slide 1 the u.s. transuranium & uranium registries (ustur): the fifth decade of nuclear worker...

The U.S. Transuranium & Uranium Registries (USTUR): The Fifth Decade of Nuclear Worker Follow-up

Anthony C. James, PhD, CRadPUSTUR Director, Research Professor

College of Pharmacy

Richland, WA 99354-4959, USA

[email protected]

www.ustur.wsu.edu

Forschungszentrum Karlsruhe (FZK) SeminarKarlsruhe Institute of Technology (KIT)

Nuclear Safety Research ProgramTuesday, April 7th, 2009

“Learning from Plutonium and Uranium Workers”

USTUR: Learning from Plutonium and Uranium Workers

The USAEC Vision


The US Transuranium Registry (USTR)


The U.S. Transuranium & Uranium Registries – 2009

•Overview of USTUR Registrant Scope, Status and Procedures.•National Human Tissue Repository (NHRTR)

- Specimen storage/inventory/tracking database.• Radiochemistry

- Improved actinide separation procedure- Introduction of ICP-MS.

• Internal Database and Web Publication of Case Data- Case Narratives/Pathology/Radiochemistry/Health

Physics.• Example of Biokinetic Case Study

- Bayesian analysis of uncertainty in model parameter values and tissue doses (HPA-RPD collaboration).

This Presentation

FZK/KIT Seminar – ACJ – April 7th, 2009

Registrant Status


As of March 31st , 2008

Total Deceased and Active (Living) Registrants: 424

Living Registrants: 92 Potential Partial-body Donors: 72 Potential Whole-body Donors: 13 Special Studies: 7

Deceased Registrants: 332 Partial-body Donations: 291 Whole-body Donations: 36 Special Studies: 5

Inactive Registrants: 447 Total Number of Registrants: 871


The Registries: Historical Profile of Partial Body Donations(“Routine” Autopsy Cases)


Major USTR Landmark: 1st Whole Body Donation (1979)

• Donor (radiochemist) worked with unsealed 241Am source in his doctoral research (1952-54)

• First indication of intake was detection of 241Am in urine sample (1958 routine surveillance program) – No chelation therapy

• Contemporary estimate of intake 0.23 – 1.1 μCi (~ 8 – 40 kBq!)


USTUR: Historical Profile of Whole Body Donations


Year of Intake for USTUR Whole Body Donors


USTUR: Trends in Donations (This Decade)


FY2008 Whole-Body Donations

• January: 87-y-old 239Pu-contaminated puncture wound(s) (Hanford – 1960s).

•March: 95-y-old 239PuO2 acute inhalation (Rocky Flats – 1965 Pu fire – high intake).

•March: 72-y-old 241AmO2 chronic inhalation (U.S. Radium Corporation – 1960s – very high intake – heavily chelated).

• September: 83-y-old U3O8-fume acute inhalation (Hanford – 1948 – up to 300 μg-U/d in urine).


USTUR Web Site – Case Narrative for Registrant 0846


USTUR Web Site – Narrative File Downloads for Registrant 0846


Case #0846 Urine Data – Years 2-3


Post Mortem 241Am External Counts (PNNL) – With and Without Lungs


Case #0846: External Counts Pre- and Post-Autopsy


NHRTR – FY2008: THEMIS Bar-coded Sample Inventory Chain of Custody/Database System


THE Management Information System (THEMIS™)

• Integrates with barcode scanner to inventory: USTUR tissues,

histopathologic slides, and acid solutions.

National Human Tissue Repository (NHRTR) tissues and bone ash.

National Radiobiology Archives (NRA) histopathologic slides, tissue blocks, and documents.


The Management Information System (THEMIS)

Assigns a unique barcode to each individual sample.

Records a sample’s mass or volume.

Tracks the sample’s current location as it is moved within the NHRTR facility (e.g., from one freezer to another).

Tracks the sample’s location (e.g., as it is ‘shipped’ for radiochemical analysis).


NHRTR also holds thousands of acid-dissolved tissue samples!

• USTR & USUR (pre-1992)- Analyses carried out primarily by Los Alamos (LASL/LANL).

• USTUR (1992-2006)- Analyses carried out by Washington State University (WSU)- Nuclear Radiation Center (NRC), Pullman, WA.

• USTUR (2006-2008)- Limited analyses carried out in temporary (leased) laboratory at

Columbia Basin College, Pasco, WA (no tissue digestion facilities).

- Tried “full-service” commercial laboratories.- New separations procedures and ICP-MS.

• USTUR (2009+)- New (leased) “in-house” radiochemistry facilities.

Radiochemistry: Tissue Sample Actinide Separation and Measurement

HPA/CRCE Seminar – ACJ – April 2nd, 2009

9) Pu Elution: 30 mL0.1M HCl - 0.05M HF - 0.04M rongalite

5) Beaker rinse: 5 mL 6MHN03

6) Separate cartridges 7) TEVA rinse: 15 mL 3M HNO3

8) Rinse: 25 mL 9M HCl (Th)

1) Sample in 12 mL warm 6M HN03 and 12mL 2M Al(NO3)3

2) Add 0.75 mL 1.5M Sulfamic Acid + 3 mL 1.5M Ascorbic Acid3) Add 2.5 mL 3.5 M Sodium Nitrite4) Sample loading (1 drop sec-1)

2 mL TEVA Resin(50-100 m)

2 mL TRU-Resin (50-100 m)

Alpha spectrometry (USTUR-600)

Electrodeposition (USTUR-510)

2 mL DGA-Resin (50-100 m)

Waste (4 – 8)

Radiochemistry: Actinide Column Separation- New Method (Adapted from Maxwell & Faison, 2008)

Radiochemistry in USTUR Program

(6)(9)

Actinide Column Separation (II)

10) Am to DGA: 15 mL 4M HCl11) Separate cartridges

Waste (10)

2 mL TRU-Resin (50-100 m)

2 mL DGA-Resin (50-100 m)

TRU – DGA cartridges from (I) Step 6

14) Am Elution: 10 mL 0.25M HCl

Alpha spectrometry (USTUR-600)

Electrodeposition (USTUR-510)

12) Rinse: 3 mL 1M HNO3

13) Rinse: 10 mL 0.1M HNO3 (U)

Waste (12,13)

Radiochemistry in USTUR Program

(11)

(14)

Radiochemistry

Actinide Separation: Comparison of Results

(a) 239Pu (b) 241Am

Radiochemistry

Comparison of Analytical Performance: USTUR-150-220-310 vs. TEVA-TRU-DGA

Description USTUR 150-220-310 TEVA-TRU-DGA

Separation techniqueExtraction

chromatography + anion exchange (gravity fed)

Extraction chromatography

(vacuum-assisted)

Sample loading 3 times once

Number of samples in batch 18 24

Reagents used 345 mL/sample 110 mL/sample

Time for Pu/Am separation 5+ days 1 day

SF/ICP-MS: Anthropogenic 236U

Uranium (nat.) atom ratio:• 235U/238U = 0.00725• 234U/235U = 0.00763• 236U/238U = 0.000

Not previously measurable in USTUR/NHRTR samples.

1028.001 (liver)

ICP-MS in USTUR Program

SF/ICP-MS: Determination of 241Pu

241Pu • T1/2 = 14.1 y, -emitter• not detectable by -spectrometry241Pu was detected in:

• 269.003 (liver)• 269.031 (femur, PE)• 269.052 (humerus, PE)• 720.001 (lung)• 720.004 (liver)


SF/ICP-MS (at NAU) vs -spectrometry


Benefits & Limitations of ICP-MS

•Rapid analysis (10 min vs 42 hr for -spectrometry)

•Low detection limits

•High precision (1-3 %)

•240Pu/239Pu isotopic ratio measurement

•236U and 241Pu detection

•Limited for 241Am and 238Pu determination c.f. AS


New Frontier: Laser Ablation ICP-MS

LA-ICP-MS in USTUR Program

Philip Doble, Ph.D., Senior Lecturer, Department of Chemistry & Forensic Science, University of Technology, Sydney, Australia

Application of LA-ICP-MS to USTUR/NHRTR

LA-ICP-MS: Potential Applications to USTUR/NHRTR

•Spatial distribution of actinides, 226Ra and major matrix elements (Ca, Mg, Sr, P) in autopsy samples

•Actinide and 226Ra concentration measurements

•Others?


Web Publication of Tissue Analysis Results

• Self-selected for relatively “high” (recorded) intakes of transuranium elements – primarily 239Pu/238Pu/241Am.

•Additional exposure to external radiation (/n).• In majority of cases, there is also additional exposure to

industrial toxic materials- Beryllium (Be), asbestos, toxic chemicals, organic solvents, benzene/toluene.

•Any pathological findings are SUMMED effects of “natural” disease incidence (including “normal” incidence of malignant cancer in matched, non-exposed population) and ALL occupational exposure factors.

• Some self-selection for existing cancer (Rocky Flats Plant).

Exposure Characteristics of USTUR Registrants



USTUR Internal Database – Pathology


Pathology Database – Case Report

Malignant Neoplasms as Primary Cause of Death in USTUR Registrants(with Exposure Co-Factors): 1. ICD-10 Codes C02.9 – C20

SEER: Surveillance, Epidemiology & End Results - http://seer.cancer.gov/

Case No. Source ICD-10 Site Fraction (85%)

Smoker Be Asbestos Toxic_Chem Solvents Benzene/Toluene

SEER 1975-2005

All Neoplasms Count = 111/317 35.0%0047 D C02.9 Tongue - - - - - - 0094 A C12 Hypopharynx 2.7% Y N Y Y Y - 1.9%0640 A C14.0 Pharynx Y N N N N - 0055 D C15.9 Esophagus - - - - - -0096 D C15.9 Esophagus 3.6% - - - - - - 2.5%0206 A C15.9 Esophagus - - - - - -0817 A C15.9 Esophagus Y Y Y Y Y Y0015 D C16.9 Stomach Y - - Y - Y 0030 D C16.9 Stomach 3.6% - N N N N N 3.0%0142 D C16.9 Stomach - - - - - - 0650 A C16.9 Stomach Y Y - Y Y - 0644 A C18.5 Colon Y N Y Y Y N 0183 D C18.9 Colon - N N N N N 0458 A C18.9 Colon 4.5% Y Y Y Y Y Y 0503 D C18.9 Colon N - - - - - 11.5%0325 A C18.9 Colon Y Y Y - Y -0095 D C19 Rectum - - - - - - 0260 D C19 Rectum 2.7% - - - - - - 0101 D C20 Rectum Y N N N N N

Malignant Neoplasms as Primary Cause of Death in USTUR Registrants(with Exposure Co-Factors): 2. ICD-10 Codes C22 – C25.9


Case No. Source ICD-10 Site Fraction Smoker Be Asbestos Toxic_Chem Solvents Benzene/

TolueneSEER

1975-2005

0262 D C22.0 Liver N Y - - - -

0306 A C22.1 Liver Y N N N Y N

0147 D C22.9 Liver 5.4% Y N N N N N 1.9%

0371 A C22.9 Liver Y N - Y Y -

0446 A C22.9 Liver Y Y Y N Y Y

1054 D C22.9 Liver - - - - - -

0054 D C24.1 Gallbladder 0.9% - - - - - - 0.3%

0099 D C25.0 Pancreas - - - - -

0104 A C25.0 Pancreas Y N N N N N

0461 A C25.2 Pancreas 4.5% Y N N N N N 4.9%

0341 A C25.9 Pancreas N Y N N N N

0846 D C25.9 Pancreas N Y - - N Y

Malignant Neoplasms as Primary Cause of Death in USTUR Registrants(with Exposure Co-Factors): 3. ICD-10 Codes C34.1 – C41.4


Case No. Source ICD-10 Site Fraction Smoker Be Asbestos Toxic_Chem Solvents Benzene/Toluene SEER 1975-20050240 A C34.1 Lung Y N N Y Y N 0255 A C34.1 Lung Y N Y Y Y N 0005 A C34.9 Lung Y - - - - - 0008 A C34.9 Lung Y N N N N N 0011 D C34.9 Lung Y - - - - - 0038 D C34.9 Lung Y - - - - - 0063 A C34.9 Lung N N N N N N 0064 A C34.9 Lung Y N N Y N N 0081 D C34.9 Lung Y - - - - - 0083 D C34.9 Lung - - - - - - 0091 D C34.9 Lung - - - - - - 0100 A C34.9 Lung Y N N N N N 0103 D C34.9 Lung - - - - - - 0149 A C34.9 Lung Y N N N - - 0161 D C34.9 Lung Y - - - - - 0185 D C34.9 Lung - - - - - - 0187 D C34.9 Lung Y - - - - - 0188 D C34.9 Lung - - - - - - 0197 D C34.9 Lung Y N - Y Y - 0203 D C34.9 Lung 31.5% - - - - - - 32.1%0205 A C34.9 Lung - - - - - - 0213 N C34.9 Lung Y N N N N N 0226 D C34.9 Lung Y N Y Y N - 0232 A C34.9 Lung - - - - - - 0247 A C34.9 Lung N N Y Y N - 0252 D C34.9 Lung Y N - Y Y - 0334 A C34.9 Lung Y Y Y Y Y N 0375 A C34.9 Lung Y - - - - - 0669 A C34.9 Lung Y N N N N N 0720 A C34.9 Lung Y Y N N N N 0727 A C34.9 Lung Y Y - Y Y - 0779 D C34.9 Lung Y - - - N - 0841 A C34.9 Lung Y N Y - Y - 1036 A C34.9 Lung Y - - Y - - 1065 A C34.9 Lung Y - Y - Y Y 1059 A C40.2 Bone 1.8% - - - - - - 0.2%0769 A C41.4 Bone - - - - - -

Malignant Neoplasms as Primary Cause of Death in USTUR Registrants(with Exposure Co-Factors): 4. ICD-10 Codes C43.6 – C63.9


Case No. Source ICD-10 Site Fraction Smoker Be Asbestos Toxic_Chem Solvents Benzene/Toluene SEER 1975-2005

0158 A C43.6 Skin (Melanoma) - - - - - -

0041 D C43.9 Skin (Melanoma) 3.6% - - - - - - 1.3%

0102 D C43.9 Skin (Melanoma) Y N Y Y N -

0245 A C43.9 Skin (Melanoma) Y N Y Y N -

0084 D C45.0 Mesothelioma N - - - - -

0256 D C45.0 Mesothelioma Y Y Y Y Y -

0648 A C45.0 Mesothelioma 5.4% N Y Y Y Y - -

1040 D C45.0 Mesothelioma - N - Y Y -

0677 A C45.7 Mesothelioma N - - Y - -

0013 D C45.9 Mesothelioma N N N Y N N

0020 D C50.9 Breast 0.9% Y - - - - - -

0079 D C55 Uterus 0.9% Y N N N N N -

0022 D C61 Prostate Y N - Y N -

0058 D C61 Prostate - - - - - -

0189 D C61 Prostate Y - - - - -

0253 D C61 Prostate 6.3% - - - - - - 12.8%

0269 A C61 Prostate Y N N N N N

0425 A C61 Prostate N Y - - - -

0778 A C61 Prostate Y Y Y Y Y Y

1030 A C63.9 Penis 0.9% Y N N - N N 0.0%

Malignant Neoplasms as Primary Cause of Death in USTUR Registrants(with Exposure Co-Factors): 5. ICD-10 Codes C64 – D46.9


Case No. Source ICD-10 Site Fraction Smoker Be Asbestos Toxic_Chem Solvents Benzene/

TolueneSEER

1975-20050092 D C64 Kidney - - - - - -0199 D C64 Kidney 2.7% - - - - - - 2.3%1007 A C64 Kidney Y - - Y - -0028 D C67.9 Bladder Y - - - - - 0106 A C67.9 Bladder 2.7% - - - - - - 3.5%0992 A C67.9 Bladder Y Y Y Y - - 0027 D C71.9 Brain - N N N N N0049 D C71.9 Brain - - - - - -0085 D C71.9 Brain - - - - - -0146 D C71.9 Brain 6.3% Y - - - - - 1.8%0216 D C71.9 Brain - - - - - -0228 D C71.9 Brain - - - - - -0107 A C72.4 Nervous System - - - - - -0156 D C78.5 Lung/Colon (Met) Y N - Y Y - -0044 D C79.0 Kidney (Met) - - - - - -0445 D C79.0 Kidney (Met) Y Y N N Y N0032 A C85.0 Lymphosarcoma 0.9% - N N N N N -1044 D C85.9 NH Lymphoma 0.9% Y Y - Y N - 3.4%0794 A C90.0 Multiple Myeloma 0.9% Y N N N Y - 1.7%0035 D C91.0 AL Leukemia 0.9% - - - - - - 0.1%0194 D C92.1 CM Leukemia 0.9% - - - - - - 0.4%

1001 D C95.0 AU Leukemia Thorotrast Injection (Female)

0274 A D45 Polycythaemia vera 0.9% Y - - Y - - -

0397 A D46.9 Myelodysplastic syndrome 0.9% Y N N N - - -


USTUR Pathology Database – Now on the Web (April 6th, 2009)!


Summary of Preliminary Findings on USTUR Registrants (Through 2008)

• No significant association found between [preliminary/rough estimates of ] tissue-weighted equivalent dose received and malignant cancer as a primary (or secondary) cause of death (α = 0.05).

• Statistically significant associations found between cause of death due to any type of cancer and exposure to:- benzene or toluene (odds ratio = 5.71; 95% CI: 1.04 to 31.34)- smoking habit (odds ratio = 5.41; 95% CI: 1.42 to 20.67)- rate of cigarette smoking (odds ratio = 2.70; 95% CI: 1.37 to 5.30).

• Lung cancer deaths found to be related to exposure to:- chlorinated solvents (odds ratio = 10.85; 95% CI: 1.02 to 115.16)- duration of exposure to these materials (odds ratio = 1.12; 95% CI: 1.01 to 1.24).

Source: Fallahian,N. A. “Study of the Association Between Exposure to Transuranic Radionuclides and Cancer Death,” PhD Dissertation, Idaho State University, 2008


USTUR Data Enable Detailed Reconstructions of Tissue Doses Received by Individual Donors – Example of USTUR Case 0262

• Worked as engineer at Hanford (1951-82).• Died 1990 – at age 71 y.• Cause of death:

- hepatocellular carcinoma (ICD-10 Code C22.0) - with metastases in diaphragm, lungs and liver.

• At autopsy:- all major soft tissue organs harvested, including axillary lymph node (for radiochemistry and NHRTR sample storage);- Skin of both hands saved for histology/autoradiography;- Bones from half skeleton dissected out – for radiochemistry;- Contents of 238Pu, 239+240Pu, 241Am measured for all tissues/organs.


Health Physics/Incident Data for USTUR Case 0262

• Two suspected Pu inhalation intakes (1956) – of nominally ‘fresh’ weapons grade material:- 1,834 days after starting Pu work, exposed to substantial airborne Pu concentration (no respirator);- 2 weeks later, both hands contaminated (10,000 dpm Pu);- Inhalation intakes from both incidents indicated by measurable Pu α-activity in prompt urine sample – subsequent samples negative (i.e., < 0.025 dpm per 24-h sample).

• Third Pu intake occurred about 500 d later – by puncture wound of left thumb (broken drill bit through glove) while working in glove box:- No general airborne release;- Initial count rate (α-probe) from contaminated wound surface 500 cpm.


“Biokinetic” Model for Wound/Inhalation Plutonium Uptake and Tissue Retention

Source: James, A.C., et al. “USTUR Whole Body Case 0262: 33-y Follow-up of PuO2 in a Skin Wound and Associated Axillary Node.” Radiat. Prot. Dosim. 127: 114-119 (2007)


Measured and “Modeled” Excretion of 239Pu in Urine for Case 0262



Measured and “Modeled” 239Pu Content of Tissues (At Autopsy)for Case 0262



Use “Modeled” Biokinetics (Intake and Absorption Behavior) to Calculate Equivalent Dose Received by Liver in Each Year (After Intakes)


NIOSH-IREP “Probability of Causation” Software - on the Web


Run Calculated Annual Equivalent Doses Through “Interactive RadioEpidemiological Program” (NIOSH-IREP) – as Done for EEOICPA


NIOSH-IREP “Probability of Causation” Results – Case 0262

Legal Standard

EEOICPA Standard


Distribution of Equivalent Dose Rate to Liver (Measured at Death) for USTUR Registrants

th International Congress of the International

Radiation Protection Association (IRPA)Buenos Aires, Argentina

October 8th- 24th, 2008

Uncertainty in Internal Doses: Using Bayes to TransferInformation from One Worker to Another

Scenario

• Comprehensive bioassay follow-up of a worker who accidentally inhaled 241AmO2 yields knowledge of the lung absorption behavior of this material.

• Can this knowledge be applied rigorously to improve dose estimates for another worker inhaling same material (with relatively sparse bioassay data and unknown time of intake)?

• Demonstrate use of the Weighted Likelihood Monte Carlo Sampling (WeLMoS) method (Puncher and Birchall, 2008) to derive posterior probability distributions of doses for the second worker. 5-month aqueous suspension

James, A.C.,1 Birchall, A.2 and Puncher, M.2

1United States Transuranium and Uranium Registries, 1854 Terminal Drive, Richland, WA 99354, USA2 Health Protection Agency-Radiation Protection Division, Chilton, Oxon OX11 0RQ, UK

USTUR Case 0855 – “Special Bioassay Study”

James, Birchall & Puncher: IRPA 2008 – TS-I.1.2

•Accidental, single acute inhalation—1996.

• Examining old ‘sealed’ 241AmO2 powder source.

• Loose 241Am contamination in work area (hotspots > 1 kBq/100 cm2).

• Healthy, 38-y-old non-smoker.

• 6 weeks after intake volunteered for USTUR “Special Study”—long-term bioassay.

• 6-y follow-up published by Kathren et al. (2003).

• Bioassay data re-analyzed here using IMBA Professional Plus (IPP).

ICRP68 Type ‘M’:2 = 2,470; NDF = 30ICRP68 Type ‘M’:2 = 2,470; NDF = 30

Does NOT behave like Type ‘M’ (or ‘S’) material.Does NOT behave like Type ‘M’ (or ‘S’) material.

Bayesian Analysis of Case 0855 Bioassay Data


Clean-up Worker – Classical Analysis (Maximum Likelihood)


• Actual time-course of intake not known.

• Must be inferred from periodic (routine) urine samples.

• Earliest ‘positive’ urine collected at 106.5 d after start of employment.

• Previous ‘negative’ at 24 d.

• Assume constant chronic intake throughout this interval.

• Assume modal absorption parameters from Case 0855

• Calculated χ2 = 13.0;NDF = 8; P = 0.11.

• ‘Most likely’ point estimates of intake/dose: I = 1,229 Bq E = 38 mSv HBS = 685 mSv Hlungs = 46 mSv.

• What are uncertainties in these estimates?

Clean-up Worker – Bayesian Analysis (Un-informative Priors)


•Resulting mean estimates of dose: E = 47 mSv (95% credible interval 34 – 62 mSv)

HBS = 929 mSv (95% credible interval 661 – 1,249 mSv).• These estimates were produced with NO explicit knowledge (assumption) of absorption rates from the lungs.

Clean-up Worker – Bayesian Analysis (Informative Priors)


Using Bayes - Conclusion


•In this particular example (of an exposed clean-up worker), the quality of

the bioassay data is sufficient to define reasonably accurately the posterior

distributions of dose—even without any information on the absorption

behavior of inhaled 241AmO2.

• Thus, the reduction in uncertainty using specific information of absorption

is not as great as it could be.

• In cases with less reliable bioassay data, the Bayesian method

automatically places greater reliance on prior knowledge.

• In cases with no bioassay data, i.e., prospective dose assessments,

absolute reliance must be placed on prior knowledge (or assumptions)

about the applicable Human Respiratory Tract Model (HRTM) parameter

values.


Current Active Registrants: Potential Whole-Body Donors Total Registrants (WB) = 13: Average age 78 y (± 14 y) Excluding #0263: Average age 81 y (± 8 y)

Case No Birth Date Age, y Site

0249 1918 90 LOS

0263 1972 36 HAN

0266 1943 65 ROC

0272 1922 86 HAN

0409 1924 84 ROC

0433 1928 80 ROC

0631 1925 82 LOS

0634 1924 84 LOS

0674 1934 73 HAN

0740 1918 90 HAN

0757 1922 86 CHI

0816 1926 81 ROC

0842 1936 71 MND

(As of March 25th, 2009)


USTUR Organization – FY2009 (Planned)


USDOE Headquarters Organization

Karlsruhe Institute of Technology (KIT), Germany, April 7th, 2009

Disclaimer: “This presentation was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.”

slide 1 the u.s. transuranium & uranium registries (ustur): the fifth decade of nuclear worker...

Documents

decade slide

usaec vision slide

uranium workers year

registrant status ustur

cradp ustur director

partialbody donations

potential partialbody

deceased registrants