.1E-04 4.8E+02 1.1E-03 1.8E-03

1996 0.0E+00

1997-2003

a. Calculated from estimated air concentrations in Table 4C-5 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 30 of 96

Table 4-5. Estimated annual 

average intakes of 3H for TA-9 

(Bq/yr).a 

Year 3H

b

1971

1972 2.1E+05

1973 1.1E+04

1974 3.8E+02

1975

1976 3.8E+04

1977 7.6E+03

1978 7.6E+02

1979 1.5E+03

1980 1.5E+03

1981-2003

a. Calculated from estimated air 

concentrations in Table 4C-6 assuming 

an inhalation rate of 2,400 m3/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those 

years. 

b. 3H intake multiplied by 1.5 to account for 

submersion dose. 

Table 4-6. Estimated annual average intakes of 241Am, 

3H, 239Pu, and 234U for TA-11 (Bq/yr).a 

Year 241Am 3H

b 239Pu 234U

1971 5.6E+03 4.2E-03 1.2E-02

1972 2.9E-03 3.2E+03 4.3E-03 8.3E-03

1973 1.7E+03 2.0E-03 1.4E-02

1974-2003

a. Calculated from estimated air concentrations in Table 4C-8 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 31 of 96

Table 4-7. Estimated annual average intakes of 241Am, 

3H, 239Pu, and 234U for TA-15 (Bq/yr).a

Year 241Am 3H

b 239Pu 234U

1971 1.1E+04 3.7E-03 6.2E-02

1972 2.0E-03 3.7E+03 4.5E-03 8.3E-03

1973 1.8E-04 2.8E+03 1.4E-03 2.8E-02

1974-1977

1978 2.1E+04

1979-1991

1992 4.5E-01

1993 1.4E+02 9.7E-01

1994 2.6E+02 3.6E-05 5.9E-03

1995 4.5E-04 2.3E+02 3.3E-04 1.3E-03

1996 2.0E-04 1.5E+02 1.2E-04 4.6E-03

1997 1.7E-04 2.5E+02 5.8E-05 2.6E-03

1998 1.9E-04 2.7E+02 7.1E-05 1.3E-03

1999 2.0E-04 2.3E+02 7.1E-05 1.7E-03

2000 3.6E-05 2.4E+02 4.4E-06 2.4E-03

2001 2.2E-04 3.1E+02 0.0E+00 5.8E-03

2002 1.8E-06 3.7E+02 0.0E+00 3.4E-03

2003 1.3E-04c2.8E+02c2.9E-05c2.9E-03c

a. Calculated from estimated air concentrations in Table 4C-9, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 

× 10-2 Bq/pCi; blanks indicate no data are available for those 

years). 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Estimated from average of corresponding values for 1998-2002. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 32 of 96

Table 4-8. Estimated annual average intakes of 241Am, 3H, 

131I, 239Pu, and 234U for TA-16 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 234U

1971 6.0E+03 8.9E-01 5.4E-03 2.8E-02

1972 3.6E-03 4.1E+03 5.1E-03 8.3E-03

1973 2.7E-04 2.1E+03 2.5E-03 1.4E-02

1974 1.6E+03 2.7E-03 9.6E-03

1975 3.6E-04 2.4E+03 1.7E-03 3.6E-03

1976 2.7E+03 4.2E-04 4.8E-03

1977 0.0E+00 4.0E+03 1.7E-03 3.8E-02

1978 0.0E+00 8.0E+02 3.2E-03 6.6E-03

1979 0.0E+00 2.9E+02 1.8E-03 3.6E-03

1980 0.0E+00 1.5E+03 9.8E-05 4.1E-03

1981 1.7E-04 2.5E+02 3.2E-04 3.2E-03

1982 2.7E-05 1.3E+03 8.9E-05 3.2E-03

1983 1.5E+03 4.9E-05 3.2E-03

1984 1.7E+03 0.0E+00 1.8E-03

1985 1.3E+03 3.5E-04 3.8E-03

1986 2.4E-04 6.3E+02 5.3E-05 1.8E-03

1987 8.9E-05 1.3E+03 6.7E-05 2.6E-03

1988 1.7E-04 5.7E+02 7.5E-05 4.7E-03

1989 2.1E-04 3.5E+02 5.3E-05 8.1E-03

1990 2.5E-04 1.5E+02 1.4E-04 4.6E-03

1991 1.1E-04 6.7E+01 8.9E-05 5.4E-03

1992 9.8E-05 2.1E+02 5.3E-04 2.5E-03

1993 1.2E+02 4.4E-05 1.7E-03

1994 1.2E+03 0.0E+00 2.3E-03

1995 4.1E-04 2.4E+04 2.9E-04 1.7E-03

1996 1.6E-04 3.2E+03 3.6E-05 2.4E-03

1997 2.0E-04 8.3E+03 7.1E-05 1.7E-03

1998 2.3E-04 3.3E+04 8.0E-05 2.6E-03

1999 2.8E-04 7.3E+03 1.1E-04 1.3E-03

2000 0.0E+00 8.1E+03 0.0E+00 1.3E-03

2001 1.8E-05 9.1E+03 0.0E+00 1.7E-03

2002 1.5E-04c1.3E+04c5.2E-05c1.7E-03c

2003 1.5E-04c1.3E+04c5.2E-05c1.7E-03c

a. Calculated from estimated air concentrations in Table 4C-10, assuming 

an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Estimated from average of corresponding values for 1997-2001. 

Table 4-9. Estimated annual average 

intakes of 234U for TA-18 (pCi/yr).a

Year 234U

1971-1978

1979 7.7E-04

1980-2003

a. Calculated from estimated air concentrations 

in Table 4C-11, assuming an inhalation rate 

of 2,400 m3/yr (and multiplying by 3.7 × 10-2

Bq/pCi; blanks indicate no data are available 

for those years). 

.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 33 of 96

Table 4-10. Estimated annual average intakes of 241Am, 3H, 131I, 

239Pu, 234U, and MFP for TA-21 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 234U MFPc

1971 5.7E-04d1.1E+04 2.6E-03 1.1E-02

1972 5.7E-04d2.0E+04e7.5E-03 9.6E-03

1973 5.7E-04d2.0E+04 2.0E-03 1.4E-02 2.0E-04

1974 5.7E-04d2.0E+04e2.1E-03 6.9E-03 5.7E-04

1975 5.7E-04d8.5E+03 1.6E-03 4.3E-03 2.8E-04

1976 5.7E-04d5.3E+03 6.7E-04 5.8E-03 1.1E-04

1977 5.7E-04d6.9E+03 1.9E-03 1.3E-02 6.4E-04

1978 6.9E-06 6.9E+03e2.0E-03 1.3E-02 2.0E-04

1979 3.8E-06 5.1E+02 5.4E-04 1.1E-02 9.1E-05

1980 1.2E-05 1.5E+03 2.8E-03 9.9E-03 8.2E-04

1981 5.9E-06 7.5E+02 4.1E-04 5.0E-03 5.5E-04

1982 7.1E-06 2.1E+03 5.3E-04 1.3E-02 8.5E-05

1983 1.9E-05 2.7E+03 8.0E-05 4.3E-03 1.6E-04

1984 5.7E-04d1.2E+03 1.3E-04 8.9E-03 6.1E-05

1985 5.7E-04d2.1E+03 3.6E-05 5.8E-03 7.1E-05

1986 5.7E-04d2.2E+03 1.2E-04 4.8E-03 6.3E-05

1987 5.7E-04d6.9E+03 9.8E-05 4.8E-03 3.7E-05

1988 5.7E-04d5.3E+03 7.1E-05 7.2E-03 3.0E-05

1989 5.7E-04d2.2E+03 1.2E-04 1.1E-02 6.1E-06

1990 5.7E-04d1.7E+03 2.0E-04 6.7E-03 2.5E-06

1991 0.0E+00 1.1E+03 1.7E-04 7.5E-03 5.9E-06

1992 2.4E-04 1.2E+03 8.9E+01 2.2E-04 3.3E-03 4.7E-06

1993 3.2E-04 5.6E+02 4.4E-04 2.4E-03 2.0E-06

1994 5.7E-04 4.5E+02 5.9E-04 2.5E-03 9.8E-06

1995 5.5E-04 1.1E+03 1.1E-03 2.8E-03

1996 3.7E-04 4.1E+02 1.5E-03 2.2E-02

1997 3.8E-04 6.3E+02 1.5E-03 1.9E-03

1998 5.0E-04 1.5E+03 2.3E-03 1.4E-03

1999 2.6E-04 8.2E+02 3.1E-04 1.9E-03

2000 8.3E-05 9.7E+02 3.3E-04 1.8E-03

2001 0.0E+00 9.6E+02 3.3E-04 2.3E-03

2002 2.4E-04f9.8E+02f9.5E-04f1.9E-03f

2003 2.4E-04f9.8E+02f9.5E-04f1.9E-03f

a. Calculated from estimated air concentrations in Table 4C-12, assuming an 

inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

d. Assumed to be the highest value of all years for which data are available. 

e. Assumed to be the highest value of the two adjacent years. 

f. Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 34 of 96

Table 4-11. Estimated annual average intakes of 241Am, 

3H, 131I, 239Pu, and 234U for TA-33 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 234U

1971 6.6E+04 8.9E-01 7.4E-03 1.1E-02

1972 2.4E+04 4.9E-03 1.2E-02

1973 8.0E+03 1.5E-03 2.8E-02

1974 1.9E+04 2.5E-03 9.6E-03

1975 2.1E+04 2.0E-03 3.4E-03

1976 7.9E+03 4.7E-04 5.6E-03

1977 1.1E+03 1.6E-03 1.1E-02

1978 3.3E+03 2.5E-03 8.4E-03

1979 5.3E+03 6.1E-04 5.4E-03

1980 5.9E+03 3.1E-04 6.2E-03

1981 4.0E+03 3.5E-04 5.0E-03

1982 1.2E+04 2.1E-04 5.1E-03

1983 4.8E+03 0.0E+00 2.9E-03

1984 7.5E+03 6.2E-04 2.5E-03

1985 1.4E+04 0.0E+00 2.7E-03

1986 4.2E+03 5.3E-05 2.0E-03

1987 2.6E+03 7.1E-05 4.5E-03

1988 7.7E+03 3.6E-05 1.3E-02

1989 2.4E+03 0.0E+00 7.3E-03

1990 1.1E+03 6.5E-04 7.7E-03

1991 4.3E+02 6.2E-05 1.7E-03

1992 4.9E+02 8.0E-05 1.3E-03

1993 4.0E+02 1.6E-04 1.4E-03

1994 2.4E+02 4.4E-05 1.3E-03

1995 3.5E-04 4.7E+02 1.4E-03 1.5E-03

1996 3.5E-04c1.9E+02 1.4E-03c1.5E-03c

1997 2.8E-04 1.2E+02 1.2E-04 1.2E-03

1998 2.1E-04 1.7E+02 1.2E-04 1.4E-03

1999 2.2E-04 5.3E+02 1.1E-04 1.8E-03

2000 0.0E+00 4.5E+02 1.8E-05 9.9E-04

2001 4.4E+02 0.0E+00 1.3E-03

2002 3.4E+02d7.5E-05d1.3E-03d

2003 3.4E+02d7.5E-05d1.3E-03d

 Calculated from estimated air concentrations in Table 4C-13, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 

× 10-2 Bq/pCi); blanks indicate no data are available for those 

years. 

3H intake multiplied by 1.5 to account for submersion dose. 

 Assumed to be the highest value of the two adjacent years. 

 Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 35 of 96

Table 4-12. Estimated annual average intakes of 241Am, 3H, 239Pu, 234U, 

MFP, and P/VAP for TA-35 (Bq /yr).a

Year 241Am 3H

b 239Pu 234U MFPc P/VAPd

1971 9.2E+05 1.4E-03

1972 7.3E+05 3.5E-03

1973 3.6E+05 4.6E-04

1974 4.1E+05 1.6E-03

1975 7.0E+05 1.2E-03

1976 4.9E+05 4.6E-04

1977 2.3E+05 1.6E-04

1978 2.0E+05 3.8E-04

1979 3.8E+05 1.4E-03

1980 7.3E+03 4.0E-05

1981 9.2E+05e5.2E-05

1982 9.2E+05e2.5E-04

1983 1.8E+03 1.8E-04

1984 6.0E+04 8.1E-05

1985 1.5E+03 1.1E-04

1986 1.4E+04 7.1E-05

1987 4.5E+04 1.2E-04

1988 3.5E+04 3.4E-05

1989 5.3E+03 1.3E-04

1990 1.2E+01 1.7E-04

1991 1.3E-03 2.4E-04

1992 2.9E+01 7.0E-05

1993 5.3E-05

1994 7.6E-05

1995 6.9E-06 5.8E-05 1.4E-04 3.2E-04 3.2E-04

1996-2003

a. Calculated from estimated air concentrations in Table 4C-14, assuming an 

inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate 

no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

d. P/VAP = Particulate/vapor activation products; claimant-favorable to assume all is 

68Ge, Class W. 

e. Assume highest average value for 3H in 1981 and 1982; there are no source terms 

or environmental data readily available. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 36 of 96

Table 4-13. Estimated annual average intakes of 

241Am, 3H, 239Pu, and 234U for TA-36 (Bq/yr).a

Year 241Am 3H

b 239Pu 234U

1971 5.1E+03 2.4E-03 7.8E-02

1972 3.9E+03 5.1E-03 8.3E-03

1973 3.9E+03 2.0E-03 1.4E-02

1974-1992

1993 1.5E+02

1994 1.7E+02 1.0E-03 6.2E-03

1995 4.1E-04 4.9E+02 1.0E-03 8.0E-03

1996 1.3E-04 1.5E+02 7.1E-05 4.3E-03

1997 1.8E-04 1.8E+02 5.8E-05 3.4E-03

1998 1.9E-04 2.4E+02 2.2E-05 3.1E-03

1999 3.2E-04 2.3E+02 4.0E-05 3.1E-03

2000 4.4E-05 2.1E+02 1.3E-05 2.9E-03

2001 0.0E+00 3.3E+02 0.0E+00 1.4E-02

2002 1.8E-06 3.7E+02 0.0E+00 3.4E-03

2003 1.1E-04c2.8E+02c1.5E-05c5.2E-03c

a. Calculated from estimated air concentrations in Table 4C-15, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying 

by 3.7 × 10-2 Bq/pCi); blanks indicate no data are available 

for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Estimated from average of corresponding values for 1998-

2002.

Table 4-14. Estimated annual average 

intakes of 3H, 239Pu, and 234U for TA-39 

(Bq/yr).a

Year 3H

b 239Pu 234U

1971 1.7E+01

1972 2.1E+01

1973-1976

1977 5.2E+03 8.9E-06 1.1E-02

1978 2.0E+03 3.1E-03 1.1E-02

1979 2.1E+03 3.3E-04 3.6E-03

1980 3.7E+03 3.9E-04 6.5E-03

1981 1.6E+03 1.8E-04 4.3E-03

1982 2.0E+04 2.4E-04 7.4E-03

1983 4.1E+03 1.6E-04 1.4E-03

1984 1.9E+03 0.0E+00 3.2E-03

1985 5.5E+03 0.0E+00 4.6E-03

1986 3.3E+03 1.3E-04 2.7E-03

1987-2003

a. Calculated from estimated air concentrations in 

Table 4C-16, assuming an inhalation rate of 

2,400 m3/yr (and multiplying by 3.7 × 10-2

Bq/pCi); blanks indicate no data are available 

for those years. 

b. 3H intake multiplied by 1.5 to account for 

submersion dose. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 37 of 96

Table 4-15. Estimated annual average 

intakes of 3H, 239Pu, and 234U for TA-41 

(Bq/yr).a

Year 3H

b 239Pu 234U

1971 8.5E+04 3.7E-03

1972 2.9E+04 2.1E-03

1973 1.6E+04 3.0E-04

1974-1978

1979 9.4E+04

1980 3.2E+04

1981 1.7E+04

1982 3.8E+04

1983 2.9E+05

1984 1.4E+06

1985 3.7E+05

1986 3.9E+05

1987 4.2E+04

1988 1.2E+05

1989 3.7E+04

1990 3.8E+04

1991 2.9E+05

1992 1.4E+06

1993 3.7E+05 2.0E-06

1994 3.9E+05 3.9E-06

1995 1.4E+05 3.0E-06 1.8E-06

1996 5.1E+05

1997 3.4E+06

1998 1.3E+06

1999 1.1E+06

2000 8.6E+04

2001 1.4E+05

2002 1.2E+06c

2003 1.2E+06c

a. Calculated from estimated air concentrations in 

Table 4C-17, assuming an inhalation rate of 2,400 

m

3

/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those 

years. 

b. 3H intake multiplied by 1.5 to account for 

submersion dose. 

c. Estimated from average of corresponding values 

for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 38 of 96

Table 4-16. Estimated annual average intakes of 

241Am, 3H, 239Pu, and 234U for TA-43 (Bq/yr).a

Year 241Am 3H

b 239Pu 234U

1971 5.7E+03 9.8E-03 1.9E-02

1972 3.7E+03 8.9E-03 8.3E-03

1973 1.9E+03 4.6E-03 1.4E-02

1974 1.3E-03

1975 3.2E-04

1976 1.5E-03

1977 9.1E-04

1978 3.0E-04

1979 1.5E-04

1980 3.6E-05

1981 7.2E-05

1982 2.7E-04

1983 6.5E-04

1984 2.1E-04

1985 3.5E-04

1986 5.7E-04

1987 9.9E-05

1988 2.9E-04

1989-1994

1995 5.3E-05 1.0E-04 2.2E-04

1996-2003

a. Calculated from estimated air concentrations in Table 4C-19, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 

3.7 × 10-2 Bq/pCi); blanks indicate no data are available for 

those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 39 of 96

Table 4-17. Estimated annual 

average intakes of 234U for TA-46 

(Bq/yr).a 

Year 234U

1971 7.8E-04

1972 2.3E-02

1973 4.2E-04

1974 8.0E-05

1975 1.0E-04

1976 6.1E-05

1977 7.8E-07

1978 4.9E-03

1979 4.4E-04

1980 2.9E-04

1981 2.7E-03

1982 4.0E-04

1983 7.0E-06

1984 1.0E-05

1985 5.5E-06

1986 7.8E-07

1987-2003

a. Calculated from estimated air 

concentrations in Table 4C-20, 

assuming an inhalation rate of 2,400 

m

3

/yr (and multiplying by 3.7 × 10-2

Bq/pCi); blanks indicate no data are 

available for those years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 40 of 96

Table 4-18. Estimated annual average intakes of 241Am, 

239Pu, 234U, MFP, and P/VAP for TA-48 (Bq/yr).a

Year 241Am 239Pu 234U MFPb P/VAPc

1971 3.7E-03

1972 2.2E-02 1.6E-03

1973 3.9E-03 3.8E-04 2.0E-01

1974 4.7E-03 2.5E-04 1.8E-01

1975 2.4E-03 6.7E-04 1.4E-01

1976 9.8E-04 2.2E-02 2.4E-01

1977 1.6E-03 1.1E-02 4.3E-01

1978 3.7E-04 2.2E-03 2.3E-01

1979 6.6E-05 2.1E-03 2.1E-01

1980 3.1E-04 1.3E-04 3.4E-01

1981 2.6E-04 4.5E-04 2.7E-01

1982 1.9E-03 1.4E-03 2.1E-01

1983 6.4E-04 1.0E-04 1.6E-01

1984 5.0E-04 2.6E-04 3.1E-01

1985 4.0E-04 3.7E-04 2.4E-01

1986 5.6E-04 1.2E-04 4.9E-01

1987 1.2E-04 3.1E-04 2.4E-01

1988 1.4E-04 4.3E-05 2.2E-01

1989 2.9E-04 5.3E-05 8.5E+01

1990 2.9E-04 3.3E-05 2.0E-01

1991 1.1E-04 2.1E-01 2.0E+01

1992 1.3E-03 8.1E-05 5.4E-01 7.4E+00

1993 6.2E-04 2.8E-04 2.6E-01 1.5E+01

1994 6.3E-04 7.8E-05 7.6E-02 1.6E+01

1995 3.3E-04 6.1E-04 1.0E-04 5.2E+00 5.2E+00

1996 9.8E-07 2.1E-06 2.0E-02

1997 7.0E-08 4.9E-07 2.7E-05 3.5E-01

1998 7.2E-08 2.1E-02

1999 1.2E-07 7.6E-01

2000 3.3E+00

2001 4.5E-01

2002 9.8E-01d

2003 9.8E-01d

a. Calculated from estimated air concentrations in Table 4C-21, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 

× 10-2 Bq/pCi); blanks indicate no data are available for those 

years. 

b. MFP = mixed fission products; claimant-favorable to assume all 

is 90Sr.

c. P/VAP = Particulate/vapor activation products; claimant-favorable 

to assume all is 68Ge, Class W. 

d. Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 41 of 96

Table 4-19. Estimated annual average intakes of 241Am, 

3H, 131I, 239Pu, and 234U for TA-49 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 234U

1971 5.9E-04c2.0E+04 8.9E-01 7.4E-03 3.3E-02

1972 5.9E-04c2.8E+03 6.7E-03 1.7E-02

1973 5.9E-04c4.3E+03 1.7E-03 1.4E-02

1974 5.9E-04c2.9E+03 2.8E-03 1.2E-02

1975 8.9E-05 2.8E+03 1.9E-03 3.7E-03

1976 5.9E-04c2.9E+03 3.8E-04 7.4E-03

1977 0.0E+00 1.6E+03 1.4E-03 1.5E-02

1978 0.0E+00 6.7E+02 2.3E-03 8.4E-03

1979 0.0E+00 7.2E+02 4.1E-04 5.6E-03

1980 2.0E-04 2.8E+02 5.7E-04 5.2E-03

1981 8.0E-05 5.9E+02 5.2E-04 4.5E-03

1982 0.0E+00 9.2E+02 1.6E-04 6.6E-03

1983 5.9E-04c1.5E+03 8.9E-06 8.9E-04

1984 5.9E-04c1.7E+03 7.1E-05 2.2E-03

1985 5.9E-04c4.8E+03 4.6E-04 3.5E-03

1986 5.9E-04c3.3E+02 8.9E-05 2.8E-03

1987 1.1E-04 2.4E+03 5.3E-05 2.8E-03

1988 5.9E-04 1.3E+03 6.2E-05 4.1E-03

1989 5.9E-04c3.5E+02 0.0E+00 6.1E-03

1990 1.5E-04 1.5E+02 7.1E-05 3.7E-03

1991 9.8E-05 1.2E+02 1.5E-04 3.2E-03

1992 4.4E-05 2.1E+02 1.1E-03 4.5E-03

1993 1.3E-04 3.2E+02 2.5E-04 3.0E-03

1994 4.1E-04 1.9E+02 2.3E-04 1.8E-03

1995 3.0E-04 2.9E+02 2.8E-04 1.7E-03

1996 4.3E-04 2.3E+02 4.6E-04 2.2E-03

1997 1.8E-04 4.7E+02 5.3E-05 7.6E-04

1998 2.8E-04 9.0E+02 1.1E-04 1.6E-03

1999 2.4E-04 4.5E+02 4.0E-05 1.6E-03

2000 1.3E-03 4.7E+02 1.8E-05 1.2E-03

2001 4.9E-04d5.0E+02d1.4E-04d1.5E-03d

2002 4.9E-04d5.0E+02d1.4E-04d1.5E-03d

2003 4.9E-04d5.0E+02d1.4E-04d1.5E-03d

a. Calculated from estimated air concentrations in Table 4C-22, 

assuming an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 

× 10-2 Bq/pCi); blanks indicate no data are available for those 

years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Assumed to be the highest value of all years for which data are 

available. 

d. Estimated from average of corresponding values for 1996-2000. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 42 of 96

Table 4-20. Estimated annual average intakes of 241Am, 3H, 131I, 239Pu, 232Th, 

234U, and MFP for TA-50 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 232Th 234U MFPc

1971 8.4E+04 8.9E-01 3.1E-03

1972 5.4E-03

1973 4.9E-04 3.4E-03

1974 7.6E-04 1.9E-02

1975 8.0E-04 8.9E-03

1976 2.1E-04 5.8E-03

1977 1.4E-02 1.8E-02

1978 3.4E-03 8.4E-03

1979 5.7E-04 2.2E-03

1980 2.3E-04 1.7E-03

1981 3.5E-04 5.1E-03

1982 1.3E-03 3.1E-03

1983 1.1E-03 1.9E-03

1984 7.2E-04 1.9E-03

1985 3.9E-04 1.8E-03

1986 5.6E-04 4.2E-03

1987 8.8E-04 4.6E-03

1988 4.0E-04 2.9E-03

1989 9.0E-05 2.1E-03

1990 2.9E-05 8.3E-04

1991 2.7E-04 6.5E-04

1992 1.1E-04 7.5E-04

1993 5.5E-05 7.9E-04

1994 6.1E-05 1.4E-03

1995 1.2E-05 1.4E-04

1996 2.1E-06 8.2E-06 3.7E-05

1997 1.6E-06 1.1E-05 2.5E-07

1998 1.3E-06 2.9E-06 1.5E-05 3.7E-05

1999 2.5E-05 1.0E-05 7.2E-06 3.7E-06

2000 2.7E-05 1.9E-06 1.0E-05

2001 1.1E-08 8.4E-06

2002 1.1E-05d6.8E-06d

2003 1.1E-05d6.8E-06d

a. Calculated from estimated air concentrations in Table 4C-23, assuming an inhalation rate 

of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data are 

available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

d. Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 43 of 96

Table 4-21. Estimated annual average intakes of 241Am, 3H, 131I, 

239Pu, 234U, and P/VAP for TA-53 (Bq/yr).a

Year 241Am 3H

b 131I239Pu 234Uc P/VAPd

1971 1.1E+04 5.9E-03 2.2E-02

1972 2.4E-06 4.4E+03 5.7E-03 9.6E-03

1973 1.1E-07 4.2E+03 2.2E-03 1.4E-02

1974 1.3E+04 2.8E-03 1.5E-02

1975 1.7E-07 9.5E+03 2.0E-03 7.3E-03

1976 6.5E+03 4.4E-04 8.5E-03

1977 6.7E-08 4.7E+03 1.6E-03 1.5E-02

1978 0.0E+00 1.7E+03 1.5E-03 5.5E-03

1979 0.0E+00 5.7E+02 4.4E-04 1.1E-02

1980 5.0E-08 8.3E+02 6.4E-04 1.1E-02

1981 7.2E-08 7.2E+02 5.6E-04 3.6E-03

1982 5.6E-09 9.7E+02 2.0E-04 7.3E-03 3.6E+04

1981 1.5E+03 8.9E-05 3.4E-03 5.2E+05

1984 1.2E+03 5.3E-05 4.5E-03 4.9E+05

1985 1.6E+03 1.1E-04 3.7E-03 3.9E+01

1986 1.7E-07 1.3E+03 7.1E-05 4.2E-03 2.0E+01

1987 4.4E-08 2.0E+03 3.6E-05 4.2E-03 3.9E+01

1988 1.2E-07 3.2E+03 2.0E-04 7.9E-03 2.0E+01

1989 1.8E-07 4.5E+02 8.9E-05 9.9E-03 2.0E+01

1990 1.2E-07 5.2E+02 2.1E-04 9.7E-03 1.6E+01

1991 3.9E-08 1.5E+02 2.7E-04 5.4E-03 3.9E+01

1992 1.0E-07 6.5E+02 2.2E-04 6.9E-03 1.4E+02

1993 2.1E-07 3.2E+02 1.2E-04 1.7E-03 2.0E+03

1994 2.2E-07 2.5E+02 2.2E-04 1.9E-03 6.1E+01

1995 3.4E-07 3.6E+02 9.6E-04 1.6E-03 5.6E+01

1996 1.1E+02 6.8E-02 2.7E+01

1997 5.0E+03 1.8E+02

1998 1.1E+03 6.4E+02

1999 6.7E+02 4.9E-01

2000 8.5E+02 1.8E+02

2001 1.9E+03 2.1E+02

2002 1.9E+03e2.4E+02e

2003 1.9E+03e2.4E+02e

a. Calculated from estimated air concentrations in Table 4C-24, assuming an 

inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks 

indicate no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

d. P/VAP = Particulate/vapor activation products; claimant-favorable to assume 

all is 68Ge, Class W. 

e. Estimated from average of corresponding values for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 44 of 96

Table 4-22. Estimated annual average intakes of 241Am, 

3H, 239Pu, and 234U for TA-54 (Bq/yr).a

Year 241Am 3H

b 239Pu 234U

1971-1975

1976 8.6E-03c4.4E+04 2.8E-03 1.5E-02

1977 4.6E-04 2.5E+04 3.2E-03 2.3E-02

1978 2.0E-04 7.6E+03 7.4E-03 1.4E-02

1979 4.4E-04 4.7E+03 2.0E-03 1.1E-02

1980 3.7E-04 7.1E+03 1.3E-03 1.2E-02

1981 1.4E-04 2.9E+03 9.7E-04 1.2E-02

1982 8.0E-05 3.1E+03 1.3E-03 1.2E-02

1983 8.6E-03c2.4E+03 6.2E-05 4.1E-03

1984 8.6E-03c8.4E+03 1.6E-03 9.2E-03

1985 8.6E-03c1.0E+04 2.1E-03 8.8E-03

1986 1.6E-03 3.7E+03 2.0E-03 8.5E-03

1987 8.4E-04 4.3E+03 1.2E-03 7.4E-03

1988 3.4E-04 3.1E+03 1.6E-03 2.2E-02

1989 7.9E-04 3.8E+03 1.5E-03 1.3E-02

1990 2.8E-04 2.2E+03 4.3E-04 7.2E-03

1991 3.6E-04 1.1E+04 1.6E-03 8.4E-03

1992 1.7E-04 5.9E+03 4.4E-04 2.9E-03

1993 3.4E-04 5.2E+03 7.1E-04 3.1E-03

1994 5.6E-04 4.4E+03 6.3E-04 8.8E-03

1995 1.2E-03 5.8E+03 1.6E-03 5.2E-03

1996 5.6E-03 6.8E+03 7.5E-03 4.9E-03

1997 8.6E-03 1.1E+04 1.3E-02 5.5E-03

1998 1.4E-03 1.7E+04 2.0E-03 6.8E-03

1999 1.4E-03 1.3E+04 2.1E-03 1.1E-02

2000 1.1E-03 1.6E+04 9.0E-04 7.5E-03

2001 9.0E-04 3.1E+04 5.2E-04 5.2E-03

2002 4.6E-03 1.6E+04 9.2E-03 5.3E-03

2003 1.9E-03d1.9E+04d3.0E-03d7.1E-03d

a. Calculated from estimated air concentrations in Table 4C25, assuming an inhalation rate of 2,400 m3

/yr (and 

multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no data 

are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Assumed to be the highest value of all years for which data 

are available. 

d. Estimated from average of corresponding values for 1998-

2002.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 45 of 96

Table 4-23. Estimated annual average intakes of 241Am, 3H, 

239Pu, 232Th, and 234U for TA-55 (Bq/yr).a

Year 241Am 3H

b 239Pu 232Th 234U

1971-1977

1978 7.8E-05

1979 2.1E-05

1980 5.7E-05

1981 1.9E-05

1982 5.5E+03 5.1E-04

1983 1.3E+04 2.1E-04

1984 4.5E+04 2.0E-04

1985 2.1E-04

1986 3.0E+05 4.6E-05

1987 2.5E+04 4.8E-05

1988 9.2E+04 3.0E-03

1989 7.8E+04 4.3E-04

1990 4.9E+04 9.1E-05

1991 2.7E+04 3.9E-04

1992 3.0E+04 2.2E-04

1993 1.9E+04 3.3E-05

1994 6.6E+03 2.3E-05

1995 1.1E-06 4.6E+03 3.2E-06

1996 6.1E-06 9.1E+03 1.7E-05 1.1E-05

1997 7.0E-05 3.5E+03 2.1E-05 8.6E-06

1998 7.4E-07 3.5E+03 1.2E-05 5.9E-06

1999 1.1E-05 5.3E+02 1.2E-05 1.4E-05

2000 6.4E-05 1.9E+03 4.9E-04

2001 1.2E-06 9.7E+02 8.4E-06 2.9E-05 3.3E-05

2002 2.9E-05c2.1E+03c1.1E-04c

2003 2.9E-05c2.1E+03c1.1E-04c

a. Calculated from estimated air concentrations in Table 4C-26, assuming 

an inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); 

blanks indicate no data are available for those years. 

b. 3H intake multiplied by 1.5 to account for submersion dose. 

c. Estimated from average of corresponding values for 1997-2001. 

Table 4-24. Estimated air concentrations from resuspension 

(pCi/m3). 

Nuclide

Bayo 

Canyon

LA 

Canyon

Mortendad 

Canyon

Acid 

Canyon

Pueblo 

Canyon

Pu-239 3E-05 4E-04 7E-05 2.5E-05

Pu-238 5E-04

Cs-137 1.3E-03 7E03

Sr/Y-90 1E-05

U-238 8E-04

Year of data 1978 1977 1977 1978 1978
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 46 of 96

Table 4-25. Area badge data - Annual TLD/film results (mrem).a

Year

Site-wide 

Maximum TA-3

b

TA-18bTA-53 bTA-54 b Backgroundc,d

Geometric 

mean

Geometric 

standard 

deviation

2002 156 115 156 129 236 150 152 1.31

2001e570 570 224 170 236 150 238 1.69

2000e268 268 195 212 236 150 208 1.24

1999e241 143 216 241 233 150 192 1.28

1998 426 157 153 426 213 150 201 1.56

1997e462 145 197 462 181 150 205 1.60

1996 173 127 241 159 173 150 166 1.27

1995 378 123 378 142 161 150 174 1.56

1994 160 130 127 152 160 150 143 1.11

1993 148 118 128 142 148 150 137 1.11

1992 236 122 123 135 236 144 147 1.31

1991 178 130 136 178 162 150 150 1.14

1990 178 137 136 178 162 164 155 1.13

1989 149 115 149 94 129 152 126 1.22

1988 188 150 188 113 131 155 145 1.21

1987 166 166 153 115 132 152 142 1.16

1986 183 183 181 143 160 152 163 1.11

1985 187 143 187 145 160 150 156 1.12

1984 183 139 183 161 159 150 158 1.11

1983 188 150 188 163 157 150 161 1.10

1982 163 163 153 138 116 146 142 1.14

1981 175 156 175 123 91 139 134 1.29

1980 303 211 303 146 134 152 180 1.40

1979 252 141 252 150 150 153 165 1.27

1978 234 144 182 234 112 137 157 1.33

1977 273 273 164 203 NM 151 183 1.29

1976 261 238 261 172 NM 145 188 1.31

1975 380 380 220 169 NM 158 202 1.47

1974 137 NA 345 169 150 151 191 1.49

1973f345 128 345 178 NA 184 195 1.54

1972f160 150 225 NA NA 176 181 1.23

1971 106 138 276 NA NA 169 186 1.43

1970 132 NA NA NA NA NA NA NA

1969 302 NA NA NA NA NA NA NA

1968 302 NA NA NA NA NA NA NA

1967 302 NA NA NA NA NA NA NA

1966 354 NA NA NA NA NA NA NA

1965 423 NA NA NA NA NA NA NA

a. Dose is based on 8760 hr/yr and can be adjusted to 2080 hr/yr by multiplying by 0.237. NA= data not available. 

b. Numbers in italics are averages of several area badges in the TA. 

c. Backgrounds in italics are a 10- yr average, because actual background is not given. 

d. Reported background is the average background for Los Alamos town site plus 2-sigma (or 20%). 

e. Neutron dose included for 1997 and 1999 at TA-18 and 2000 and 2001 at TA-3, TA-18.

f. In these years, TA-36 exposure was elevated due to experiments at adjacent TA-18: 1973 dose, 81 mrem (net); 1972 dose, 53 mrem 

(net). For the only other year of data, 1971, dose was not elevated. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 47 of 96

Table 4-26. Estimated annual 

deposition of 140La and doses 

from radioactive lanthanum 

experiments.a

Year

Doseb

(mrem)

Depositionc

(μCi/m2)

1945 8 4.2E3

1946 8 4.2E3

1947 9 4.7E3

1948 3 1.6E3

1949 12 6.3E3

1950 8 4.2E3

1951 3 1.6E3

1952 1 5.3E2

1953 9 4.7E3

1954 15 7.9E3

1955 23 1.2E4

1956 21 1.1E4

1957 10 5.3E3

1958 6 3.2E3

1959 5 2.6E3

1960 3 1.6E3

Geometric mean 6.9

Geometric std. Dev. 2.2

a. Applicable to town site, TA-2, and 

vicinity. 

b. Source: Kraig (1997, Figure 5). 

c. Calculated from Kraig (1997, 

Equations 2 and 3). 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 48 of 96

Table 4-27. Estimated average external doses 

from 41Ar released from TA-2 (mrem/yr).a 

Year Skinb Whole bodyc

1971 3.1E+00 2.0E+00

1972 1.3E+00 8.1E-01

1973 5.4E-01 3.4E-01

1974 6.1E-03 3.9E-03

1975 4.7E-01 3.0E-01

1976 6.7E-01 4.3E-01

1977 6.2E-01 4.0E-01

1978 4.7E-01 3.0E-01

1979 6.9E-01 4.4E-01

1980 1.0E+00 6.5E-01

1981 5.9E-01 3.8E-01

1982 6.7E-01 4.3E-01

1983 8.2E-01 5.3E-01

1984 6.6E-01 4.2E-01

1985 7.7E-01 4.9E-01

1986 5.4E-01 3.5E-01

1987 4.6E-01 2.9E-01

1988 5.2E-01 3.3E-01

1989 4.4E-01 2.8E-01

1990 3.1E-01 2.0E-01

1991 4.0E-01 2.6E-01

1992 2.7E-01 1.8E-01

Geometric mean 5.0E-01 3.2E-01

Geometric std. Dev. 3 3

a. Assumes receptor is at 500 m from the source 2,000 hr 

per yr, no plume depletion, no plume rise (stack height 

is zero). 

b. Calculated using skin dose factor for 41Ar from 

Eckerman and Ryman (1993). 

c. Calculated using whole-body dose factor for 41Ar from 

Eckerman and Ryman (1993). 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 49 of 96

Table 4-28. Estimated average external doses from 

gaseous/mixed activation products released from TA-53

(mrem/yr).a 

Year Skinb Whole bodyc

1943-1976 Not in operation

1976 1.2E+01 7.4E+00

1977 9.6E+01 6.0E+01

1978 2.4E+02 1.5E+02

1979 2.4E+02 1.5E+02

1980 3.0E+02 1.8E+02

1981 7.1E+02 4.5E+02

1982 5.1E+02 3.2E+02

1983 9.3E+02 5.8E+02

1984 1.5E+03 9.3E+02

1985 2.5E+02 1.6E+02

1986 2.3E+02 1.4E+02

1987 3.0E+02 1.9E+02

1988 2.4E+02 1.5E+02

1989 3.2E+02 2.0E+02

1990 2.5E+02 1.6E+02

1991 1.2E+02 7.2E+01

1992 1.5E+02 9.1E+01

1993 6.5E+01 4.0E+01

1994 1.0E+02 6.3E+01

1995 8.8E+01 5.5E+01

1996 2.2E+01 1.4E+01

1997 4.0E+01 2.5E+01

1998 1.6E+01 9.9E+00

1999 6.1E-01 3.8E-01

2000 1.4E+00 8.7E-01

2001 1.2E+01 7.5E+00

2002 1.4E+01d8.8E+00d

2003 1.4E+01d8.8E+00d

Geometric mean 8.5E+01 5.3E+01

Geometric std. Dev. 6.5 6.5

a. Assumes receptor is at 500 m from the source 2,000 hr per yr, no 

plume depletion, no plume rise (stack height is zero). 

b. Calculated using skin dose factor for 15O from Eckerman and 

Ryman (1993). 

c. Calculated using whole-body dose factor for 41Ar from Eckerman 

and Ryman (1993). 

d. Estimated assuming equal to average of corresponding values 

for 1997-2001. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 50 of 96

Table 4-29. Estimated average external doses from 

gaseous/mixed activation products released from TA-21 and 

TA-72 (mrem/yr). 

Year

TA-21 TA-72

Skina Whole bodyb Skina Whole bodyb

1976 6.55E-01 4.10E-01 1.97E+00 1.23E+00

1977 5.30E+00 3.31E+00 1.59E+01 9.93E+00

1978 1.30E+01 8.14E+00 3.91E+01 2.44E+01

1979 1.32E+01 8.28E+00 3.97E+01 2.48E+01

1980 1.62E+01 1.02E+01 4.87E+01 3.05E+01

1981 3.93E+01 2.46E+01 1.18E+02 7.37E+01

1982 2.79E+01 1.75E+01 8.38E+01 5.24E+01

1983 5.13E+01 3.21E+01 1.54E+02 9.62E+01

1984 8.17E+01 5.11E+01 2.45E+02 1.53E+02

1985 1.40E+01 8.76E+00 4.21E+01 2.63E+01

1986 1.25E+01 7.79E+00 3.74E+01 2.34E+01

1987 1.67E+01 1.04E+01 5.01E+01 3.13E+01

1988 1.35E+01 8.42E+00 4.04E+01 2.52E+01

1989 1.74E+01 1.08E+01 5.21E+01 3.25E+01

1990 1.37E+01 8.55E+00 4.11E+01 2.57E+01

1991 6.37E+00 3.98E+00 1.91E+01 1.19E+01

1992 8.01E+00 5.01E+00 2.40E+01 1.50E+01

1993 3.56E+00 2.23E+00 1.07E+01 6.68E+00

1994 5.56E+00 3.48E+00 1.67E+01 1.04E+01

1995 4.85E+00 3.03E+00 1.46E+01 9.10E+00

1996 1.22E+00 7.65E-01 3.67E+00 2.30E+00

1997 2.23E+00 1.39E+00 6.68E+00 4.17E+00

1998 8.68E-01 5.42E-01 2.60E+00 1.63E+00

1999 3.34E-02 2.09E-02 1.00E-01 6.26E-02

2000 7.68E-02 4.80E-02 2.30E-01 1.44E-01

2001 6.57E-01 4.10E-01 1.97E+00 1.23E+00

2002 7.72E-01c4.83E-01c2.32E+00c1.45E+00c

2003 7.72E-01c4.83E-01c4.83E-01c1.45E+00c

Geometric mean 4.6E+00 2.9E+00 1.4E+01 8.7E+00

Geometric std. dev. 6.5E+00 6.5E+00 6.5E+00 6.5E+00

a. Calculated using skin dose factor for 15O from Eckerman and Ryman 

(1993). 

b. Calculated using whole-body dose factor for 41Ar from Eckerman and 

Ryman (1993). 

c. Estimated assuming equal to average of corresponding values for 1997-

2001.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 51 of 96

Table 4-30. Estimated annual site wide maximum intakes and ambient dose rates for all radionuclides .

Year

Maximum intakes (Bq/yr)a Maximum 

ambient dose 

rates (mrem/yr) 241Am 3H

131I239Pu 232Th 234U MFPb P/VAPc

1971 9.2E+05 8.9E-01 2.5E-02 1.7E+01 276

1972 3.6E-03 7.3E+05 1.4E+00 2.2E-02 2.1E+01 225

1973 6.2E-04 3.6E+05 8.3E-01 1.2E-02 3.0E-03 4.1E-02 2.5E+00 345

1974 4.1E+05 9.2E-01 2.9E-01 3.9E-02 1.8E-01 137

1975 9.8E-04 7.0E+05 2.7E-01 8.2E-02 3.8E-02 1.4E-01 380

1976 4.9E+05 5.9E-02 7.7E-03 7.1E-02 2.4E-01 238

1977 4.6E-04 2.3E+05 1.7E-02 1.4E-02 6.6E-02 4.3E-01 273

1978 2.0E-04 2.0E+05 1.6E-02 1.1E-02 3.6E-02 2.3E-01 234

1979 4.4E-04 3.8E+05 3.1E-02 2.1E-01 5.1E-02 2.1E-01 252

1980 3.7E-04 3.2E+04 1.8E-02 1.4E-01 3.0E-02 3.4E-01 303

1981 4.0E-03 1.7E+04 8.6E-03 7.7E-03 4.6E-02 2.7E-01 175

1982 8.0E-05 3.8E+04 1.5E-01 1.5E-02 6.3E-02 2.1E-01 3.6E+04 163

1983 1.9E-05 2.9E+05 1.6E-02 1.7E-02 3.5E-02 1.6E-01 5.2E+05 188

1984 1.4E+06 1.4E-02 2.2E-02 4.2E-02 3.1E-01 4.9E+05 183

1985 3.7E+05 2.9E-02 3.8E-02 6.7E-02 2.4E-01 3.9E+01 187

1986 1.6E-03 3.9E+05 7.4E-03 3.8E-02 1.2E-01 4.9E-01 2.0E+01 183

1987 8.4E-04 4.5E+04 1.3E-02 1.7E-01 2.4E-01 3.9E+01 166

1988 5.9E-04 1.2E+05 1.0E-02 9.8E-02 2.2E-01 2.0E+01 188

1989 7.9E-04 7.8E+04 7.6E-03 7.1E-02 8.5E+01 2.0E+01 149

1990 2.8E-04 4.9E+04 4.2E-03 3.8E-02 2.0E-01 1.6E+01 178

1991 3.6E-04 2.9E+05 1.6E-03 8.4E-03 2.1E-01 3.9E+01 178

1992 4.0E-04 1.4E+06 8.9E+01 1.3E-03 4.5E-01 5.4E-01 1.4E+02 236

1993 1.7E-03 3.7E+05 4.9E-03 9.7E-01 2.6E-01 2.0E+03 148

1994 5.7E-04 3.9E+05 1.0E-03 8.8E-03 7.6E-02 6.1E+01 160

1995 1.3E-03 1.4E+05 1.6E-03 8.0E-03 5.2E+00 4.4E+02 161

1996 5.6E-03 5.1E+05 6.8E-02 7.5E-03 3.2E-05 2.2E-02 2.7E+01 241

1997 8.6E-03 3.4E+06 1.3E-02 7.4E-05 5.5E-03 1.8E+02 462

1998 1.4E-03 1.3E+06 2.3E-03 8.2E-05 6.8E-03 6.4E+02 426

1999 1.4E-03 1.1E+06 2.1E-03 4.3E-05 1.1E-02 7.6E-01 241

2000 1.3E-03 8.6E+04 9.0E-04 2.5E-05 7.5E-03 1.8E+02 268

2001 9.0E-04 1.4E+05 5.2E-04 2.9E-05 1.4E-02 2.1E+02 570

2002 4.6E-03 1.2E+06 9.2E-03 5.0E-05 5.3E-03 2.4E+02 156

2003 1.9E-03 1.2E+06 3.0E-03 5.0E-05 7.1E-03 2.4E+02

a. Values are the maximum annual average intake reported for all technical areas in Tables 4-1 through 4-23 for each radionuclide, and are based on an 

inhalation rate of 2,400 m3/yr (and multiplying by 3.7 × 10-2 Bq/pCi); blanks indicate no release or air concentration data were available. 

b. MFP = mixed fission products; claimant-favorable to assume all is 90Sr.

c. P/VAP = Particulate/vapor activation products; claimant-favorable to assume all is 68Ge, Class 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 52 of 96

ATTACHMENT 4A, 4B, 4C, 4D 

TABLES OF SOURCE EMISSIONS, SCREENING ESTIMATES, AIR CONCENTRATIONS 

LIST OF TABLES 

Table Page

4A-1 Estimated source emissions from TA-1 ..............................................................................54

4A-2 Estimated source emissions from TA-2 ..............................................................................54

4A-3 Estimated source emissions from TA-3 ..............................................................................55

4A-4 Estimated source emissions from TA-9 ..............................................................................56

4A-4 Estimated source emissions from TA-10 ............................................................................56

4A-6 Estimated source emissions from TA-15 ............................................................................57

4A-7 Estimated source emissions from TA-16 ............................................................................58

4A-8 Estimated source emissions from TA-18 ............................................................................58

4A-9 Estimated source emissions from TA-21 ............................................................................59

4A-10 Estimated source emissions from TA-33 ............................................................................60

4A-11 Estimated source emissions from TA-35 ............................................................................61

4A-12 Estimated source emissions from TA-36 ............................................................................62

4A-13 Estimated source emissions from TA-39 ............................................................................62

4A-14 Estimated source emissions from TA-41 ............................................................................63

4A-15 Estimated source emissions from TA-42 ............................................................................63

4A-16 Estimated source emissions from TA-43 ............................................................................64

4A-17 Estimated source emissions from TA-46 ............................................................................64

4A-18 Estimated source emissions from TA-48 ............................................................................65

4A-19 Estimated source emissions from TA-50 ............................................................................66

4A-20 Estimated source emissions from TA-53 ............................................................................67

4A-21 Estimated source emissions from TA-54 ............................................................................68

4A-22 Estimated source emissions from TA-55 ............................................................................69

4B-1 Data and results of screening analysis for potential contributors to inhalation 

dose ....................................................................................................................................71

4C-1 Estimated average air concentrations for 239Pu for TA-1 ....................................................72

4C-2 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-2 ...........................72

4C-3 Estimated average air concentrations for 241Am, 3H, 131I, Pu, 232Th, U, MFP, and 

P/VAP for TA-3 ...................................................................................................................73

4C-4 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-5 ...........................74

4C-5 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-6 ...........................75

4C-6 Estimated average air concentrations for 3H for TA-9 .........................................................76

4C-7 Estimated average air concentrations for U for TA-10........................................................77

4C-8 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-11 .........................77

4C-9 Estimated average air concentrations for 241Am. 3H, Pu, 232Th, and U for TA-15 ...............78

4C-10 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-16...................79

4C-11 Estimated average estimated air concentrations for U for TA-18 .......................................80

4C-12 Estimated average air concentrations for 241Am, 3H, 131I, Pu, U, and MFP for TA21 ........................................................................................................................................81

4C-13 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-33...................82

4C-14 Estimated average air concentrations for 241Am, 3H, Pu, U, MFP, and P/VAP for 

TA-35 ..................................................................................................................................83

4C-15 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-36 .........................84

4C-16 Estimated average air concentrations for 3H, Pu, and U for TA-39.....................................85

4C-17 Estimated average air concentrations for 3H, Pu, and U for TA-41.....................................86

4C-18 Estimated average air concentrations for Pu for TA-42 ......................................................87
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 53 of 96

4C-19 Estimated average air concentrations for 241Am , 3H, Pu, and U for TA-43 ........................87

4C-20 Estimated average air concentrations for U for TA-46........................................................88

4C-21 Estimated average air concentrations for 241Am , Pu, U, MFP, and P/VAP for TA48 ........................................................................................................................................89

4C-22 Estimated average air concentrations for 241Am, 3H, 131I, Pu, and U for TA-49...................90

4C-23 Estimated average air concentrations for 241Am, 3H, 131I, Pu, 232Th, U, and MFP 

for TA-50 .............................................................................................................................91

4C-24 Estimated average air concentrations for 241Am, 3H, 131I, Pu, U, and P/VAP for 

TA-53 ..................................................................................................................................92

4C-25 Estimated average air concentrations for 241Am, 3H, Pu, and U for TA-54 .........................93

4C-26 Estimated average air concentrations for 241Am, 3H, Pu, 232Th, and U for TA-55 ...............94

4D-1 Estimated average annual air concentrations of 41Ar for TA-2 ............................................95

4D-2 Estimated average annual air concentrations of gaseous/mixed activation 

products for TA-53, TA-21, and TA-72................................................................................96
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 54 of 96

Tables 4A-1 through 4A-22 contain emissions data that have been reported by year and radionuclide 

for many of the Technical Areas (TAs) at Los Alamos National Laboratory (LANL). In recent years, 

effluents have been reported by stack and/or building vent; in these cases, the effluents were 

summed within a TA. For years prior to 1971, the reported effluent releases rely on data from the 

Center for Disease Control and Prevention’s Los Alamos Historical Document Retrieval and 

Assessment project; after 1971, the reported releases are found in annual environmental surveillance 

reports. 

Table 4A-1. Estimated source emissions from 

TA-1 (μCi/yr). 

Year Pu

1943 No source estimates for this year

1944 No source estimates for this year

1945 2.11E+05

1946 2.65E+05

1947 4.21E+05

1948-2001 No source estimates for these years

2002

2003

Table 4A-2. Estimated source emissions from 

TA-2 (μCi/yr). 

Year 4`Ar

1943-1966 No source estimates for this year

1967 1.55E+10

1968 6.48E+09

1969 1.80E+09

1970 1.30E+09

1971 1.57E+09

1972 6.40E+08

1973 2.73E+08

1974 3.12E+06

1975 2.37E+08

1976 3.39E+08

1977 3.15E+08

1978 2.39E+08

1979 3.51E+08

1980 5.13E+08

1981 3.01E+08

1982 3.42E+08

1983 4.18E+08

1984 3.35E+08

1985 3.90E+08

1986 2.76E+08

1987 2.32E+08

1988 2.64E+08

1989 2.22E+08

1990 1.60E+08

1991 2.03E+08

1992 1.40E+08

1993-2003 Not in operation
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 55 of 96

Table 4A-3. Estimated source emissions from TA-3 (μCi/yr). 

Year 241Am 3H

131I Pu 232Th U MFP P/VAP

1943-1951 No source estimates for these years

1952 1.00E+01

1953 2.30E+02

1954 1.30E+03

1955 1.89E+03

1956 1.49E+03

1957 1.12E+03

1958 3.21E+03

1959 8.90E+02

1960 2.97E+03

1961 1.92E+03

1962 1.80E+03

1963 6.52E+05 8.60E+02

1964 2.97E+05 6.50E+02

1965 3.81E+05 1.59E+03

1966 1.88E+03

1967 4.19E+03

1968 6.05E+03

1969 1.16E+04

1970 1.35E+04

1971 8.90E+07 6.95E+03 1.43E+04 5.80E+02

1972 4.80E+07a7.40E+03a7.90E+03a3.60E+02a

1973 4.23E+03 7.30E+03 1.56E+01 5.93E+02 1.28E+04

1974 4.73E+03 1.47E+03 2.02E+02 3.42E+02

1975 2.20E+07 1.36E+03 4.20E+02 1.94E+02 1.84E+02

1976 0.00E+00 3.00E+02 3.95E+01 3.63E+02 4.15E+02

1977 4.00E+08 8.80E+01 3.35E+01 3.38E+02 4.81E+02

1978 9.98E+07 8.10E+01 5.83E+01 1.85E+02 4.03E+02

1979 3.02E+09 1.58E+02 1.07E+03 2.61E+02 4.72E+02

1980 4.55E+06 9.40E+01 7.41E+02 1.55E+02 4.24E+02

1981 8.99E+08 4.40E+01 3.96E+01 2.36E+02 1.72E+02

1982 1.94E+09 7.85E+02 7.44E+01 3.21E+02 7.63E+01

1983 2.28E+09 8.30E+01 8.85E+01 1.81E+02 1.71E+01

1984 1.78E+09 7.30E+01 1.15E+02 2.14E+02 4.15E+01

1985 2.12E+09 1.46E+02 1.95E+02 3.44E+02 3.47E+01

1986 1.23E+09 3.80E+01 1.94E+02 6.31E+02 4.79E+01

1987 8.51E+08 6.49E+01 8.68E+02 2.16E+01

1988 8.35E+09 5.19E+01 5.00E+02 2.97E+01

1989 2.91E+08 3.91E+01 3.65E+02 3.82E+01

1990 4.96E+08 2.16E+01 1.96E+02 3.89E+01

1991 2.05E+08 3.08E+01 2.44E+02 1.41E+01

1992 1.15E+08 2.73E+00 1.98E+02 8.42E+00

1993 7.63E+07 1.74E+00 2.18E+02 6.05E+00

1994 5.38E+07 6.00E+00 1.96E+02 3.84E+01

1995 4.02E+00 2.25E+06 5.35E+01 1.53E+02 9.38E+02 9.38E+02

1996 1.22E+00 2.31E+01 1.64E-01 3.87E+01

1997 3.70E-01 3.50E+00 3.80E-01 2.20E+01

1998 1.60E+00 1.10E+01 4.20E-01 3.10E+01 6.70E+00

1999 2.60E+00 2.10E+01 2.20E-01 7.60E+00

2000 1.80E-01 3.20E+00 1.30E-01 6.80E+00

2001 2.60E-01 9.20E+00 1.40E-01 7.10E+00

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions noted in database for 1972. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 56 of 96

Table 4A-4. Estimated source emissions from 

TA-9 (μCi/yr). 

Year 3H

1943-1971 No source estimates for these years

1972 7.00E+08a

1973 3.60E+07b

1974 1.30E+06

1975 No source estimates for this year 

1976 1.29E+08

1977 2.60E+07

1978 2.60E+06

1979 5.00E+06

1980 5.00E+06

1981-2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to 

inconsistencies or omissions noted in database for 

1972.

b. Value taken from LASL (1973) due to 

inconsistencies noted in database for 1973. 

Table 4A-5. Estimated source emissions from 

TA-10 (μCi/yr). 

Year U

1943 No source estimates for this year

1944 1.00E+04

1945 1.00E+04

1946 3.00E+04

1947 4.00E+04

1948 6.00E+04

1949 1.00E+05

1950 5.00E+05

1951 2.00E+05

1952 2.00E+05

1953 2.00E+05

1954 4.00E+03

1955 3.30E+04

1956 3.50E+04

1957 1.10E+04

1958 7.00E+03

1959 1.20E+04

1960 7.00E+03

1961 8.82E+05

1962 1.82E+05

1963 5.00E+04

1964-2001 No source estimates for these years

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 57 of 96

Table 4A-6. Estimated source emissions from TA15 (μCi/yr). 

Year 3H

232Th U

1943 No source estimates for this year

1944 6.00E+04

1945 1.20E+05

1946 2.40E+05

1947 3.60E+05

1948 5.40E+05

1949 8.70E+05

1950 4.50E+06

1951 2.00E+06

1952 1.80E+06

1953 1.60E+06

1954 1.49E+06

1955 1.19E+06

1956 7.93E+05

1957 1.20E+06

1958 1.07E+06

1959 5.16E+05

1960 7.14E+05

1961 3.48E+05

1962 4.73E+05

1963 3.96E+05

1964 5.97E+05

1965 5.72E+05

1966 9.42E+05

1967 3.59E+09 2.00E+09 7.20E+05

1968 4.50E+09 2.00E+09 5.37E+05

1969 4.50E+09 4.28E+05

1970 2.87E+10 3.07E+05

1971 2.66E+09 4.95E+05

1972 1.81E+09 1.64E+05

1973 9.30E+08a

1974-1977 No source estimates for these years

1978 7.16E+07

1979-1991 No source estimates for these years

1992 2.29E+03

1993 4.94E+03

1994 7.87E+03

1995-2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1973) due to omission noted 

in database for 1973. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 58 of 96

Table 4A-7. Estimated source emissions from 

TA-16 (μCi/yr). 

Year 3H U

1943-53 No source estimates for these years

1954 3.80E+04

1955 No source estimates for this year

1956 No source estimates for this year

1957 1.40E+04

1958 No source estimates for this year

1959 1.00E+03

1960 5.00E+04

1961 No source estimates for this year

1962 No source estimates for this year

1963 4.80E+04

1964 3.00E+03

1965 4.00E+03

1966 No source estimates for this year

1967 5.00E+03

1968 3.90E+04

1969 3.00E+03

1970 1.10E+04

1971 2.00E+03

1972-1991 No source estimates for these years

1992 6.28E+04

1993 7.73E+05

1994 2.46E+07

1995 8.90E+07

1996 9.90E+07

1997 9.80E+07

1998 2.40E+08

1999 1.60E+08

2000 2.60E+08

2001 7.90E+09

2002

2003

Table 4A-8. Estimated source emissions from 

TA-18 (μCi/yr). 

Year U

1943-1978 No source estimates for these years

1979 3.95E+00

1980-2001 No source estimates for these years

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 59 of 96

Table 4A-9. Estimated source emissions from TA-21 

(μCi/yr). 

Year 241Am 3H Pu U MFP

1943-1947 No source estimates for these years (see TA-1 data)

1948 1.55E+05

1949 1.55E+05

1950 1.85E+05

1951 2.70E+04

1952 5.70E+04

1953 3.50E+04

1954 2.20E+04

1955 8.80E+04

1956 7.60E+04

1957 7.40E+04

1958 8.00E+04

1959 1.86E+05

1960 3.53E+04

1961 6.24E+03

1962 7.99E+03 6.29E+03

1963 2.87E+04 3.05E+04

1964 1.24E+04 2.31E+03

1965 9.31E+03 9.13E+03

1966 1.04E+04 1.00E+04

1967 9.99E+03 6.91E+03

1968 1.94E+03 1.30E+03

1969 4.17E+03 3.56E+03

1970 2.82E+03 1.03E+03

1971 5.00E+06 1.79E+03 1.18E+03

1972 2.17E+03 1.20E+03a

1973 4.00E+06b1.40E+03 9.08E+02 1.00E+00

1974 5.71E+00 6.00E+02 2.90E+00

1975 3.06E+08 1.11E+01 7.21E+02 1.44E+00

1976 9.50E+07 1.22E+01 8.70E+02 5.50E-01

1977 1.33E+08 9.99E+00 3.17E+02 3.26E+00

1978 3.40E-02 3.07E+01 3.05E+02 1.03E+00

1979 1.90E-02 9.49E+07 6.46E+00 6.55E+02 4.68E-01

1980 6.10E-02 1.06E+08 2.27E+00 6.33E+02 4.18E+00

1981 2.90E-02 1.08E+08 1.31E+01 1.02E+03 2.80E+00

1982 3.50E-02 1.69E+08 1.58E+01 1.04E+03 4.35E-01

1983 9.50E-02 1.80E+08 9.92E+00 7.06E+02 7.94E-01

1984 8.02E+08 1.73E+01 9.90E+02 3.14E-01

1985 3.67E+08 1.06E+01 3.82E+02 3.61E-01

1986 4.48E+08 3.57E+00 2.12E+02 3.24E-01

1987 5.96E+08 1.43E+00 2.07E+02 1.88E-01

1988 5.28E+08 7.13E-01 5.88E+01 1.54E-01

1989 4.55E+08 1.39E+00 2.89E+01 3.10E-02

1990 4.39E+08 9.01E-01 4.32E+01 1.30E-02

1991 3.24E+08 8.45E-01 9.20E+01 3.00E-02

1992 4.29E+08 8.70E-01 5.20E+01 2.40E-02

1993 4.26E+08 8.10E-01 5.17E+01 1.00E-02

1994 3.32E+08 2.40E+00 1.82E+02 5.00E-02

1995 7.72E-03 7.12E+08 6.41E-01 1.71E+00

1996 3.90E+08

1997 2.10E+08

1998 4.60E+08

1999 4.90E+08

2000 9.40E+08

2001 4.90E+08

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions noted in database for 

1972.

b. Value taken from LASL (1973) due to inconsistencies noted in database for 1973. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 60 of 96

Table 4A-10. Estimated source emissions from 

TA-33 (μCi/yr). 

Year 3H U

1943-1965 No source estimates for these years

1966 1.00E+04

1967-1970 No source estimates for these years

1971 4.10E+09

1972 2.90E+09a

1973 3.90E+09b

1974 5.92E+09

1975 3.48E+09

1976 1.35E+09

1977 3.70E+10

1978 1.78E+10

1979 1.05E+10

1980 6.97E+09

1981 6.09E+09

1982 1.36E+10

1983 4.41E+09

1984 7.11E+09

1985 4.87E+09

1986 6.66E+09

1987 1.00E+09

1988 No source estimates for this year

1989 1.77E+09

1990 8.54E+08

1991 2.54E+08

1992 3.18E+08

1993 3.50E+08

1994 4.56E+08

1995 1.09E+08

1996 No source estimates for this year

1997 4.30E+07

1998 6.50E+07

1999 9.40E+08

2000 1.20E+09

2001 4.60E+08

2002

2003

a. Value taken from LASL (1972) due to inconsistencies 

or omissions noted in database for 1972. 

b. Value taken from LASL (1973) due to inconsistencies 

noted in database for 1973. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 61 of 96

Table 4A-11. Estimated source emissions from TA-35 (μCi/yr). 

Year 241Am 3H Pu U MFP PVAP

1943-1966 No source estimates for these years

1967 6.60E+00

1968 5.90E+00

1969 5.57E+00

1970 4.21E+00

1971 3.13E+09 7.37E+00

1972 2.50E+09a1.79E+01

1973 1.23E+09 2.35E+00

1974 1.40E+09 8.01E+00

1975 2.39E+09 5.91E+00

1976 1.66E+09 2.37E+00

1977 7.86E+08 8.19E-01

1978 6.76E+08 1.96E+00

1979 1.30E+09 7.40E+00

1980 2.50E+07 2.07E-01

1981 2.66E-01

1982 1.30E+00

1983 6.00E+06 9.26E-01

1984 2.06E+08 4.17E-01

1985 5.28E+06 5.61E-01

1986 4.76E+07 3.63E-01

1987 1.55E+08 6.36E-01

1988 1.18E+08 1.72E-01

1989 1.82E+07 6.80E-01

1990 4.00E+04 8.95E-01

1991 4.30E+00 1.22E+00

1992 1.00E+05 3.58E-01

1993 MDA 2.70E-01

1994 3.90E-01

1995 3.55E-02 2.97E-01 6.93E-01 1.63E+00 1.63E+00

1996-2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions noted in database for 

1972.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 62 of 96

Table 4A-12. Estimated source emissions from 

TA-36 (μCi/yr). 

Year U

1943-1957 No source estimates for these years

1958 4.30E+04

1959 8.00E+03

1960 1.40E+04

1961 No source estimates for this year

1962 1.00E+04

1963 1.40E+04

1964 4.00E+03

1965 2.00E+04

1966 2.80E+04

1967 4.80E+04

1968 2.70E+04

1969 1.90E+04

1970 6.00E+03

1971 1.00E+04

1972 4.00E+03

1973-2001 No source estimates for these years

2002

2003

Table 4A-13. Estimated source emissions from 

TA-39 (μCi/yr). 

Year U

1943-53 No source estimates for these years

1954 1.91E+05

1955 1.48E+05

1956 1.73E+05

1957 2.66E+05

1958 2.85E+05

1959 1.89E+05

1960 1.16E+05

1961 1.63E+05

1962 1.63E+05

1963 1.26E+05

1964 1.15E+05

1965 1.07E+05

1966 1.23E+05

1967 2.00E+05

1968 5.00E+04

1969 6.60E+04

1970 5.10E+04

1971 8.70E+04

1972 1.10E+05

1973-2001 No source estimates for these years

2002

2003
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Table 4A-14. Estimated source emissions from 

TA-41 (μCi/yr). 

Year 3H Pu U

1943-1966 No source estimates for these years

1967 1.20E+02

1968 3.30E+01

1969 9.00E+00

1970 7.80E+00

1971 3.20E+08 1.90E+01

1972 1.10E+08a1.10E+01

1973 5.90E+07 1.52E+00

1974-1978 No source estimates for these years

1979 1.43E+08

1980 4.14E+08

1981 1.26E+08

1982 1.30E+08

1983 9.74E+08

1984 4.78E+09

1985 1.27E+09

1986 1.32E+09

1987 4.70E+08

1988 1.73E+09

1989 1.16E+10

1990 4.44E+09

1991 3.84E+09

1992 2.92E+08

1993 4.83E+08 1.00E-02

1994 1.72E+08 2.00E-02

1995 7.85E+07 1.56E-02 9.02E-03

1996 1.10E+08

1997 4.20E+07

1998 3.60E+07

1999 1.30E+07

2000 6.30E+06

2001 5.30E+08

2002

2003

a. Value taken from LASL (1972) due to 

inconsistencies or omissions noted in database for 

1972.

Table 4A-15. Estimated source emissions from 

TA-42 (μCi/yr). 

Year Pu source

1943-1968 No source estimates for these years

1969 8.10E+02

1970-2001 No source estimates for this year

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 64 of 96

Table 4A-16. Estimated source emissions from 

TA-43 (μCi/yr). 

Year 241Am Pu U

1943-1972 No source estimates for these years

1973 4.80E-01

1974 6.91E+00

1975 1.65E+00

1976 7.72E+00

1977 4.65E+00

1978 1.55E+00

1979 7.55E-01

1980 1.84E-01

1981 3.68E-01

1982 1.39E+00

1983 3.33E+00

1984 1.05E+00

1985 1.80E+00

1986 2.91E+00

1987 5.06E-01

1988 1.46E+00

1989-1994 No source estimates for these years

1995 2.69E-01 5.27E-01 1.12E+00

1996-2001 No source estimates for these years

2002

2003

Table 4A-17. Estimated source emissions from 

TA-46 (μCi/yr). 

Year U source

1950-70 Operations started in 1950; No 

source estimates for these years

1971 4.00E+00

1972 1.20E+02a

1973 2.17E+00

1974 4.10E-01

1975 5.20E-01

1976 3.10E-01

1977 4.00E-03

1978 2.53E+01

1979 2.27E+00

1980 1.48E+00

1981 1.38E+01

1982 2.03E+00

1983 3.60E-02

1984 5.10E-02

1985 2.80E-02

1986 4.00E-03

1987-2001 No source estimates for these years

2002

2003

a. Value taken from LASL (1972) due to 

inconsistencies or omissions noted in database for 

1972.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 65 of 96

Table 4A-18. Estimated source emissions from TA-48 (μCi/yr). 

Year 241Am Pu U MFP PVAP GMAP

19-1966 Started operations in mid 1950s; No source estimates for these years

1967 1.10E+02

1968 1.50E+02

1969 1.30E+02

1970 5.70E+01

1971 1.89E+01

1972 1.13E+02 8.00E+00a

1973 1.98E+01 1.96E+00 1.02E+03

1974 2.39E+01 1.26E+00 9.41E+02

1975 1.23E+01 3.44E+00 7.22E+02

1976 5.02E+00 1.12E+02 1.23E+03

1977 8.38E+00 5.52E+01 2.19E+03

1978 1.91E+00 1.12E+01 1.17E+03

1979 3.36E-01 1.08E+01 1.07E+03

1980 1.57E+00 6.66E-01 1.75E+03

1981 1.32E+00 2.31E+00 1.37E+03

1982 9.95E+00 7.33E+00 1.09E+03

1983 3.30E+00 5.11E-01 8.16E+02

1984 2.55E+00 1.34E+00 1.57E+03

1985 2.07E+00 1.91E+00 1.21E+03

1986 2.85E+00 6.11E-01 2.50E+03

1987 6.15E-01 1.58E+00 1.25E+03

1988 7.24E-01 2.20E-01 1.11E+03

1989 1.49E+00 2.70E-01 4.35E+05

1990 1.48E+00 1.70E-01 1.04E+03

1991 5.86E-01 1.08E+03 1.00E+05 1.78E+05

1992 6.72E+00 4.17E-01 2.74E+03 3.79E+04

1993 3.16E+00 1.42E+00 1.35E+03 7.59E+04

1994 3.22E+00 4.00E-01 3.90E+02 8.13E+04

1995 1.71E+00 3.10E+00 5.37E-01 2.64E+04 2.64E+04

1996 5.00E-03 1.10E-02 1.00E+02

1997 3.60E-04 2.50E-03 1.40E-01 1.80E+03

1998 3.70E-04 1.10E+02

1999 6.10E-04 3.90E+03

2000 1.70E+04

2001 2.30E+03

2002

2003

a. Value taken from LASL (1972) due to inconsistencies or omissions noted in database for 1972. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 66 of 96

Table 4A-19. Estimated source emissions from TA-50 (μCi/yr). 

Year 241Am Pu 232Th U MFP

1943-1966 No source estimates for these years

1967 1.01E+02

1968 6.88E+01

1969 4.20E+01

1970 2.04E+01

1971 1.60E+01

1972 2.74E+01

1973 2.49E+00 1.72E+01

1974 3.90E+00 8.83E+01

1975 4.11E+00 4.22E+01

1976 1.10E+00 2.75E+01

1977 6.96E+01 8.58E+01

1978 1.74E+01 3.99E+01

1979 2.90E+00 1.06E+01

1980 1.17E+00 8.25E+00

1981 1.79E+00 2.42E+01

1982 6.54E+00 1.45E+01

1983 5.55E+00 9.08E+00

1984 3.67E+00 8.90E+00

1985 2.02E+00 8.49E+00

1986 2.88E+00 2.01E+01

1987 4.51E+00 2.16E+01

1988 2.05E+00 1.38E+01

1989 4.59E-01 9.78E+00

1990 1.48E-01 3.92E+00

1991 1.38E+00 3.09E+00

1992 5.50E-01 3.57E+00

1993 2.80E-01 3.75E+00

1994 3.10E-01 6.79E+00

1995 6.26E-02 7.21E-01

1996 1.10E-02 4.20E-02 1.90E-01

1997 8.40E-03 5.41E-02 1.30E-03

1998 6.50E-03 1.50E-02 7.70E-02 1.90E-01

1999 1.30E-01 5.11E-02 3.70E-02 1.90E-02

2000 9.80E-03 5.30E-02

2001 5.80E-05 4.30E-02

2002

2003
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Table 4A-20. Estimated source emissions from TA-53 

(μCi/yr). 

Year 3H

131I PVAP GMAP

1943-1973 No source estimates for these years

1974 1.00E-02

1975 1.00E-02

1976 1.71E+08 5.89E+09

1977 2.90E+08 4.76E+10

1978 1.17E+11

1979 1.19E+11

1980 1.46E+11

1981 6.59E+06 3.53E+11

1982 2.72E+05 1.8E+08 2.51E+11

1983 2.6E+09 4.61E+11

1984 2.70E+07 2.5E+09 7.34E+11

1985 6.96E+06 2.0E+05 1.26E+11

1986 6.10E+06 1.0E+05 1.12E+11

1987 1.52E+07 2.0E+05 1.50E+11

1988 4.27E+06 1.0E+05 1.21E+11

1989 8.20E+06 1.0E+05 1.56E+11

1990 2.84E+06 8.0E+04 1.23E+11

1991 8.87E+05 2.0E+05 5.72E+10

1992 4.21E+07 7.3E+05 7.20E+10

1993 4.86E+07 1.0E+07 3.20E+10

1994 1.46E+07 3.1E+05 5.00E+10

1995 3.17E+06 2.9E+05 4.36E+10

1996 4.80E+06 3.50E+02 1.4E+05 1.10E+10

1997 1.70E+07 9.0E+05 2.00E+10

1998 3.80E+06 3.3E+06 7.80E+09

1999 2.30E+06 2.5E+03 3.00E+08

2000 2.90E+06 9.3E+05 6.90E+08

2001 6.37E+06 1.1E+06 5.90E+09

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 68 of 96

Table 4A-21. Estimated source emissions from 

TA-54 (μCi/yr). 

Year Pu U

1943-1976 No source estimates for these years

1977 3.00E-03

1978 2.60E-02

1979 1.30E-02

1980 3.00E-03

1981 1.00E-02

1982 2.00E-02

1983 2.00E-03

1984 2.30E-02

1985 6.00E-03

1986 1.65E-01

1987 2.60E-02

1988 1.40E-02

1989 2.20E-02

1990 8.40E-02

1991 4.50E-02

1992 1.00E-02

1993 <MDA

1994 1.00E-02

1995 8.48E-04

1996

1997 2.80E-02

1998-2001 No source estimates for these years

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 69 of 96

Table 4A-22. Estimated source emissions from TA-55 (μCi/yr). 

Year 241Am 3H Pu 232Th U

1943-1977 No source estimates for these years

1978 3.99E-01

1979 1.08E-01

1980 2.94E-01

1981 9.70E-02

1982 1.87E+07 2.59E+00

1983 4.42E+07 1.07E+00

1984 1.52E+08 1.04E+00

1985 1.07E+00

1986 1.01E+09 2.34E-01

1987 8.54E+07 2.45E-01

1988 3.14E+08 1.53E+01

1989 2.66E+08 2.22E+00

1990 1.67E+08 4.68E-01

1991 9.12E+07 2.00E+00

1992 1.02E+08 1.12E+00

1993 6.46E+07 1.70E-01

1994 2.26E+07 1.20E-01

1995 5.45E-03 1.56E+07 1.63E-02

1996 3.10E-02 3.10E+07 8.85E-02 5.50E-02

1997 1.20E+07 1.10E-01 4.40E-02

1998 3.80E-03 1.20E+07 6.20E-02 3.00E-02

1999 5.40E-02 1.80E+06 6.30E-02 7.10E-02

2000 3.30E-01 6.40E+06 2.50E+00

2001 6.20E-03 3.30E+06 4.30E-02 1.50E-01 1.70E-01

2002

2003
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 70 of 96

Table 4B-1 presents results of a screening analysis used to identify radionuclides of potential 

significance to inhalation dose. The analysis evaluated the potential 50-year committed inhalation 

dose associated with the maximum annual reported emission of each radionuclides from data in 

Tables 4A-1 through 4A-22. Inhalation doses were calculated by estimating maximum air 

concentrations using a screening-level dispersion model, assuming an annual inhalation rate of 3,400 

m

3

/yr, and maximum effective and organ dose factors from the CD1 compilation for ICRP 68 (ICRP 

2001). 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 71 of 96

Table 4B-1. Data and results of screening analysis for potential contributors to inhalation dose. 

Radionuclide

Year 

of max 

release

Maximum 

releasea

(μCi/yr)

Estimated 

max intakeb

(Bq/yr)

Organ with 

highest dose 

factorc

Max organ dose 

coefficient 

ICRP 68c

(Sv/Bq)

Effective dose 

coefficient 

ICRP 68c

(Sv/Bq)

Estimated 

max organ 

dose (Sv/yr)

Estimated max 

effective dose 

(Sv/yr)

<10E-5

effective dose 

(Sv/yr)?

H-3 1977 3.70E+10 5.31E+08 All 1.8E-11 1.8E-11 9.6E-03 9.6E-03

Be-7 1991 1.94E+04 2.79E+02 ET airways 4.2E-10 4.6E-11 1.2E-07 1.3E-08 Screened

P-32 1977 3.04E+02 4.37E+00 Lung 1.6E-08 2.9E-09 7.0E-08 1.3E-08 Screened

As-72 1991 8.72E+04 1.25E+03 ET airways 1.0E-08 1.3E-09 1.3E-05 1.6E-06 Screened

Br-76 1991 2.00E+03 2.87E+01 ET airways 1.0E-08 5.8E-10 2.9E-07 1.7E-08 Screened

Rb-88 1973 3.00E+06 4.31E+04 ET airways 3.8E-10 2.8E-11 1.6E-05 1.2E-06 Screened

Sr-90 1971 1.48E+03 2.13E+01 Lung 6.3E-07 7.7E-08 1.3E-05 1.6E-06 Screened

I-131 1963 6.52E+05 9.36E+03 Thyroid 2.1E-07 1.1E-08 2.0E-03 1.0E-04

Cs-137 1971 5.60E+02 8.04E+00 ET airways 1.3E-08 6.7E-09 1.0E-07 5.4E-08 Screened

Cs-138 1971 2.60E+04 3.73E+02 ET airways 9.4E-10 4.6E-11 3.5E-07 1.7E-08 Screened

La-140 1955 5.43E+04 7.80E+02 ET airways 1.4E-08 1.5E-09 1.1E-05 1.2E-06 Screened

Ir-192 1971 9.67E-01 1.39E-02 Lung 3.4E-08 4.9E-09 4.7E-10 6.8E-11 Screened

Hg-203 1980 4.67E+01 6.71E-01 Lung 5.1E-08 7.0E-09 3.4E-08 4.7E-09 Screened

Th-232 1967 2.00E+09 2.87E+07 Bone surface 1.5E-03 2.9E-05 4.3E+04 8.3E+02

Th-234 1975 6.56E+03 9.42E+01 Lung 3.7E-08 5.8E-09 3.5E-06 5.5E-07 Screened

U-234 1950 3.33E+06 4.78E+04 ET airways 7.5E-05 6.8E-06 3.6E+00 3.3E-01

U-235 1950 1.80E+05 2.58E+03 ET airways 6.9E-05 6.1E-06 1.8E-01 1.6E-02

U-238 1950 9.45E+05 1.36E+04 ET airways 6.5E-05 5.7E-06 8.8E-01 7.7E-02

Pu-238 1947 2.65E+05 3.81E+03 Bone surface 9.1E-04 3.0E-05 3.5E+00 1.1E-01

Pu-239 1947 2.65E+05 3.81E+03 Bone surface 1.0E-03 3.2E-05 3.8E+00 1.2E-01

Am-241 1995 4.02E+00 5.77E-02 Bone surface 1.1E-03 2.7E-05 6.3E-05 1.6E-06

MFPd1989 4.35E+05 6.25E+03 Lung 6.3E-07 4.7E-08 3.9E-03 2.9E-04

P/VAPe1983 2.64E+09 3.79E+07 Lung 5.9E-08 9.3E-09 2.2E+00 3.5E-01

a. From Table 4A -1 through 4A-22.

b. Calculated assuming dispersion factor of .0036 s/m3and an annual inhalation rate of 3,400 m3/hr. 

c. From ICRP CD1 Database containing ICRP 68 dose coefficients (ICRP 2001). 

d. Assume MFP is 90Sr to give maximum estimate. 

e. Assume P/VAP is 68Ge to give maximum estimate. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 72 of 96

Tables 4C-1 through 4C-26 provide estimated average air concentrations for TAs at LANL for which 

air monitoring data and/or emissions data were available. Air monitoring data, when available, formed 

the basis for estimates at each TA. For some TAs, more than one monitoring stations was active 

during many years. In these cases, the concentrations were averaged over all stations within the TA. 

For years and locations when monitoring data were not available, an estimate was made based on 

the relationship between source emission rate and air concentration for years when data were 

available (See Section 4.2.1.3).

Table 4C-1. Estimated average air 

concentrations for 239Pu for TA-1 (pCi/m3).a

Year

239Pu Average Air 

Concentration

1943-1944 Not availableb

1945 4.6E-01

1946 5.8E-01

1947 9.3E-01

1948-1975 Not availableb

1976-2003 TA was decontaminated in 1975

a. Based on estimated average ratio of plutonium 

activity:source emission activity for TA-3 and TA21 of 2.2 × 10-12 yr/m3

. 

b. Source term estimates or measured air 

concentrations not available during these years. 

Table 4C-2. Estimated average air concentrations for 

241Am, 3H, 239Pu, and 234U for TA-2(pCi/m3

).a

Year 241Am 3H

239Pu 234U

1943-1986 Not availableb

1987 2.7E+01 1.0E-06 5.3E-05

1988 7.8E+01 2.3E-05 7.1E-05

1989 2.3E+01 2.2E-06 1.0E-04

1990 1.1E+01 1.3E-06 3.7E-05

1991 5.2E+00 5.0E-07 7.5E-05

1992 4.3E+00 1.5E-06 3.7E-05

1993 2.5E+00 6.4E-06 2.7E-05

1994 4.2E+00 3.1E-06 1.7E-05

1995 5.2E-06 3.4E+00 6.2E-06 4.2E-05

1996 Not availableb

2000 0.00E+00 1.8E+00 1.5E-06 1.8E-05

2001-2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-2, averaged over results reported at 

locations within the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not 

available during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 73 of 96

Table 4C-3. Estimated average air concentrations for 241Am, 3H, 131I, 239Pu, 232Th, 234U, MFP, and 

P/VAP for TA-3 (pCi/m3).a

Year 241Am 3H

131I239Pu 232Th 234U MFP,b P/VAP

1943-1951 Not availablec

1952 2.2E-05d

1953 5.1E-04d

1954 2.9E-03d

1955 4.2E-03d

1956 3.3E-03d

1957 2.5E-03d

1958 7.1E-03d

1959 2.0E-03d

1960 6.5E-03d

1961 4.2E-03d

1962 4.0E-03d

1963 1.4E+00d1.9E-03d

1964 6.5E-01d1.4E-03d

1965 8.4E-01d3.5E-03d

1966 4.1E-03d

1967 9.2E-03d

1968 1.3E-02d

1969 2.6E-02d

1970 3.0E-02d

1971 2.0E+02 1.0E-02 2.8E-04 2.6E-04

1972 3.2E-05 3.3E+01 1.6E-02d1.4E-04 7.8E-05

1973 7.0E-06 3.5E+01 9.3E-03d1.4E-04 3.4E-05d1.6E-04 2.8E-02d

1974 1.0E-02d3.2E-03d4.4E-04d7.5E-04d

1975 4.8E+01 3.0E-03d9.2E-04d4.3E-04d4.0E-04d

1976 6.6E-04d8.7E-05d8.0E-04d9.1E-04d

1977 8.8E+02d1.9E-04d7.4E-05d7.4E-04d1.1E-03d

1978 2.2E+02d1.8E-04d1.3E-04d4.1E-04d8.9E-04d

1979 6.6E+03d3.5E-04d2.4E-03d5.7E-04d1.0E-03d

1980 1.0E+01d2.1E-04d1.6E-03d3.4E-04d9.3E-04d

1981 2.0E+03d9.7E-05d8.7E-05d5.2E-04d3.8E-04d

1982 4.3E+03d1.7E-03d1.6E-04d7.1E-04d1.7E-04d

1983 5.0E+03d1.8E-04d1.9E-04d4.0E-04d3.8E-05d

1984 3.9E+03d1.6E-04d2.5E-04d4.7E-04d9.1E-05d

1985 4.7E+03d3.2E-04d4.3E-04d7.6E-04d7.6E-05d

1986 2.7E+03d8.4E-05d4.3E-04d1.4E-03d1.1E-04d

1987 1.9E+03d1.4E-04d1.9E-03d4.8E-05d

1988 1.8E+04d1.1E-04d1.1E-03d6.5E-05d

1989 6.4E+02d8.6E-05d8.0E-04d8.4E-05d

1990 1.1E+03d4.8E-05d4.3E-04d8.6E-05d

1991 1.5E-06 1.5E+01 1.2E-06 9.3E-05 3.1E-05d

1992 3.2E-06 2.7E+01 2.5E-06 3.6E-05 1.9E-05d

1993 1.9E-05 5.3E+00 5.6E-05 1.4E-05 1.3E-05d

1994 5.8E-06 2.0E+00 3.2E-06 3.7E-05 8.4E-05d

1995 1.4E-05 6.0E+00 2.9E-06 2.0E-05 2.1E-03d2.1E-03d

1996 1.5E-06 1.3E+00 2.7E-06 3.6E-07d2.3E-05

1997 2.5E-06 3.6E+00 2.7E-06 8.4E-07d1.7E-05

1998 3.5E-06 2.7E+00 4.0E-07 9.2E-07d1.5E-05 1.5E-05d

1999 2.2E-06 2.7E+00 2.7E-06 4.8E-07d1.9E-05

2000 0.0E+00 2.4E+00 2.6E-06 2.9E-07d3.0E-05

2001 0.0E+00 3.1E+00 6.0E-07 3.1E-07d2.7E-05

2002-2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-3, averaged over results reported at locations in the TA (LANL 2003), 

unless otherwise indicated. 

b. MFP – Mixed Fission Products; P/VAP = Particulate and Vapor Activation Products 

c. Source term estimates or measured air concentrations not available during these years. 

d. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 of 2.2 × 10-12 yr/m3. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 74 of 96

Table 4C-4. Estimated average air concentrations for 

241Am, 3H, 239Pu, and 234U for TA-5 (pCi/m3

).a

Year 241Am 3H

239Pu 234U

1943-1972 Not availableb

1973 1.0E+02 1.9E-05 4.7E-04

1974 8.1E+01 2.4E-05 1.6E-04

1975 1.7E+02 2.2E-05 1.1E-04

1976 1.2E+02 4.9E-06 9.5E-05

1977 5.7E+01 2.2E-05 1.3E-04

1978 1.6E+01 2.9E-05 9.5E-05

1979 1.5E+01 8.4E-06 1.2E-04

1980 1.7E+01 1.0E-06 8.7E-05

1981 4.4E+00 6.1E-06 6.5E-05

1982 2.5E+01 1.5E-06 6.5E-05

1983 1.7E+01 3.1E-06 7.4E-05

1984 1.8E+01 1.3E-06 5.7E-05

1985 1.2E+01 0.0E+00 5.0E-05

1986 9.8E+00 1.0E-06 4.1E-05

1987 1.9E+01 2.0E-07 6.1E-05

1988 1.5E+01 2.0E-07 1.1E-04

1989 3.5E+00 4.0E-07 1.2E-04

1990 3.2E+00 1.8E-06 5.0E-05

1991 3.7E+00 7.0E-07 8.6E-05

1992 1.4E-06 4.4E+00 8.0E-07 3.4E-05

1993 2.6E+00 1.5E-06 3.5E-05

1994 1.5E+00 1.2E-06 3.5E-05

1995 3.4E-06 2.4E+00 4.4E-06 4.8E-05

1996 2.5E-06 1.1E+00 1.2E-06 5.6E-05

1997 2.4E-06 5.5E+00 5.0E-07 2.4E-05

1998 2.0E-06 3.3E+01 1.0E-06 2.4E-05

1999 3.6E-06 2.2E+00 2.0E-07 2.1E-05

2000 3.0E-07 2.7E+00 2.0E-06 5.4E-05

2001 0.0E+00 4.2E+00 0.0E+00 3.4E-05

2002-2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-3, averaged over results reported at 

locations in the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not 

available during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 75 of 96

Table 4C-5. Estimated average air concentrations for 

241Am, 3H, 239Pu, and 234U for TA-6 (pCi/m3

).a

Year 241Am 3H

239Pu 234U

1943-1970 Not availableb

1971 3.6E+01 4.1E-05 3.7E-04

1972 2.9E+01 1.5E-04 9.3E-05

1973

1974 1.6E+01 2.6E-05 7.8E-05

1975 1.1E-05 2.2E+01 5.5E-05 4.2E-05

1976 2.5E+01 3.9E-06 9.1E-05

1977 3.0E-07 2.5E+01 1.7E-05 2.6E-04

1978 3.0E-07 5.0E+00 2.7E-05 1.1E-04

1979 0.0E+00 2.8E+00 3.3E-06 5.1E-05

1980 1.0E-07 3.8E+00 2.6E-06 4.3E-05

1981 4.5E-05 6.7E+00 5.7E-06 5.0E-05

1982 2.0E-07 1.1E+01 1.2E-06 4.8E-05

1983 1.1E+01 1.2E-06 5.3E-05

1984 4.4E+00 1.2E-06 3.1E-05

1985 8.3E+00 1.9E-06 6.0E-05

1986 3.1E-06 3.6E+00 1.2E-06 5.8E-05

1987 1.5E-06 1.1E+01 6.0E-07 6.2E-05

1988 6.4E-06 9.4E+00 7.0E-07 8.1E-05

1989 2.8E-06 2.3E+00 4.6E-06 1.0E-04

1990 1.6E-06 1.4E+00 2.1E-06 7.2E-05

1991 9.0E-07 1.6E+00 1.0E-06 8.3E-05

1992 4.5E-06 2.7E+00 1.7E-06 2.7E-05

1993 1.5E-06 3.3E+00 2.2E-06 2.2E-05

1994 4.1E-06 1.3E+00 8.0E-07 2.8E-05

1995 5.7E-06 3.6E+00 1.2E-05 2.1E-05

1996 0.0E+00

1997-2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-3, averaged over results reported at 

locations within the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not 

available during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 76 of 96

Table 4C-6. Estimated average air 

concentrations for 3H for TA-9 

(pCi/m3).a

Year 3H

1943-1971 Not availableb

1972 1.5E+03

1973 7.9E+01

1974 2.9E+00

1975 Not availableb

1976 2.8E+02

1977 5.7E+01

1978 5.7E+00

1979 1.1E+01

1980 1.1E+01

1981-2003 Not availableb

a. Based on estimated average ratio of 

plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12

yr/m3. 

b. Source term estimates or measured air 

concentrations not available during 

these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 77 of 96

Table 4C-7. Estimated 

average air concentrations for 

234U for TA-10 (pCi/m3).a

Year 234U

1943 Not availableb

1944 2.2E-02

1945 2.2E-02

1946 6.6E-02

1947 8.8E-02

1948 1.3E-01

1949 2.2E-01

1950 1.1E+00

1951 4.4E-01

1952 4.4E-01

1953 4.4E-01

1954 8.8E-03

1955 7.3E-02

1956 7.7E-02

1957 2.4E-02

1958 1.5E-02

1959 2.6E-02

1960 1.5E-02

1961 1.9E+00

1962 4.0E-01

1963 1.1E-01

1964-2003 Not availableb

a. Based on estimated average 

ratio of plutonium activity:source 

emission activity for TA-3 and 

TA-21 of 2.2 × 10-12 yr/m3

. 

b. Source term estimates or 

measured air concentrations not 

available during these years. 

Table 4C-8. Estimated average air concentrations for 

241Am, 3H, 239Pu, and 234U for TA-11 (pCi/m3

).a

Year 241Am 3H

239Pu 234U

1943-1970 Not availableb

1971 4.2E+01 4.7E-05 1.4E-04

1972 3.3E-05 2.4E+01 4.8E-05 9.3E-05

1973 1.3E+01 2.3E-05 1.6E-04

1974-2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-3, averaged over results reported at 

locations within the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not 

available during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 78 of 96

Table 4C-9. Estimated average air concentrations for 

241Am, 3H, 239Pu, 232Th, and 234U for TA-15 (pCi/m3

).a

Year 241Am 3H

239Pu 232Th 234U

1944 1.3E-01b

1945 2.6E-01b

1946 5.3E-01b

1947 7.9E-01b

1948 1.2E+00b

1949 1.9E+00b

1950 9.9E+00b

1951 4.4E+00b

1952 4.0E+00b

1953 3.5E+00b

1954 3.3E+00b

1955 2.6E+00b

1956 1.7E+00b

1957 2.6E+00b

1958 2.4E+00b

1959 1.1E+00b

1960 1.6E+00b

1961 7.7E-01b

1962 1.0E+00b

1963 8.7E-01b

1964 1.3E+00b

1965 1.3E+00b

1966 2.1E+00b

1967 7.9E+03b4.4E+03b1.6E+00b

1968 9.9E+03b4.4E+03b1.2E+00b

1969 9.9E+03b9.4E-01b

1970 6.3E+04b6.8E-01b

1971 8.2E+01 4.2E-05 7.0E-04

1972 2.2E-05 2.8E+01 5.1E-05 9.3E-05

1973 2.0E-06 2.1E+01 1.6E-05 3.1E-04

1974-1977 Not availablec

1978 1.6E+02b

1979-1991 Not availablec

1992 5.0E-03b

1993 1.1E+00 1.1E-02b

1994 2.0E+00 4.0E-07 6.7E-05

1995 5.1E-06 1.8E+00 3.7E-06 1.4E-05

1996 2.3E-06 1.1E+00 1.4E-06 5.2E-05

1997 2.0E-06 1.9E+00 6.5E-07 2.9E-05

1998 2.2E-06 2.1E+00 8.0E-07 1.4E-05

1999 2.3E-06 1.7E+00 8.0E-07 1.9E-05

2000 4.0E-07 1.8E+00 5.0E-08 2.7E-05

2001 2.5E-07 2.3E+00 0.0E+00 6.6E-05

2002 2.0E-08 2.8E+00 0.0E+00 3.8E-05

2003 Not availablec

a. From AIRNET database of summarized measured concentrations for TA-15, 

averaged over results reported at locations within the TA (LANL 2003), 

unless otherwise indicated. 

b. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 

c. Source term estimates or measured air concentrations not available during 

these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 79 of 96

Table 4C-10. Estimated average air concentrations for 

241Am, 3H, 131I, 239Pu, and 234U for TA-16 (pCi/m3

).a

Year 241Am 3H

131I239Pu 234U

1943-1953 Not availableb

1954 8.4E-02c

1955

1956

1957 3.1E-02c

1958

1959 2.2E-03c

1960 1.1E-01c

1961

1962

1963 1.1E-01c

1964 6.6E-03c

1965 8.8E-03c

1966

1967 1.1E-02c

1968 8.6E-02c

1969 6.6E-03c

1970 2.4E-02c

1971 4.5E+01 1.0E-02 6.1E-05 3.2E-04

1972 4.0E-05 3.1E+01 5.7E-05 9.3E-05

1973 3.0E-06 1.6E+01 2.8E-05 1.6E-04

1974 1.2E+01 3.0E-05 1.1E-04

1975 4.0E-06 1.8E+01 1.9E-05 4.0E-05

1976 2.0E+01 4.7E-06 5.4E-05

1977 0.0E+00 3.0E+01 1.9E-05 4.3E-04

1978 0.0E+00 6.0E+00 3.6E-05 7.4E-05

1979 0.0E+00 2.2E+00 2.0E-05 4.0E-05

1980 0.0E+00 1.1E+01 1.1E-06 4.7E-05

1981 1.9E-06 1.9E+00 3.6E-06 3.6E-05

1982 3.0E-07 1.0E+01 1.0E-06 3.6E-05

1983 1.1E+01 5.5E-07 3.6E-05

1984 1.3E+01 0.0E+00 2.0E-05

1985 9.5E+00 3.9E-06 4.3E-05

1986 2.7E-06 4.7E+00 6.0E-07 2.1E-05

1987 1.0E-06 9.9E+00 7.5E-07 2.9E-05

1988 1.9E-06 4.3E+00 8.5E-07 5.3E-05

1989 2.4E-06 2.7E+00 6.0E-07 9.1E-05

1990 2.8E-06 1.1E+00 1.6E-06 5.2E-05

1991 1.2E-06 5.0E-01 1.0E-06 6.1E-05

1992 1.1E-06 1.6E+00 6.0E-06 2.8E-05

1993 9.0E-01 5.0E-07 1.9E-05

1994 9.1E+00 0.0E+00 2.6E-05

1995 4.6E-06 1.8E+02 3.3E-06 1.9E-05

1996 1.8E-06 2.4E+01 4.0E-07 2.7E-05

1997 2.2E-06 6.2E+01 8.0E-07 1.9E-05

1998 2.6E-06 2.5E+02 9.0E-07 2.9E-05

1999 3.2E-06 5.5E+01 1.2E-06 1.5E-05

2000 0.0E+00 6.1E+01 0.0E+00 1.4E-05

2001 2.0E-07 6.8E+01 0.0E+00 1.9E-05

2002-2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA16, averaged over results reported at locations within the TA (LANL 

2003), unless otherwise indicated. 

b. Source term estimates or measured air concentrations not available 

during these years. 

c. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 80 of 96

Table 4C-11. Estimated average 

estimated air concentrations for 234U 

for TA-18 (pCi/m).a

Year 234U

1943-1978 Not availableb

1979 8.7E-06

1980-2003 Not availableb

a. Based on estimated average ratio of 

plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-

12 yr/m3. 

b. Source term estimates or measured air 

concentrations not available during 

these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 81 of 96

Table 4C-12. Estimated average air concentrations for 

241Am, 3H, 131I, 239Pu, 234U, and MFP for TA-21 (pCi/m3

).a

Year 241Am 3H

131I239Pu 234U MFP,b

1943-1947 Not availablec

1948 3.4E-01d

1949 3.4E-01d

1950 4.1E-01d

1951 5.9E-02d

1952 1.3E-01d

1953 7.7E-02d

1954 4.8E-02d

1955 1.9E-01d

1956 1.7E-01d

1957 1.6E-01d

1958 1.8E-01d

1959 4.1E-01d

1960 7.8E-02d

1961 1.4E-02d

1962 1.8E-02d1.4E-02d

1963 6.3E-02d6.7E-02d

1964 2.7E-02d5.1E-03d

1965 2.0E-02d2.0E-02d

1966 2.3E-02d2.2E-02d

1967 2.2E-02d1.5E-02d

1968 4.3E-03d2.9E-03d

1969 9.2E-03d7.8E-03d

1970 6.2E-03d2.3E-03d

1971 8.5E+01 2.9E-05 1.2E-04

1972 3.6E+01 8.4E-05 1.1E-04

1973 1.5E+02 2.3E-05 1.6E-04 2.2E-06d

1974 6.8E+01 2.4E-05 7.8E-05 6.4E-06d

1975 6.4E+01 1.8E-05 4.8E-05 3.2E-06d

1976 4.0E+01 7.6E-06 6.5E-05 1.2E-06d

1977 5.2E+01 2.1E-05 1.5E-04 7.2E-06d

1978 7.5E-08d2.3E+01 2.3E-05 1.5E-04 2.3E-06d

1979 4.2E-08d3.8E+00 6.1E-06 1.3E-04 1.0E-06d

1980 1.3E-07d1.1E+01 3.1E-05 1.1E-04 9.2E-06d

1981 6.4E-08d5.6E+00 4.6E-06 5.6E-05 6.2E-06d

1982 7.7E-08d1.6E+01 6.0E-06 1.5E-04 9.6E-07d

1983 2.1E-07d2.0E+01 9.0E-07 4.8E-05 1.7E-06d

1984 8.8E+00 1.5E-06 1.0E-04 6.9E-07d

1985 1.6E+01 4.0E-07 6.6E-05 7.9E-07d

1986 1.6E+01 1.4E-06 5.4E-05 7.1E-07d

1987 5.2E+01 1.1E-06 5.4E-05 4.1E-07d

1988 4.0E+01 8.0E-07 8.1E-05 3.4E-07d

1989 1.7E+01 1.3E-06 1.3E-04 6.8E-08d

1990 1.3E+01 2.2E-06 7.6E-05 2.9E-08d

1991 0.0E+00 8.5E+00 1.9E-06 8.4E-05 6.6E-08d

1992 2.7E-06 9.4E+00 1.0E+00 2.5E-06 3.8E-05 5.3E-08d

1993 3.6E-06 4.2E+00 4.9E-06 2.8E-05 2.2E-08d

1994 6.4E-06 3.4E+00 6.6E-06 2.8E-05 1.1E-07d

1995 6.2E-06 8.0E+00 1.2E-05 3.2E-05

1996 4.2E-06 3.1E+00 1.7E-05 2.5E-04

1997 4.3E-06 4.8E+00 1.7E-05 2.1E-05

1998 5.6E-06 1.1E+01 2.6E-05 1.6E-05

1999 2.9E-06 6.1E+00 3.5E-06 2.2E-05

2000 9.3E-07 7.3E+00 3.7E-06 2.0E-05

2001 0.0E+00 7.2E+00 3.7E-06 2.6E-05

2002-2003 Not availablec

a. From AIRNET database of summarized measured concentrations for TA-21, averaged 

over results reported at locations within the TA (LANL 2003), unless otherwise indicated. 

b. MFP – Mixed Fission Products.

c. Source term estimates or measured air concentrations not available during these 

years. 

d. Based on estimated average ratio of plutonium activity:source emission activity for TA-21 

of 2.28 × 10-12 yr/m3. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 82 of 96

Table 4C-13. Estimated average air concentrations for 241Am, 

3H, 131I, 239Pu, and 234U for TA-33 (pCi/m3

).a

Year 241Am 3H

131I239Pu 234U

1943-1965 Not availableb

1966 2.2E-02c

1967-1870 Not availableb

1971 5.0E+02 1.0E-02 8.3E-05 1.2E-04

1972 1.8E+02 5.5E-05 1.4E-04

1973 6.0E+01 1.7E-05 3.1E-04

1974 1.4E+02 2.8E-05 1.1E-04

1975 1.6E+02 2.3E-05 3.9E-05

1976 5.9E+01 5.3E-06 6.4E-05

1977 8.0E+00 1.8E-05 1.2E-04

1978 2.5E+01 2.8E-05 9.5E-05

1979 4.0E+01 6.9E-06 6.0E-05

1980 4.4E+01 3.5E-06 7.0E-05

1981 3.0E+01 3.9E-06 5.6E-05

1982 8.8E+01 2.4E-06 5.7E-05

1983 3.6E+01 0.0E+00 3.3E-05

1984 5.6E+01 7.0E-06 2.8E-05

1985 1.1E+02 0.0E+00 3.0E-05

1986 3.1E+01 6.0E-07 2.2E-05

1987 2.0E+01 8.0E-07 5.1E-05

1988 5.8E+01 4.0E-07 1.5E-04

1989 1.8E+01 0.0E+00 8.2E-05

1990 7.9E+00 7.3E-06 8.7E-05

1991 3.2E+00 7.0E-07 1.9E-05

1992 3.7E+00 9.0E-07 1.5E-05

1993 3.0E+00 1.8E-06 1.6E-05

1994 1.8E+00 5.0E-07 1.5E-05

1995 3.9E-06 3.5E+00 1.5E-05 1.7E-05

1996 1.4E+00

1997 3.1E-06 9.0E-01 1.4E-06 1.3E-05

1998 2.4E-06 1.3E+00 1.4E-06 1.5E-05

1999 2.5E-06 4.0E+00 1.2E-06 2.0E-05

2000 0.0E+00 3.4E+00 2.0E-07 1.1E-05

2001 3.3E+00 0.0E+00 1.4E-05

2002-2003

a. From AIRNET database of summarized measured concentrations for 

TA-33, averaged over results reported at locations within the TA (LANL 

2003), unless otherwise indicated.

b. Source term estimates or measured air concentrations not available 

during these years. 

c. Based on estimated average ratio of plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3

. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 83 of 96

Table 4C-14. Estimated average air concentrations for 241Am, 3H, 239Pu, 

234U, MFP, and P/VAP for TA-35 (pCi/m3

).a

Year 241Am 3H

239Pu 234U MFPb P/VAPb

1943-1966 Not availablec

1967 1.5E-05

1968 1.3E-05

1969 1.2E-05

1970 9.3E-06

1971 6.9E+03 1.6E-05

1972 5.5E+03 3.9E-05

1973 2.7E+03 5.2E-06

1974 3.1E+03 1.8E-05

1975 5.3E+03 1.3E-05

1976 3.7E+03 5.2E-06

1977 1.7E+03 1.8E-06

1978 1.5E+03 4.3E-06

1979 2.9E+03 1.6E-05

1980 5.5E+01 4.6E-07

1981 5.9E-07

1982 2.9E-06

1983 1.3E+01 2.0E-06

1984 4.5E+02 9.2E-07

1985 1.2E+01 1.2E-06

1986 1.0E+02 8.0E-07

1987 3.4E+02 1.4E-06

1988 2.6E+02 3.8E-07

1989 4.0E+01 1.5E-06

1990 8.8E-02 2.0E-06

1991 9.5E-06 2.7E-06

1992 2.2E-01 7.9E-07

1993 5.9E-07

1994 8.6E-07

1995 7.8E-08 6.5E-07 1.5E-06 3.6E-06 3.6E-06

1996-2003 Not availablec

a. Based on estimated average ratio of plutonium activity:source emission activity for 

TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 

b. MFP – Mixed Fission Products; P/VAP = Particulate and Vapor Activation Products 

c. Source term estimates or measured air concentrations not available during these 

years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 84 of 96

Table 4C-15. Estimated average air concentrations 

for 241Am, 3H, 239Pu, and 234U for TA-36 (pCi/m3).a

Year 241Am 3H

239Pu 234U

1943-1957 Not availableb

1958 9.5E-02c

1959 1.8E-02c

1960 3.1E-02c

1961 Not availableb

1962 2.2E-02c

1963 3.1E-02c

1964 8.8E-03c

1965 4.4E-02c

1966 6.2E-02c

1967 1.1E-01c

1968 5.9E-02c

1969 4.2E-02c

1970 1.3E-02c

1971 3.8E+01 2.7E-05 9.5E-02

1972 2.9E+01 5.7E-05 1.8E-02

1973 2.9E+01 2.2E-05 3.1E-02

1974-1992 Not availableb

1993 1.1E+00

1994 1.3E+00 1.2E-05 7.0E-05

1995 4.6E-06 3.7E+00 1.1E-05 9.0E-05

1996 1.5E-06 1.1E+00 8.0E-07 4.9E-05

1997 2.0E-06 1.4E+00 6.5E-07 3.8E-05

1998 2.1E-06 1.8E+00 2.5E-07 3.5E-05

1999 3.6E-06 1.7E+00 4.5E-07 3.5E-05

2000 5.0E-07 1.6E+00 1.5E-07 3.3E-05

2001 0.0E+00 2.5E+00 0.0E+00 1.5E-04

2002 2.0E-08 2.8E+00 0.0E+00 3.8E-05

2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-36, averaged over results reported at 

locations within the TA (LANL 2003), unless otherwise 

indicated. 

b. Source term estimates or measured air concentrations not 

available during these years. 

c. Based on estimated average ratio of plutonium 

activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3

. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 85 of 96

Table 4C-16. Estimated average air 

concentrations for 3H, 239Pu, and 234U for 

TA-39 (pCi/m3).a

Year 3H

239Pu 234U

1943-1953 Not availableb

1954 4.2E-01c

1955 3.3E-01c

1956 3.8E-01c

1957 5.9E-01c

1958 6.3E-01c

1959 4.2E-01c

1960 2.6E-01c

1961 3.6E-01c

1962 3.6E-01c

1963 2.8E-01c

1964 2.5E-01c

1965 2.4E-01

c

1966 2.7E-01c

1967 4.4E-01c

1968 1.1E-01c

1969 1.5E-01c

1970 1.1E-01c

1971 1.9E-01c

1972 2.4E-01c

1973-1976 Not availableb

1977 3.9E+01 1.0E-07 1.2E-04

1978 1.5E+01 3.5E-05 1.3E-04

1979 1.6E+01 3.7E-06 4.0E-05

1980 2.8E+01 4.4E-06 7.3E-05

1981 1.2E+01 2.0E-06 4.8E-05

1982 1.5E+02 2.7E-06 8.4E-05

1983 3.1E+01 1.8E-06 1.6E-05

1984 1.4E+01 0.0E+00 3.6E-05

1985 4.2E+01 0.0E+00 5.1E-05

1986 2.5E+01 1.5E-06 3.0E-05

1987-2003 Not availableb

a. From AIRNET database of summarized 

measured concentrations for TA-39, averaged 

over results reported at locations within the TA 

(LANL 2003), unless otherwise indicated. 

b. Source term estimates or measured air 

concentrations not available during these 

years. 

c. Based on estimated average ratio of plutonium 

activity:source emission activity for TA-3 and 

TA-21 of 2.2 × 10-12 yr/m3

. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 86 of 96

Table 4C-17. Estimated average air 

concentrations for 3H, Pu, and U for TA-41 

(pCi/m3).a

Year 3H

239Pu 234U

1943-1966 Not availableb

1967 2.64E-04

1968 7.26E-05

1969 1.98E-05

1970 1.72E-05

1971 7.0E+02 4.18E-05

1972 2.4E+02 2.42E-05

1973 1.3E+02 3.34E-06

1974-1978 Not availableb

1979 3.1E+02

1980 9.1E+02

1981 2.8E+02

1982 2.9E+02

1983 2.1E+03

1984 1.1E+04

1985 2.8E+03

1986 2.9E+03

1987 1.0E+03

1988 3.8E+03

1989 2.6E+04

1990 9.8E+03

1991 8.4E+03

1992 6.4E+02

1993 1.1E+03 2.2E-08

1994 3.8E+02 4.4E-08

1995 1.7E+02 3.4E-08 2.0E-08

1996 2.4E+02

1997 9.2E+01

1998 7.9E+01

1999 2.9E+01

2000 1.4E+01

2001 1.2E+03

2002-2003 Not availableb

a. Based on estimated average ratio of plutonium 

activity:source emission activity for TA-3 and TA21 of 2.2 × 10-12 yr/m3

. 

b. Source term estimates or measured air 

concentrations not available during these years.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 87 of 96

Table 4C-18. Estimated average air 

concentrations for 239Pu for TA-42 

(pCi/m3).a

Year 239Pu

1943-1968 Not availableb

1969 1.8E-03

1970-2003 Not availableb

a. Based on estimated average ratio of 

plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12

yr/m3. 

b. Source term estimates or measured air 

concentrations not available during 

these years. 

Table 4C-19. Estimated average air concentrations 

for 241Am , 3H, 239Pu, and 234U for TA-43 (pCi/m3).a

Year 241Am 3H

239Pu 234U

1943-1971 Not availableb

1971 4.3E+01 1.1E-04 2.2E-04

1972 2.8E+01 1.0E-04 9.3E-05

1973 1.4E+01 5.2E-05 1.6E-04

1974 1.5E-05c

1975 3.6E-06c

1976 1.7E-05c

1977 1.0E-05c

1978 3.4E-06c

1979 1.7E-06c

1980 4.0E-07c

1981 8.1E-07c

1982 3.1E-06

1983 7.3E-06c

1984 2.3E-06c

1985 4.0E-06c

1986 6.4E-06c

1987 1.1E-06c

1988 3.2E-06c

1989-1994 Not availableb

1995 5.9E-07c1.2E-06c2.5E-06c

1996-2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-43, averaged over results reported at 

locations in the TA (LANL 2003), unless otherwise 

indicated. 

b. Source term estimates or measured air concentrations not 

available during these years. 

c. Based on estimated average ratio of plutonium 

activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3

. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 88 of 96

Table 4C-20. Estimated average air 

concentrations for 234U for TA-46 

(pCi/m3).a

Year 234U

1943-1970 Not availableb

1971 8.8E-06

1972 2.6E-04

1973 4.8E-06

1974 9.0E-07

1975 1.1E-06

1976 6.8E-07

1977 8.8E-09

1978 5.6E-05

1979 5.0E-06

1980 3.3E-06

1981 3.0E-05

1982 4.5E-06

1983 7.9E-08

1984 1.1E-07

1985 6.2E-08

1986 8.8E-09

1987-2003 Not availableb

a. Based on estimated average ratio of 

plutonium activity:source emission 

activity for TA-3 and TA-21 of 2.2 × 10-12

yr/m3, unless otherwise indicated. 

b. Source term estimates or measured air 

concentrations not available during 

these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 89 of 96

Table 4C-21. Estimated average air concentrations for 

241Am , 239Pu, 234U, MFP, and P/VAP for TA-48 (pCi/m3

).a

Year 241Am 239Pu 234U MFPb P/VAPb

1943-1966 Not availablec

1967 2.4E-04

1968 3.3E-04

1969 2.9E-04

1970 1.3E-04

1971 4.2E-05

1972 2.5E-04 1.8E-05

1973 4.4E-05 4.3E-06 2.2E-03

1974 5.3E-05 2.8E-06 2.1E-03

1975 2.7E-05 7.6E-06 1.6E-03

1976 1.1E-05 2.5E-04 2.7E-03

1977 1.8E-05 1.2E-04 4.8E-03

1978 4.2E-06 2.5E-05 2.6E-03

1979 7.4E-07 2.4E-05 2.4E-03

1980 3.5E-06 1.5E-06 3.9E-03

1981 2.9E-06 5.1E-06 3.0E-03

1982 2.2E-05 1.6E-05 2.4E-03

1983 7.3E-06 1.1E-06 1.8E-03

1984 5.6E-06 2.9E-06 3.5E-03

1985 4.6E-06 4.2E-06 2.7E-03

1986 6.3E-06 1.3E-06 5.5E-03

1987 1.4E-06 3.5E-06 2.8E-03

1988 1.6E-06 4.8E-07 2.4E-03

1989 3.3E-06 5.9E-07 9.6E-01

1990 3.3E-06 3.7E-07 2.3E-03

1991 1.3E-06 2.4E-03 2.2E-01

1992 1.5E-05 9.2E-07 6.0E-03 8.3E-02

1993 7.0E-06 3.1E-06 3.0E-03 1.7E-01

1994 7.1E-06 8.8E-07 8.6E-04 1.8E-01

1995 3.8E-06 6.8E-06 1.2E-06 5.8E-02 5.8E-02

1996 1.1E-08 2.4E-08 2.2E-04

1997 7.9E-10 5.5E-09 3.1E-07 4.0E-03

1998 8.1E-10 2.4E-04

1999 1.3E-09 8.6E-03

2000 3.7E-02

2001 5.1E-03

200-2003 Not availablec

a. Based on estimated average ratio of plutonium activity:source 

emission activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 

b. MFP – Mixed Fission Products; P/VAP = Particulate and Vapor 

Activation Products 

c. Source term estimates or measured air concentrations not available 

during these years.
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 90 of 96

Table 4C-22. Estimated average air concentrations for 241Am, 

3H, 131I, 239Pu, and 234U for TA-49 (pCi/m3

).a

Year 241Am 3H

131I239Pu 234U

1943-1970 Not availableb

1971 1.5E+02 1.0E-02 8.4E-05 3.7E-04

1972 2.1E+01 7.6E-05 1.9E-04

1973 3.2E+01 1.9E-05 1.6E-04

1974 2.2E+01 3.2E-05 1.4E-04

1975 1.0E-06 2.1E+01 2.1E-05 4.2E-05

1976 2.2E+01 4.3E-06 8.4E-05

1977 0.0E+00 1.2E+01 1.6E-05 1.7E-04

1978 0.0E+00 5.0E+00 2.6E-05 9.5E-05

1979 0.0E+00 5.4E+00 4.6E-06 6.4E-05

1980 2.2E-06 2.1E+00 6.4E-06 5.9E-05

1981 9.0E-07 4.4E+00 5.9E-06 5.1E-05

1982 0.0E+00 6.9E+00 1.8E-06 7.4E-05

1983 1.1E+01 1.0E-07 1.0E-05

1984 1.3E+01 8.0E-07 2.5E-05

1985 3.6E+01 5.2E-06 3.9E-05

1986 2.5E+00 1.0E-06 3.2E-05

1987 1.2E-06 1.8E+01 6.0E-07 3.1E-05

1988 6.6E-06 9.6E+00 7.0E-07 4.6E-05

1989 2.6E+00 0.0E+00 6.9E-05

1990 1.7E-06 1.1E+00 8.0E-07 4.2E-05

1991 1.1E-06 9.0E-01 1.7E-06 3.6E-05

1992 5.0E-07 1.6E+00 1.3E-05 5.1E-05

1993 1.5E-06 2.4E+00 2.8E-06 3.4E-05

1994 4.6E-06 1.5E+00 2.6E-06 2.1E-05

1995 3.4E-06 2.2E+00 3.1E-06 1.9E-05

1996 4.8E-06 1.7E+00 5.2E-06 2.4E-05

1997 2.1E-06 3.5E+00 6.0E-07 8.6E-06

1998 3.2E-06 6.7E+00 1.3E-06 1.8E-05

1999 2.8E-06 3.4E+00 4.5E-07 1.8E-05

2000 1.5E-05 3.6E+00 2.0E-07 1.3E-05

2001-2003 Not availableb

a. From AIRNET database of summarized measured concentrations for TA-49, 

averaged over results reported at locations in the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not available during 

these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 91 of 96

Table 4C-23. Estimated average air concentrations for 241Am, 

3H, 131I, 239Pu, 232Th, 

234U, and MFP for TA-50 (pCi/m3

).a

Year 241Am 3H

131I239Pu 232Th 234U MFPb

1943-1966 Not availablec

1967 2.2E-04d

1968 1.5E-04d

1969 9.2E-05d

1970 4.5E-05d

1971 6.3E+02 1.0E-02 3.5E-05d

1972 6.0E-05d

1973 5.5E-06d3.8E-05d

1974 8.6E-06d2.1E-04d

1975 9.0E-06d1.0E-04d

1976 2.4E-06d6.5E-05d

1977 1.5E-04d2.0E-04d

1978 3.8E-05d9.5E-05d

1979 6.4E-06d2.5E-05d

1980 2.6E-06d2.0E-05d

1981 3.9E-06d5.8E-05

1982 1.4E-05d3.5E-05d

1983 1.2E-05d2.2E-05

1984 8.1E-06d2.1E-05d

1985 4.4E-06d2.0E-05d

1986 6.3E-06d4.8E-05d

1987 9.9E-06d5.1E-05d

1988 4.5E-06d3.3E-05d

1989 1.0E-06d2.3E-05d

1990 3.3E-07d9.3E-06d

1991 3.0E-06d7.4E-06d

1992 1.2E-06d8.5E-06d

1993 6.2E-07d8.9E-06d

1994 6.8E-07d1.6E-05d

1995 1.4E-07d1.6E-06d

1996 2.4E-08d9.2E-08d4.2E-07d

1997 1.8E-08d1.2E-07d2.9E-09d

1998 1.4E-08d3.3E-08d1.7E-07d4.2E-07d

1999 2.9E-07d1.1E-07d8.1E-08d4.2E-08d

2000 2.2E-08d1.2E-07d

2001 1.3E-10d9.5E-08d

2002-2003 Not availablec

a. From AIRNET database of summarized measured concentrations for TA-50, averaged over results 

reported at locations in the TA (LANL 2003), unless otherwise noted. 

b. 2.2MFP – Mixed Fission Products. 

c. Source term estimates or measured air concentrations not available during these years. 

d. Based on estimated average ratio of plutonium activity:source emission activity for TA-3 and TA-21 of 

2.2 × 10-12 yr/m3. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 92 of 96

Table 4C-24. Estimated average air concentrations for 241Am, 3H, 131I, 

239Pu, 234U, and P/VAP for TA-53 (pCi/m3

).a

Year 241Am 3H

131I239Pu 234U P/VAPb

1943-1970 Not availablec

1971 7.9E+01 6.6E-05 2.5E-04

1972 4.4E-05 3.3E+01 6.4E-05 1.1E-04

1973 2.0E-06 3.2E+01 2.5E-05 1.6E-04

1974 9.8E+01 3.1E-05 1.7E-04

1975 3.0E-06 7.1E+01 2.3E-05 8.2E-05

1976 4.9E+01 5.0E-06 9.6E-05

1977 1.2E-06 3.5E+01 1.8E-05 1.7E-04

1978 0.0E+00 1.3E+01 1.7E-05 6.2E-05

1979 0.0E+00 4.3E+00 4.9E-06 1.2E-04

1980 9.0E-07 6.2E+00 7.2E-06 1.3E-04

1981 1.3E-06 5.4E+00 6.3E-06 4.0E-05

1982 1.0E-07 7.3E+00 2.2E-06 8.2E-05 4.0E+02d

1983 1.1E+01 1.0E-06 3.9E-05 5.8E+03d

1984 8.9E+00 6.0E-07 5.1E-05 5.5E+03d

1985 1.2E+01 1.2E-06 4.2E-05 4.4E-01d

1986 3.0E-06 9.6E+00 8.0E-07 4.8E-05 2.2E-01d

1987 8.0E-07 1.5E+01 4.0E-07 4.7E-05 4.4E-01d

1988 2.1E-06 2.4E+01 2.3E-06 8.9E-05 2.2E-01d

1989 3.3E-06 3.4E+00 1.0E-06 1.1E-04 2.2E-01d

1990 2.2E-06 3.9E+00 2.4E-06 1.1E-04 1.8E-01d

1991 7.0E-07 1.1E+00 3.0E-06 6.1E-05 4.4E-01d

1992 1.8E-06 4.9E+00 2.5E-06 7.8E-05 1.6E+00d

1993 3.7E-06 2.4E+00 1.4E-06 1.9E-05 2.2E+01d

1994 3.9E-06 1.9E+00 2.5E-06 2.1E-05 6.9E-01d

1995 6.1E-06 2.7E+00 1.1E-05 1.8E-05 6.3E-01d

1996 8.0E-01 7.7E-04d3.1E-01d

1997 3.7E+01d2.0E+00d

1998 8.4E+00d7.3E+00d

1999 5.1E+00d5.5E-03d

2000 6.4E+00d2.0E+00d

2001 1.4E+01 2.4E+00d

2002-2003 Not availablec

a. From AIRNET database of summarized measured concentrations for TA-53, 

averaged over results reported at locations in the TA (LANL 2003), unless otherwise 

indicated. 

b. MFP – Mixed Fission Products; P/VAP = Particulate and Vapor Activation Products. 

c. Source term estimates or measured air concentrations not available during these 

years. 

d. Based on estimated average ratio of plutonium activity:source emission activity for 

TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 93 of 96

Table 4C-25. Estimated average air concentrations 

for 241Am, 3H, 239Pu, and 234U for TA-54 (pCi/m3).a

Year 241Am 3H

239Pu 234U

1943-1975 Not availableb

1976 3.3E+02 3.1E-05 1.7E-04

1977 5.2E-06 1.9E+02 3.6E-05 2.6E-04

1978 2.2E-06 5.7E+01 8.3E-05 1.6E-04

1979 5.0E-06 3.5E+01 2.3E-05 1.2E-04

1980 4.2E-06 5.3E+01 1.4E-05 1.4E-04

1981 1.6E-06 2.2E+01 1.1E-05 1.3E-04

1982 9.0E-07 2.3E+01 1.4E-05 1.3E-04

1983 1.8E+01 7.0E-07 4.7E-05

1984 6.3E+01 1.8E-05 1.0E-04

1985 7.6E+01 2.4E-05 9.9E-05

1986 1.8E-05 2.8E+01 2.3E-05 9.5E-05

1987 9.5E-06 3.2E+01 1.4E-05 8.3E-05

1988 3.8E-06 2.3E+01 1.8E-05 2.5E-04

1989 8.9E-06 2.9E+01 1.7E-05 1.4E-04

1990 3.2E-06 1.6E+01 4.8E-06 8.1E-05

1991 4.1E-06 8.1E+01 1.8E-05 9.5E-05

1992 1.9E-06 4.4E+01 4.9E-06 3.2E-05

1993 3.8E-06 3.9E+01 8.0E-06 3.5E-05

1994 6.3E-06 3.3E+01 7.1E-06 9.9E-05

1995 1.4E-05 4.4E+01 1.8E-05 5.8E-05

1996 6.3E-05 5.1E+01 8.5E-05 5.6E-05

1997 9.7E-05 8.4E+01 1.5E-04 6.2E-05

1998 1.5E-05 1.3E+02 2.3E-05 7.6E-05

1999 1.6E-05 1.0E+02 2.4E-05 1.2E-04

2000 1.3E-05 1.2E+02 1.0E-05 8.5E-05

2001 1.0E-05 2.3E+02 5.9E-06 5.9E-05

2002 5.2E-05 1.2E+02 1.0E-04 6.0E-05

2003 Not availableb

a. From AIRNET database of summarized measured 

concentrations for TA-54, averaged over results reported 

at locations in the TA (LANL 2003). 

b. Source term estimates or measured air concentrations not 

available during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 94 of 96

Table 4C-26. Estimated average air concentrations for 241Am, 

3H, 239Pu, 232Th, and 234U for TA-55 (pCi/m3

).a

Year 241Am 3H

239Pu 232Th 234U

1943-1977 Not availableb

1978 8.8E-07

1979 2.4E-07

1980 6.5E-07

1981 2.1E-07

1982 4.1E+01 5.7E-06

1983 9.7E+01 2.4E-06

1984 3.3E+02 2.3E-06

1985 2.4E-06

1986 2.2E+03 5.1E-07

1987 1.9E+02 5.4E-07

1988 6.9E+02 3.4E-05

1989 5.9E+02 4.9E-06

1990 3.7E+02 1.0E-06

1991 2.0E+02 4.4E-06

1992 2.2E+02 2.5E-06

1993 1.4E+02 3.7E-07

1994 5.0E+01 2.6E-07

1995 1.2E-08 3.4E+01 3.6E-08

1996 6.8E-08 6.8E+01 1.9E-07 1.2E-07

1997 2.6E+01 2.4E-07 9.7E-08

1998 8.4E-09 2.6E+01 1.4E-07 6.6E-08

1999 1.2E-07 4.0E+00 1.4E-07 1.6E-07

2000 7.3E-07 1.4E+01 5.5E-06

2001 1.4E-08 7.3E+00 9.5E-08 3.3E-07 3.7E-07

2002-2003 Not availableb

a. Based on estimated average ratio of plutonium activity:source 

emission activity for TA-3 and TA-21 of 2.2 × 10-12 yr/m3. 

b. Source term estimates or measured air concentrations not available 

during these years. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 95 of 96

Table 4D-1. Estimated average annual 

air concentrations of 41Ar for TA-2 

(uCi/m3).a

Year 41Ar

1944-1966 No emissions data available

1967 1.13E-02

1968 4.73E-03

1969 1.31E-03

1970 9.48E-04

1971 1.14E-03

1972 4.67E-04

1973 1.99E-04

1974 2.28E-06

1975 1.73E-04

1976 2.47E-04

1977 2.30E-04

1978 1.74E-04

1979 2.56E-04

1980 3.74E-04

1981 2.19E-04

1982 2.49E-04

1983 3.05E-04

1984 2.44E-04

1985 2.84E-04

1986 2.01E-04

1987 1.69E-04

1988 1.93E-04

1989 1.62E-04

1990 1.17E-04

1991 1.48E-04

1992 1.02E-04

1993-2003 Reactors not in operation

a. Receptor assumed to be at 500 m from 

ground-level release point. 
Effective Date: 10/08/2004 Revision No. 00 Document No. ORAUT-TKBS-0010-4 Page 96 of 96

Table 4D-2. Estimated average annual air 

concentrations of gaseous/mixed activation 

products for TA-53, TA-21, and TA-72 (uCi/m3). 

Year TA-53aTA-21bTA-72c

1943-1975 LANSCE not in operation

1976 4.30E-03 2.37E-04 7.10E-04

1977 3.47E-02 1.91E-03 5.73E-03

1978 8.53E-02 4.70E-03 1.41E-02

1979 8.68E-02 4.78E-03 1.43E-02

1980 1.06E-01 5.86E-03 1.76E-02

1981 2.57E-01 1.42E-02 4.25E-02

1982 1.83E-01 1.01E-02 3.02E-02

1983 3.36E-01 1.85E-02 5.55E-02

1984 5.35E-01 2.95E-02 8.84E-02

1985 9.19E-02 5.06E-03 1.52E-02

1986 8.17E-02 4.50E-03 1.35E-02

1987 1.09E-01 6.02E-03 1.81E-02

1988 8.82E-02 4.86E-03 1.46E-02

1989 1.14E-01 6.27E-03 1.88E-02

1990 8.97E-02 4.94E-03 1.48E-02

1991 4.17E-02 2.30E-03 6.89E-03

1992 5.25E-02 2.89E-03 8.67E-03

1993 2.33E-02 1.29E-03 3.86E-03

1994 3.65E-02 2.01E-03 6.02E-03

1995 3.18E-02 1.75E-03 5.25E-03

1996 8.02E-03 4.42E-04 1.33E-03

1997 1.46E-02 8.03E-04 2.41E-03

1998 5.69E-03 3.13E-04 9.40E-04

1999 2.19E-04 1.20E-05 3.61E-05

2000 5.03E-04 2.77E-05 8.31E-05

2001 4.30E-03 2.37E-04 7.11E-04

2002

2003

a. Receptor assumed to be at 500 m from ground-level 

release point. 

b. Receptor assumed to be at 2,000 m from 30-m stack 

release height. 

c. Receptor assumed to be at 700 m from 30-m stack 

release height.