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Assessment of Potential for Radon

Exposure at ANL-E 

White Paper

National Institute for Occupational 

Safety and Health

September 30, 2019

Vincent A. King

Oak Ridge Associated Universities Team

Reviewed by Megan L. Lobaugh

Division of Compensation Analysis and Support

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

 

INTRODUCTION

During the June 27, 2018, Advisory Board on Radiation and Worker Health (ABRWH) Argonne 

National Laboratory-East (ANL-E) work group teleconference meeting regarding the current 

status of Sanford Cohen & Associates (SC&A) findings and observations against the ANL-E Site 

Profile [ORAUT 2006a to 2006e; SC&A 2009], the ABRWH requested additional information 

on radon sources and the potential for radon exposure at ANL-E (affiliated with 

Observation/Secondary Issue 4 in SC&A [2009]).

Observation 4 is entitled “Internal Dose to Workers from Radon Exposures is Not Considered” 

[SC&A 2009] and states since ANL-E handled 226Ra, 227Ac, and 230Th as part of the research and 

development, as well as other programs, there is a potential for exposure to radon (222Rn), 

actinon (219Rn), and thoron (220Rn), which is not thoroughly discussed in the Site Profile. 

Past discussions between SC&A and the National Institute for Occupational Safety and Health

(NIOSH), documented in the Board Review System and in SC&A memos, include more specific

information regarding Observation 4. A summary of this dialogue is provided here: 

NIOSH has not found any indication of routine worker monitoring for radon. Given that 

there are not large quantities of uranium or radium ore stored or handled at ANL-E, any 

radon exposure likely would have been minimal and secondary to other nuclide 

exposures (i.e., radium, actinium, and thorium). SC&A finds that there were 

opportunities for exposure to Ra-226, Ac-227, and thorium, according to the Site Profile, 

for ANL-E, therefore further investigation into occupational exposures to radon, thoron, 

and actinon are necessary. NIOSH has found indications that protective measures (e.g., 

radon traps in areas of radium work, use of ventilated hoods) and area air monitoring 

were implemented, even in early operations that had the potential for high radon 

exposures. SC&A asked about whether there is ANL-E bioassay data for radium and its 

decay products, which would indicate the potential exposure to radon. NIOSH found over 

800 bioassay samples for radium between 1949 and 1979, but the documentation is 

insufficient to know the process and workplace specific information (e.g., chemical and 

physical form, quantity) about what radium handling was done for each sample to know 

whether radon exposures would have been significant. But given the ANL-E policy of 

performing radiation work in fumehoods, glove boxes, and ventilated enclosures,1

NIOSH assumes that the occupational internal exposure from radon, actinon, and thoron 

(and their progeny) due to handling and use of these sources was minimal. 

1 Policy of air filtration where alpha contamination was possible is outlined in Fleury [1946]; Wing M of building 

200 required ventilation and use of hoods and gloveboxes [DOE 1982, PDF p. 32]; other routine reports in tables 

below verify implementation of these policies.
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

This white paper will further explore the assumption that occupational exposure to radon, 

actinon, and thoron was minimal by reviewing the potential sources of radon occupational 

exposure at ANL-E and the resulting exposure potential.

NOTE: This paper uses the term “radon” to discuss any isotope of radon and uses the specific 

isotopes for discussing specific exposures.

CURRENT ANL-E SITE PROFILE DISCUSSION OF RADON EXPOSURE AND 

ASSIGNMENT OF RADON DOSES

No radon (220Rn, 219Rn, or 222Rn) doses are assigned in the ANL-E Occupational Internal Dose 

technical basis document (TBD) [ORAUT 2006a]. This approach is based on the assumption that 

the work with radium, actinium, and thorium was performed in laboratories with engineered 

controls, like ventilation, gloveboxes, etc., and was a part of a routine workplace monitoring 

program that would have prevented routine occupational exposures to the gaseous daughter 

products. Due to the demonstrated storage and working approaches (i.e., known sources of radon 

were encapsulated and stored in unoccupied areas, work was performed in fumehoods), radon 

exposure would only have been feasible during transfer of material to laboratory locations. 

Records demonstrate control of and protection from exposure were accomplished by wrapping or 

sealing source materials to limit radon emanation and by use of respiratory protection by 

workers, minimizing such exposures [Rose 1949, PDF pp. 5, 17, 19; ANL 1953, PDF p. 10; 

Lonergan and Novak 1959, PDF p. 24; Lonergan and Novak 1963, PDF p. 168].

Radon (

220Rn) releases and emissions are noted in environmental monitoring at ANL-E starting 

in 1984 from specific buildings where specific operations were performed. Doses from these 

releases are assigned via the Occupational Environmental Dose TBD [ORAUT 2006b] as an 

environmental internal dose to workers in the 200 Area facilities at ANL-E and to workers 

whose work locations cannot be identified, as a claimant favorable assumption.

These environmental radon releases are associated with a specific program in which spent fuel 

rods with high quantities of 232Th were sheared, analyzed, and prepared for disposal in the M 

Wing of Building 200 [ORAUT 2006b]. This work was done in controlled-ventilated areas (i.e., 

hot cells, radiochemistry labs with fume hoods) [DOE 1982]. Due to the engineered controls and 

established routine monitoring, occupational exposure from the source material was controlled 

and off-normal events would have been detected. Exposure to radon (

220Rn) due to the emanation 

from this source material would have been controlled by the workplace controls in place for the 

source material. These activities, however, did result in 220Rn environmental releases through the 

high-efficiency participate air (HEPA)-filtered exhaust of the ventilation system from the M 

Wing of Building 200. These releases resulted in potential environmental exposures to 

individuals in nearby buildings in the 200 Area. Since this exposure pathway is already discussed 

in the Occupational Environmental Dose TBD, further assessment of exposures from this 

program will not be described in this document.
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

HISTORICAL BACKGROUND

The Metallurgical Laboratory (also called Met Lab) in Chicago was the direct predecessor to 

ANL-E, which began operations on July 1, 1946 [Hilberry 1949]. Although Met Lab facilities 

and operations are not covered by the ANL-E TBD [ORAUT 2006a], evaluation of records of 

Met Lab operations indicate familiarity with radon and radon progeny as a health risk, an 

interference with air and surface monitoring performed for other hazardous radionuclides (e.g., 

uranium and plutonium), and as an indicator to measure radium content in the body.

The Met Lab was involved in early biomedical research on human exposure to radium, including

radium watch dial painters and patients treated with radium, because it was “...concerned 

especially with protecting workers exposed to radiation...” [Holl et al. 1997, PDF p. 64]. 

Because this research was performed under laboratory conditions to evaluate radium in patients

who typically received the radium intakes from their workplace (i.e., radium watch dial painters) 

or medical procedures, it did not involve “free” quantities of radium large enough to represent a 

radon risk to researchers. The exposure route to researchers for this work would have been via 

the exhalation of radon from the study subjects. Rowland [1994] presented results for 2,403 

individuals for whom radium body burdens were determined. Of these results, 144 results (6%) 

were 1 μCi or greater and the largest derived body burden listed was 25 μCi. From ORAUTOTIB-0025, Estimation of Radium-226 Activity in the Body from Breath Radon-222 

Measurements [ORAUT 2005], the expected 222

Rn concentration in breath from an individual 

with a body burden of 25 μCi 226Ra is 100 pCi/l. This is coincidently the concentration of 222Rn 

considered equivalent to one working level (WL) of exposure for continuous exposure 

conditions. However, the concentration the worker would have been exposed to was reduced due 

to mixing with room air, and the total exposure time would have been short (on the order of 

hours or days), rather than continuous. Therefore, even assuming the highest potential exposure 

situation (i.e., working with the experimental subject with the highest body burden), there was no 

significant exposure to exhaled radon for laboratory personnel.

This early Met Lab research in radiation effects is noted here to illustrate the early development 

of techniques (e.g., radon breath analysis) for determining radium body burdens, which used 

radon measurement technologies. It is therefore reasonable to assume the relationship between 

radium, radon, and radon progeny was well understood and that monitoring techniques had been 

developed to detect and distinguish radon at low concentrations.

Other activities are described in the SEC-00135 Evaluation Report for the Met Lab, where 

radium research was performed in the Ryerson Physical Laboratory, Eckhart Hall, the Kent 

Chemical Laboratory, and the Jones Chemical Laboratory [Huntsinger et al. 1952; NIOSH 2008, 

PDF p. 10]. These were radiochemistry research facilities operated by the University of Chicago

where work with radium was performed in hoods and ventilated areas; therefore, significant 

radon quantities would not have been encountered by workers on a routine basis due to the 

engineered controls. This would also have been the case at Site B, a complex used by the 

Biology Division and which included “an animal facility where research involving the use of 

radionuclides, including transuranic nuclides, was conducted” [Huntsinger et al. 1952, PDF 

p. 290]. A 1946 memo describing waste disposal at the Chicago facilities also lists a potential 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

source of contaminated waste as animal carcasses “injected with radium and other radioactive 

materials” [Fleury 1946, PDF p. 3]. Animal carcasses would not have been a significant source 

of radon because the only significant pathway for radon emanation is exhalation (as described 

above for human exposures), which would have been nonexistent in an animal carcass. Since the 

radium intake would have been largely concentrated in bone tissues, radon created in that tissue 

would not have had time to migrate through intervening tissue before decay, and permeation 

through skin would also have been diminished in an animal carcass. Furthermore, worker contact 

times with animal carcasses in unventilated conditions would have been minimal due to aesthetic 

and hygienic considerations. 

Available records consistently indicate that work with radium at the Met Lab was conducted in 

laboratory settings. Radium sources were sealed or in sealed containers to prevent radon 

emanation [Rose 1949, PDF p. 17] and kept in non-occupied storage locations when not in use. 

In addition, charcoal filters (called radon traps) were used to absorb any radon emanated from 

sealed sources and containers [Rose 1948, 1949]. While detailed descriptions of radon traps have 

not been located, it should be noted that ANL-E was involved in research of solid absorbents for 

radon [ANL 1979a, PDF p. 91]. Room-filtered air ventilation and hoods were in place [Fleury 

1946, PDF p. 3; Huntsinger et al. 1952, PDF pp. 193–196]. 

This historical perspective, including information about the Met Lab, is included to demonstrate 

that the potential for exposure to radon was recognized and controlled, even early in the 

operations of Met Lab, the direct predecessor of ANL-E.

ANL-E OPERATIONS INVOLVING RADIUM

Radium use at ANL-E involved small (i.e., gram quantity) radium sources or radium compounds, 

as well as other special uses, such as dosimeter and instrument calibrations [ANL 1979a, PDF p. 

246; Strom 1982, PDF pp. 12, 79, 268, 317–318] and accelerator studies [Holl et al. 1997, PDF 

p. 176; Lonergan and Novak 1962, PDF p. 41]. These operations were consistently described in 

the records as being conducted in laboratory settings, which involved the use of hoods, 

gloveboxes, filtered building ventilation, and routine health physics coverage, including routine 

air monitoring. No records have been found indicating that large-scale processing or handling of 

radium occurred. 

Chemistry Division 

With the move from Met Lab to ANL-E, chemistry activities were relocated to Site D (Building 

40, East Area and Building 200, 200 Area) [ANL 1955b, PDF p. 5] at the new ANL-E site.

Records indicate that precautions and protective measures initiated during Met Lab operations 

were carried over to ANL-E facilities at Site D when operations were transferred, including 

sealing of radium sources, storage in non-occupied areas, design of facilities to ensure ventilation 

by filtered air, and work in hoods [Rose 1949, PDF p. 3; ANL 1955b, PDF pp. 5, 19]. 

As noted in the site profile [ORAUT 2006c], work with potential sources of radon included use 

of 226Ra in Buildings 203 and 211 as part of the accelerator program. 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

As stated in the introduction, it has been pointed out that the existence of a radium (226Ra) in 

vitro bioassay program could indicate a potential for exposure to radon (222Rn). Although many 

bioassay results in the records are not identified by work location, those that can be identified are 

consistent with the locations identified above as using radium (e.g., D-200, D-203), and many of 

the results were for follow-up samples for six individuals involved in the June 1952 incident 

[ANL 1960a], an individual who received a skin puncture wound involving 223Ra contaminated 

forceps [ANL 1951–1960], and two individuals involved with a liquid sample spill of 300 

microcuries of 226Ra in a fume hood [Fairman 1974, PDF p. 9]. Table 1 below contains 

descriptions of representative work activities or incidents involving radium from various safety 

reports throughout the years. 

Typical numbers of radium bioassay samples were less than 10 per month or around 1% to 2% of 

the total number of bioassay samples processed for ANL-E, indicating that radium was not 

involved in most radiological work. Consequently, the existence of the radium bioassay program,

as described in records, is consistent with the processes described in this document and does not 

suggest additional large-scale radium operations existed that would have generated significant 

radon quantities.

Biology Division

The Biology Division (in Building 202, the Biology Building) continued research on the radium 

dial painters, transferred from Site B by the end of 1952 [Novak 1952, PDF p. 69], as well as 

biological studies on the effects of radiation on animals and plants. Numerous reports reviewed 

from between 1952 and 1963 describe animal injections with various radionuclides identified. 

Radium injections were occasionally reported in microcurie amounts [Lonergan and Novak 

1959, 1961, 1962, 1963; Novak 1952, 1953, 1957b; Okolowitz and Novak 1956; ANL 1955b, 

1955c, 1958, 1960b]. These reports consistently describe this work as being performed in 

laboratory environments with associated radiological monitoring. Potential radiological 

exposures were identified in monthly safety reports (typically none or minor spills). Radon 

exposures would not have been likely due to the small amounts of material involved, the matrix

of the material, and the containers of the source material (liquid solutions in syringes).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Table 1. Incidents or Documented Work with Radium

Reference Date Location Source Description

Rose 1949 02/21/1949 Site A,

Room A-10

Leaking 0.5 g

Ra-Be source

Air counts in adjacent rooms to where the 

source was located were twice background 

levels. Source was placed in room D-6 storage 

area. Air counts in storage area on 02/28/1949 

were 5.3 times the permissible level for radon 

at 1 hour and slightly more than permissible at 

5 hours (radon permissible level given as 10-11

Ci/L). Source moved to ventilated area at New 

Chem (University of Chicago site). Storage 

room was tested again on 03/11/1949 after 

having been closed and it showed air 

concentrations 5x permissible level (PDF p. 

22).

Rose 1949 03/14/1949 Site A,

Room A-18

1 g radium 

source (RaBr2) 

ruptured

Source discovered ruptured when opened. 

Accounts for high radon levels in storage area. 

Decontamination of Room A-18, where the 

source was opened, continued through 

03/23/1949. Three named individuals involved

in clean-up wore respirators, protective 

clothing, and two of the three provided followup bioassay for 'Ra and Rn'. Bioassay results 

were negative. Radon leakage from container 

gave surface contamination readings of "20M" 

(or 20,000 cpm/100 cm2

; “M” = 1,000 dpm/100 

cm2

). Eventually, this source was sent back to 

New York on 04/04/1949 (PDF pp. 19, 20).

Rose 1949 04/12/1949

New Chem

(University of 

Chicago site) 

Leaking 500 

mg radium 

source soldered

Individual worked in a Pb-shielded steel dry 

box in the hot lab. External doses were 

measured at various locations and personnel 

dosimetry (wrist, head, and special body 

badges) were worn and measured (PDF p. 17). 

Presumably, this is the same leaking source as 

02/21/1949.

ANL 1979a 06/13/1952 Building 203 50 mg radium 

sulfate powder 

PDF p.246, release of radium sulfate powder 

during calibration of pocket dosimeters.

ANL 1953 11/02/1953 D-202

(Room E-101)

Monitoring 

service 

provided while 

rats were 

injected with 

radium

Fifty rats injected with radium (total activity 

800 μCi). Surveys were done pre and post job. 

Post job survey found 2M alpha contamination 

in on 2’x2’ area on the benchtop. 

Contamination was cleaned with acetone. Air 

monitoring was taken (filter queen) during the 

job and showed 1 dpm/m3 when decayed to 16 

hours (PDF p. 7).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Reference Date Location Source Description

ANL 1953 07/07/1953 D-202

(Room B-222)

Radon leak 

from low level 

radium waste 

container

Radon leak from corroded cap, initial air 

sample result of 5,696 dpm/M3 (26% of radon 

MPL); result of 6 dpm/ M3 after 24-hour decay

(PDF p. 10). Cap was replaced preventing 

further leaks

ANL 1954–

1955 1954 D-200 Ra-223

Ra-223 incident bioassay results (see ANL 

[1951–1960] below)

ANL 1951– 1960 1954 D-200 Ra-223

Ra-223 intake due to skin puncture with 

contaminated forceps (PDF p. 3); associated 

bioassay results

ANL 1955c 01/1955

Building 203

(various 

electrical substations in 

waist [sic] 

area)

Contamination 

from 

06/13/1952 

incident

Contamination from the 06/13/1952 radium 

spill discovered during survey; decontaminated 

to a fixed level of 1M to 10M from initial 54M

(PDF p. 120)

ANL 1955c 12/12/1955

Building 203 

(A fuse and 

breaker switch 

housing at substation B)

Contamination 

from 

06/13/1952 

incident

Contamination from the 06/13/1952 radium 

spill decontaminated from 40M to fixed levels 

of 1 to 5M (PDF p. 6)

Okolowitz and 

Novak 1956 1956

Site A 

Building 40 

Chemistry

Radium

Site A Building 40 Chemistry - radium spill 

near hood in room E134 was deconned

06/27/1956 (PDF p. 4); 01/06/1956, transfer of 

sample to cave in hood in Special Materials

(PDF p. 50)

ANL 1958 1958 Building 203

Contamination 

from 

06/13/1952 

incident

Further decontamination of electrical 

substations contaminated by 1952 spill 

(described in ANL 1955c) with no resulting 

personnel, equipment, floor, or airborne 

contamination (PDF p. 78,); residual 

contamination from same spill found in sump 

pump pit and partially deconned, with 

remainder fixed in place (PDF p. 181)

Lonergan and 

Novak 1959 1959 200 Area Radium

Release of radium from flask in hood room 

F114 contaminated only hood, response in 

Scott Air Paks (PDF p. 24)

Lonergan and 

Novak 1961 02/1961

Building 203

(air supply 

duct in G049 

and adjacent 

storage cage)

Contamination 

from 

06/13/1952 

incident

Surveys of 40” section cut out and to be 

replaced by outside contractors showed activity 

of 1 to 3M direct and 0.2 to 2M loose 

contamination from the June 13, 1952, radium 

spill. Reclamation personnel cleaned the duct to 

permissible levels before the sheet metal men 

were allowed to proceed (PDF p. 226).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

Lonergan and 

Novak 1961 02/14/1961

Building 203

(G097 

electronic 

stockroom 

wall)

Ra-226

Monitoring provided to contract personnel 

during removal the section of the wall. Survey 

of the wall showed spots of 1 to 5M direct and 

less than 0.2M smears. Only one individual 

involved and wore coveralls and respirator. Air 

sample taken during operation showed 86%

MPC (MPC for 168-hour week = 22 dpm/m3

) 

for Ra-226 after 24 hours decay (PDF p. 226).

Lonergan and 

Novak 1961 08/24/1961

Building 350

(Fabrication 

and Technical 

Area room 

exhaust)

Radon, Thoron 

and daughter 

products 

detected on 

prefilters

Forty-eight prefilters were changed by 

Reclamation Services. Filters read 0-1,000 

dpm/62cm2 alpha and less than 0.1/1” H&S 

(hard and soft) beta-gamma. Contamination is 

due to radon and thoron and their daughter 

products (PDF p. 105).

Lonergan and 

Novak 1962 1962 Building 316 Radon source

Zero Gradient Synchrotron (ZGS) - ring coil 

magnet alignment in D369 (proton area) using 

a "radon source" (PDF p. 41), previously a 

radium source used.

Lonergan and 

Novak 1962 1962 Building 316 Radon source

Radium

Spill in Building 200 room E134 (material not 

listed) resulted in hand/foot/floor radon 

contamination, spill of radium in room R066 

Special Materials (PDF p. 68).

Lonergan and 

Novak 1963 1963 Building 200 Rn-222

Ra-226

Building 200 Chemistry, room F110 -

preparing Rn-222 generator from Ra-226

sample, flask arm broke releasing 1 mCi of Rn222, all work and recovery performed in hoods 

with no airborne release to laboratory (PDF p. 

69).

Lonergan and 

Novak 1963 01/30/1963 Building 200 Radium source

Special Materials workroom routine survey 

found radon progeny contamination on floor, 

traced to leaking radium source moved to hood, 

work performed with assault masks (PDF p. 

168–169).

Lonergan and 

Novak 1963 02/13/1963 D-369 Radon source

ZGS - ring coil magnet alignment of 

accelerator in the D369 Building using radon 

source, area off limits to personnel during 

exposure (PDF p. 157–158).

Sedlet 1972–

1974 10/05/1972 Building 203 Radium

Bioassay records of all involved in 06/13/1952 

radium release (described above in ANL 

[1979a, PDF p. 246]) were reviewed and the 

decision was made to recheck urine samples 

from involved individuals that were still 

employed at ANL-E (PDF p. 26).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

Sedlet 1972–

1974 01/29/1973 No 

information

Broken tube 

containing Rn222

PDF p. 152: Tube containing Rn-222 broken 

during a chemical reaction experiment. The two 

occupants (one CHM, one visitor) in the area 

were counted in the BRC (body radioactivity 

counter) with small amounts of Bi-214 and Pb214 detected. Evaluation pending per the 

January 1973 report. 

Fairman 1974 11/05/1974 Building 203

Radium

(Ra-226)

chloride

A 1 milliliter, 300 μCi solution of radium (Ra226) chloride being evaporated on a hot plate in 

a hood splattered off planchet and 

contaminated the immediate surroundings. 

Follow-up radium bioassay performed for two 

involved individuals.

ANL 1979a 1979 Building 200

Wing M

Radium

Radon 

generator

1979 - Wing M work described, only work 

with radium is radon generator for developing 

solid absorbents for radon (PDF p. 91); 

accident history outlining 06/13/1952 radium 

release (PDF p. 246)

ANL-E OPERATIONS INVOLVING THORIUM

No records have been found indicating that large-scale processing or handling of thorium 

occurred, except for the operations with spent fuel currently described in the ANL-E 

Occupational Environmental Dose TBD (ORAUT 2006b). 

Chemistry Division

As noted in the site profile [ORAUT 2006c], work with potential sources of radon included 

production of 220Rn in Building 200, handling of natural thorium in the East Area, and handling 

of Th-228/Th-230 in Building 211. Table 2 gives examples of thorium work discussed in various 

safety reports throughout the years at ANL-E. As demonstrated in the information in Table 2, 

planned work with thorium typically involved air and contamination monitoring, as well as use 

of respiratory protection when there was a potential for elevated air concentrations. Thorium 

incident follow-up was similar to that seen for radium incidents (i.e., use of respiratory 

protection for re-entry/clean-up efforts and special bioassay for individuals present at the time of 

incidents). 

Note that because the thorium isotope is not identified in several of the records shown in Table 2, 

the associated radon isotope [i.e., 220Rn (232Th decay series) versus 222Rn (230Th and 238U decay 

series)] cannot be determined with certainty. It is assumed that the term “thorium” would 

typically be natural thorium (232Th); therefore, the references are included in this section. 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Table 2. Incidents or Documented Work with Thorium

Reference Date Location Source Description

Novak 1952 04/10/1952 D-16 Thorium, 

uranium

Thorium, uranium, and beryllium compound 

removed from Site B Special Materials vault and 

packed in secondary containers, relocated to D-16; 

protective clothing and assault masks worn at all 

times in the vault.

ANL 1955c 02/28/1955 D-203 Thorium

Small bottle of thorium surveyed that had been 

ground into fine powder outside of hood in Room 

G-126 with no monitoring requested and no air 

sampling performed; urine and fecal samples 

requested and recommendation made that similar 

work be performed in hood; fecal sample results in

Robinson [1955–1956, PDF p. 36]; no urine results 

found, but this document only reports positive 

results, so any urine sample was likely 0 

dpm/1,500 cc.

Novak 1956 08/25/1955 D-301 Thorium, 

uranium

Airborne release of uranium and thorium oxide in 

Cave #2.

Okolowitz 

and Novak

1956

01/01/1956 D-200 Thorium

Series of high air samples determined to be due to 

thorium crucibles stored in cabinet in lab (lab not 

identified).

Okolowitz 

and Novak

1956

06/01/1956 D-22 Thorium

Air samples exceeded [thorium] MPLs during 

operations using powdered thorium oxide; 

operations suspended 3 weeks to develop methods 

to address; pressing of Th-232 pellets begun 

06/29/1956, air sampling performed.

Novak 1957a 12/18/1956 N/A Thorium, 

uranium

Twenty-two urinalyses for thorium and uranium to 

be sent to A.P. Greene company.

Novak 1957a 01/16/1957 D-23 Thorium Permission given to use thorium in Building 23 as 

long as monitoring performed.

Novak 1957b 10/15/1957 D-316 Thorium

Spill of 1-2 grams of 96% thorium oxide/4% 

enriched uranium oxide from ZPR-VII fuel tube; 

urine samples requested, no activity above control 

values.

ANL 1958 12/15/1958 D-301 Thorium, 

uranium

Cell B; fuel assembly (uranium-thorium) cut in 

isolation area, personnel in adjoining area 

evacuated, air sample showed no significant alpha 

after 21 hours.

Lonergan and 

Novak 1959 01/01/1959 Buildings 25, 200, 301 Thorium Various thorium samples, fuel pellets in use.

ANL 1960b 03/31/1960 D-205 Thorium F111; rad safety monitoring of thorium 

solidification run, no incidents.

ANL 1960b 09/01/1960 D-208 Thorium

Evaporating thorium on gold foils in cold trap 

equipped vacuum; no long-lived activity on air 

samples.

ANL 1960b 09/15/1960 D-205 Thorium, 

uranium

Spill of 6-8 liters of uranium-thorium nitrate 

solution; air samples below 10% maximum 

permissible concentration (MPC) for uranium, 

urine samples negative.
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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

ANL 1960b 10/04/1960 D-16 Thorium

F area; machining of thorium rods with air 

monitoring; "Various radioactive materials are 

handled in this room including uranium of various 

enrichments with associated radon-thoron daughter 

products. Therefore, a more realistic decay time to 

determine the presence of long-lived activity was 

used. Based on the thorium B half-life of 10.6 hr. 

and 8 half-lives, approximately 3.5 days was used. 

Under these assumptions no significant amount of 

thorium was detected." (PDF p. 40)

ANL 1960b 12/01/1960 D-205 Thorium 

Decon of furnace wearing assault masks, air 

samples below thorium MPC (168-hour week) of 

22 dpm/ m3

.

ANL 1960b 12/21/1960 D-200 Thorium

Minor thorium compound spill in Hood #4 room 

F102; no air or personnel contamination. 

ANL 1960b 12/28/1960 D-205 Thorium

B133; spill of thorium compound (100 ml of 

liquid), no personnel or air contamination. 

Lonergan and 

Novak 1961 07/09/1961 D-22 Thorium

Dismantling of thoria spray booth wearing assault 

masks, shoe covers, and protective clothing. 

Lonergan and 

Novak 1961 08/08/1961 D-40 Thorium

Decontamination of glovebox where experiments 

with Th-228/-229/-232 were conducted; assault 

masks worn; air sample 12% MPC (22.2 dpm/ m3

, 

168-hour week) after 5 days.

Lonergan and 

Novak 1961 08/24/1961

Building 

350

(Fabrication 

and 

Technical 

Area room 

exhaust)

Radon, 

thoron

Radon, thoron, and daughter products detected on 

room exhaust system prefilters; 48 prefilters were 

changed by Reclamation Services. Filters read 0-

1,000 dpm/62cm2 alpha and less than 0.1/1” H&S 

beta-gamma. Contamination is due to radon and 

thoron and their daughter products (PDF p. 105). 

Lonergan and 

Novak 1962 11/07/1962 D-37 vaults Thorium

Entry to area where kilogram quantities of thorium 

stored wearing half-face respirators; air samples at

25.7 and 4.0 MPC after 18 and 22 hours; both 

samples below 2% MPC after 5 days; Th-nat MPC 

(168 hours/week exposure) = 44 dpm/m3

; Pa-234 

detected in sample.

Lonergan and 

Novak 1963 04/01/1963 D-205 Thorium, 

uranium

Arc-melting of uranium and thorium samples in 

room H125 in furnace, no room, personnel, or air 

contamination resulted (PDF p. 103).

Lonergan and 

Novak 1963 04/26/1963 D-17 Thorium

Machining of thorium rods without prior 

notification of Radiation Safety; hand/clothing 

contamination of 1,000 dpm/61 cm2 resulted, 

which was successfully deconned; urine sample 

result negative (PDF p. 101).

Lonergan and 

Novak 1963 05/23/1963 D-17 Thorium Machining of 1 kg thorium rod without incident 

(PDF p. 83). 

Golchert and 

Kolzow 1998 1997 N/A Rn-220 Rn-220 release, maximum perimeter dose of 0.24 millirem/year (PDF p. 29).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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ANL-E OPERATIONS INVOLVING ACTINIUM

No records have been found indicating that large-scale processing or handling of actinium

occurred. 

Chemistry Division

As noted in the site profile [ORAUT 2006c], work with potential sources of radon included 

handling of 227Ac in Building 200. 

With the move from Met Lab to ANL-E, chemistry activities were relocated to Site D (Building 

40, East Area and Building 200, 200 Area) [ANL 1955b, PDF p. 5] at the new ANL-E site. 

Records indicate that precautions and protective measures in use at the Met Lab facilities were 

carried over to ANL-E facilities at Site D when operations were transferred, including sealing of 

radium sources, storage in non-occupied areas, design of facilities to ensure ventilation by 

filtered air, and work in hoods [Rose 1949, PDF p. 3; ANL 1955b, PDF pp. 5, 19]. 

During work with 227Ac in Building 200, which occurred between 1952 and 1958, knowledge of 

the potential for release of 219Rn (actinon) was evident in handling the materials. Samples were 

used in shielded gloveboxes and enclosed ventilation systems, or stored in Special Materials 

vaults, and were sealed in plastic during transfer, with air sampling performed [ANL 1955c, PDF 

pp. 107, 118]. Record of an incident involving disconnecting a glovebox from the ventilation 

system resulted in high concentrations of 219Rn measured in room air; Scott Air Paks [i.e., selfcontained breathing apparatus (SCBAs) with supplied air] were worn during incident recovery 

operations [ANL 1958, PDF p. 179]. Table 3 gives examples of actinium work discussed in 

various documents and safety reports throughout the years at ANL-E.

Table 3. Incidents or Documented Work with Actinium

Reference Date Location Source Description

Staniforth 

1950 12/20/1950 N/A Actinium

Indicates 'possible' decision by ANL-E to allow 

Mound to operate a cave for actinium extraction 

at ANL-E, with 7 Ci available in May and June 

1952 and Jan and Feb 1953.

Novak 1952 10/22/1952 D-200 Ac-227

F-110; 3 mg Ac-227 samples opened in a hood;

air counts, dosimeters, and contamination

surveys showed no exposures approaching

permissible levels occurred.

Novak 1953 12/25/1952 D-200 Ac-227

Room F-110; accidental hood opening 

containing 7 mg of Ac-227 and other 

contaminants; air sample for short lived activity 

'somewhat higher than normal'; urine samples 

requested (results in Sedlet [1954, PDF pp. 106–

107]).
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

Novak 1953 01/05/1953 D-200 Ac-227

Room F-118, hood #1, removed Ac-227 

contaminated equipment and waste from hood, 

air sample at 12.3x MPL for Pu-239; surface 

contamination on horizontal surfaces from 

'actinium emanations'; equipment and waste 

sealed and removed on 01/06/1953 wearing 

assault masks; room deconned on 01/07 and 

01/08/1953; no contamination of adjoining 

rooms.

Huntsinger 

1953; 

Novak 1953

04/08/1953 D-200 (Room

F-118) Ac-227 spill

A 5-page memo detailing spill in F-118 that was 

spread to rooms F-110, F-122, and adjacent 

corridors and involved shoe and clothing 

contamination of a number of workers. 

Contamination was of a ‘spot’ nature, with the 

highest activity 12,800 M (M = 1,000 dpm/100 

cm2

) recorded in Room F-118. Air samples were 

background except for sample in F-118, which 

was 135% MPL of 70 dpm/M3 after 30 minutes, 

and 8% of MPL at 21 hours. Bioassay samples 

were requested from several individuals, with 

corresponding results in Sedlet [1954, PDF pp.

69–77]. Additional incident description in Novak

[1953, PDF pp. 24–26].

ANL 1953 08/24–

08/25/1953

D-200

(Room F-102)

Elevated air 

samples while 

cleaning 

known Ac-227 

“Berkely Box”

General cleaning of equipment and materials in 

the “Berkely Box” resulted in 2 air samples above 

the MPL of 70 dpm/m3

. Box had been used for 

high level Ac-227 samples. Coveralls, gloves, and 

shoe covers worn at all times by the two workers 

doing the clean-up. Scott Air Packs were issued 

on August 25. Urine and fecal samples were 

requested from the two workers, as well as the 

Industrial Hygiene Section support person (PDF 

p. 2); gross alpha results for follow-up urine fecal

samples for involved workers listed in Sedlet

[1954, PDF pp. 21–29].

ANL 1953 10/22/1953 D-200

(Room F-110)

Removal of 

hood #6 and 

section of 

exhaust duct

Ac-227 in an adjacent hood attached to the same 

exhaust as hood #6 had 3mg of Ac-227. Rather 

than move source, ventilation (large elephant hose 

attached to glove port) at 800 lineal feet per 

minute was exhausted to a fume hood on a 

separate system. Assault masks and protective 

clothing worn by personnel and air samples taken 

during the entire operation. Air samples showed 

less than 10% MPL after 4-day decay. Post job 

survey showed no new contamination. 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

ANL 1953

11/27/1953 

and 

11/30/1952

D-200

(Room F-110)

Monitoring 

service 

provided 

during 

unpackaging 

of Ac-227

Monitoring service provided during unpackaging 

of two high-level Ac-227 samples (99 mc and 200 

mc). Unpackaging was performed in a Lucite box 

in glove paneled Blickman hood. Protective 

clothing including leaded gloves, as well as 

personnel monitoring devices, were worn by 

workers. Air samples taken during the operation 

indicated no activity above normal room 

background levels.

ANL 1954–

1955 1954 D-200 Ra-223

Ra-223 incident bioassay results (see ANL 

[1951–1960] below).

ANL 1951–

1960 1954 D-200 Ra-223

Ra-223 intake due to skin puncture with 

contaminated forceps (PDF p. 3); associated 

bioassay results.

ANL 1955c 01/06/1955 D-200 Ac-227

F-118; transfer, plating, and preparation of Ac227 samples in shielded glovebox; hoods and

gloveboxes taped prior to electrical shutdown,

air sampling showed no elevated levels; constant

alpha air monitor installed in F-118 on

01/25/1955.

ANL 1955c 02/02/1955 D-200 Ac-227

F-118; eight 0.3 mg electrodes removed from

shielded glove box and relocated to spectroscopy

laboratory (K-127); sealed in plastic pouches

before transfer; samples mounted and arced in

enclosed ventilation system, then resealed in

plastic pouches and transferred to special

materials vault for storage.

ANL 1955c 03/08/1955 D-200 Actinium 

powder

F-118; Removal of northwest hood used mainly

for dry actinium powder work, subsequent

cleaning and decon; contamination levels

exceeding 7,000M (M=1,000dpm/100cm2

);

operation monitored and conducted in Scott Air

Pak without incident.

ANL 1955c 06/27/1955 D-200 Ac-227

F-118; Removal, preparation, and plating, of an

Ac-227 sample; air sampling and frequent

surveys of hands, clothing, and floor conducted

with no contamination found during operation.

ANL 1955c 07/07/1955 D-200 Ac-227 F-118; Several Ac-227 samples moved from a

hood to a small cave without incident.
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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

Reference Date Location Source Description

ANL 1958 01/15/1958 D-200 Ac-227

Room F-118; release of Ac-227 during removal 

of glovebox containing ~2 mg; after 

disconnection from ventilation system, 

extremely high concentrations of Rn-219 

detected in room air; room sealed, no activity in 

adjoining rooms or corridor; glovebox wrapped 

in poly sheeting, placed in plywood container, 

and moved to isolation room of F-118, where it 

was determined no radioactive gas was escaping; 

box sent to 317 for disposal; air sample indicated 

“4.7x OPL” (assumed to have been a 

typographical error, intending to stand for 

maximum permissible level, or “MPL”) for Ac227 after 8 days decay; Scott Air Paks worn, 

room reopened 01/28/1958.

INCIDENTS OR DOCUMENTED WORK INVOLVING RADIUM, THORIUM, OR 

ACTINIUM

A number of incidents resulting in radon releases or potential exposures have been located in 

ANL-E records, as noted in the tables above. While this is not an exhaustive list, it gives a good 

idea of the types of incidents and planned unusual work (with health physics support) that 

occurred at ANL-E, as well as any follow-up conducted as a result of it. Most of this information 

is coming from searches of monthly Radiation Safety, Radiological Physics, or Industrial 

Hygiene reports. These reports typically provide names of ANL-E employees that were involved, 

the survey results, as well as bioassay monitoring that was completed, but not necessarily 

bioassay results, as these reports would have been completed at a later time after investigations 

and follow-up. A number of characteristics are common to these incidents and the responses to 

them.

First, none of the incidents represented long-term, unidentified exposures to personnel. While 

some releases were known immediately, others were identified by routine surveys. Prompt 

corrective actions were taken, using protective clothing and respiratory protection for more 

significant releases.

The incidents also did not represent large potential source terms for radon progeny exposure. 

Although the quantities of radium were large enough to trigger the use of radiation protection 

measures because of the potential for internal and external exposure, respiratory protection 

measures in response to the immediate recovery activities [e.g., use of assault masks (similar to 

half- or full-face respirators) and Scott Air Paks, relocation of source to hoods] would have also 

protected against associated short-term radon progeny concentrations that might have occurred 

during initial response. 

After incident response, removal of the released material (in the case of a spill) may have 

resulted in residual surface contamination. The most significant incident noted in the records was 

a release involving approximately 50 milligrams of radium sulfate powder on June 13, 1952, in 
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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Building 203 [ANL 1979a, PDF pp. 246–247], which contaminated much of the building. 

Decontamination efforts were extensive and residual surface contamination remained for several 

years. Typical surface contamination levels measured on the interior surfaces of ductwork, a fuse 

and breaker switch housing, and electrical substations ranged from 1,000 to 40,000 dpm/100cm2

after initial decontamination, which correspond to microcurie levels of activity per square meter 

of surface. These levels do not represent potential sources of significant airborne radon activities, 

especially on the interior of enclosed structures. [ANL 1955c, PDF pp. 6, 120; ANL 1958, PDF 

pp. 78, 181; Lonergan and Novak 1961, PDF p. 226].

Despite the activities discussed above, a 1982 Environmental Report describing the primary 

functions of Wing M of Building 200 makes no mention of radium use [DOE 1982, PDF p. 31],

which is consistent with the infrequent use and small quantities described in the documents 

above. Additionally, in a 1981 Dosimetry Records and Radiation Hazards Questionnaire 

sponsored by the U.S. Department of Energy (DOE), “radon & daughters” is the only 

specifically excluded selection by ANL-E under the question regarding “types of internal 

exposures that may have occurred at your facility” [Dolecek 1981, PDF p. 15]; all other internal 

exposure types were included as applicable to ANL-E (these were fission products, tritium, 

iodine, activation products, uranium, plutonium, other transuranics, other beta-gamma emitters, 

and other alpha emitters). The conclusion that direct personnel monitoring was not necessary for 

exposure to radon would be consistent with this information.

AIR SAMPLING AT ANL-E

In addition, air samples were routinely collected and analyzed to detect elevated concentrations 

of radioactive materials, primarily uranium and plutonium (see Table 4). Evaluation of the 

records in Table 4 indicates that general area air sampling supporting worker activities was 

performed on a daily basis for either the entire day or for the period during which the covered 

activity was being performed. Samples specifically for 222Rn associated with the A5 stack in 

Building D-200 were noted in ANL [1967]; these samples were collected in unoccupied areas 

and were of shorter duration (an hour or less during vented releases) than those supporting 

worker activities. These samples provided information relevant to offsite releases reported in 

ANL-E environmental reports and are accounted for in the assigned occupational environmental 

doses [ORAUT 2006b]. 

Air samples were typically analyzed for alpha and beta activity. Samples would have been 

promptly counted after collection, then counted at later times to determine long-lived 

radionuclide activity following decay of radon progeny. Radon progeny could have been from 

natural sources or from occupational sources, depending on the location of the air sampler and 

the work activities being monitored. Because radiation protection personnel were familiar with 

typical results for ambient (non-occupational) radon interference, initial count values exceeding 

normal levels allowed identification of elevated (higher than ambient) radon levels due to 

occupational sources. Evaluation of ANL-E air sampling records indicated that initial counts of 

samples intended to monitor long-lived alpha emitting radionuclides without potential for radon 

exposure were typically on the order of tens to hundreds of dpm/m3 with subsequent counts 

lower (indicating the presence of non-occupational ambient radon progeny interference in the 
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initial count). Samples in areas with identified radon sources were on the order of hundreds to 

several thousand dpm/m3 and would have been compared with the maximum permissible level 

(MPL) for radon (1E-11 Ci/L or 10 pCi/L); this MPL was established for radon as early as 1949 

[Rose 1949, PDF p. 22]. As seen in the incidents discovered by elevated radon air concentrations 

in areas of known radon sources (discussed in the tables above), ANL-E follow-up typically 

involved isolating the source of the radon and clean-up of the areas, which would have been 

performed in respiratory protection. 

Available records indicate air sampling and site-specific analysis of results (i.e., knowledge of 

typical ambient radon levels) were used on multiple occasions to identify and isolate radon leaks 

from radium sources in unoccupied storage locations [Rose 1949, PDF pp. 19, 22, Site A; ANL

1953, PDF p. 10, Site D; Lonergan and Novak 1963, PDF pp. 168–169, Site D, Building 200]. 

Table 4. Air Sampling Locations.

Reference

Date of 

Sampling Description

ANL 1946 1946 Site B (Chicago)

ANL 1947–1948 1947–48 Site A

ANL 1950 1950 Unknown, one page

ANL 1952 1952 D-300, 301, 310, 340

ANL 1953–1954 1953–54 Site A; West Stands; D-306 and 317

ANL 1954a 1954 D-202

ANL 1954b 1954 D-301; D-306; D-310

ANL 1954c 1954 West Stands; results in %MPL only

ANL 1955a 1955 D-301

ANL 1955–1956 1955–56 D-306

ANL 1956a 1956 D-202

ANL 1956b 1956 Site A

ANL 1956c 1956 D-200

ANL 1956d 1956 D-205

ANL 1956e 1956 D-202, D-310

ANL 1967 1967

Various 200, 300, East Area locations; “Stack Monitor Data Sheet: Radon 

Monitor Channel 1” (PDF pp. 504–508) (some illegible); Rn-222 air 

sample result (PDF p. 416), (after release from Cell A-5) (PDF pp. 484, 

492, 509)

ANL 1968 1968 D-350, New Brunswick Laboratory (NBL)

ANL 1972 1972 D-350

ANL 1973 1973 D-350, NBL

ANL 1974 1974 D-350, NBL

ANL 1975 1975 D-350, NBL

ANL 1976 1976 D-350, NBL
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Reference

Date of 

Sampling Description

ANL 1977 1977 Various locations

ANL 1978a 1978 Various locations

ANL 1978b 1978 Various locations

ANL 1979b 1979 Various locations

ANL 1979c 1979 D-350

OTHER DOE RADON REFERENCES

A DOE study performed in 1989 to 1990 and summarized in the report “Results of the U.S. 

Department of Energy Indoor Radon Study” [DOE 1990], evaluated radon levels throughout the 

DOE complex. During this study, radon concentrations were measured at 138 locations at the 

ANL-E site, 4 of which exceeded the action level of 4 pCi/L. These buildings and their 

associated values were:

14.3 pCi/L - Building 576 (office, 500 area electrical/water distribution buildings) 

8.3 pCi/L - Building 212 (Alpha Gamma Hot Cell Facility, HVEM Tandem Accelerator, 

room F2) 

6.5 pCi/L - Building 25 (Argonaut demonstration reactor, room A-110) 

4.3 pCi/L - Building 33 (East area surplus facilities, room 108) 

None of these buildings are associated with radium operations or processes anticipated to release 

radon; consequently, these results are considered to be due to environmental rather than 

occupational sources of radon. The Indoor Radon Study report further notes that the expected 

probability of any particular building exceeding the 4 pCi/L action level was 7% based on the 

Nero distribution [Nero, et. al. 1984]; the sitewide value was less than 3% by comparison.

An additional DOE report [Strom and Reif 1996] identified ANL-E as one of 12 DOE facilities 

and projects having elevated radon levels in a DOE report for year 1991 compliance with 

National Emissions Standards for Hazardous Air Pollutants (NESHAPs). The NESHAPs 

compliance report [DOE 1992] references a release of 2900 Ci of 222Rn during calendar year 

1991, projected to result in a maximum offsite dose of 0.29 mrem/yr. These values were obtained 

from the ANL-E site environmental report [Golchert et al. 1992] and are attributed to

environmental releases from the proof of breeding program. Exposures from these releases are

discussed and doses assigned in the ANL-E Occupational Environmental Dose TBD [ORAUT 

2006b]. 

CONCLUSIONS

There is no large source term for radon, thoron, or actinon identified at ANL-E; no bulk 

materials, such as ores, were identified. ANL-E did, however, use millicurie or milligram 
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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

amounts of the radium, thorium, and actinium (i.e., primary source material), as demonstrated in 

the records listed above. These records consistently demonstrate that ANL-E used these 

materials in controlled laboratory environments (i.e., filtered air flow for building ventilation and 

work performed in hoods). Measures to control internal exposures to the primary source

materials reduced the potential for radon progeny exposures as well, even though radon exposure 

was not typically the primary emphasis of monitoring and protection measures. Records also 

demonstrate that during interruptions of ventilation air flow, laboratories would have been sealed 

and recovery operations would have involved respiratory protection measures for workers. 

Surface contamination, laboratory sample quantities, and radium sources in sealed containers in 

unoccupied storage areas would not have provided a significant source of airborne radon. It is 

further evident that ANL-E was aware of radon as a potential for exposure from the beginning of 

operation and did not identify it as a significant internal dose pathway. 

In response to Observation 4 in SC&A [2009], that there is a potential for exposure to radon 

(

222Rn), actinon (219Rn), and thoron (220Rn), which is not thoroughly discussed in the Site Profile, 

NIOSH attests that routine exposures to radon from the presence of source materials would not 

have resulted in significant exposures because: 

• engineered measures to control exposure to long-lived radionuclides also prevented 

exposure to radon, 

• incidents where significant exposure was possible were readily identified by routine 

monitoring and mitigated, and

• response to identified incidents were conducted using worker protective equipment, 

restricted access, and isolation of sources. 

To address the observation, additional exposure assessment explanation based on the information 

in this document will be added to ANL-E Occupational Internal Dose TBD [ORAUT 2006a] in 

order to provide additional background information and justification for the current dose 

reconstruction methodology. 

It should be noted, as is the case for the current dose reconstruction process, claims received for 

individuals involved in known incidents involving elevated radon levels, such as those discussed 

above, will be reviewed on a case-by-case basis to determine appropriate assignment of dose. 
White Paper Assessment of Potential for Radon Exposure at ANL-E September 30, 2019

Page 21 of 26

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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Page 22 of 26

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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Page 25 of 26

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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Page 26 of 26

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution. 

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