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EURADOS WG7 Meeting Forschungszentrum Karlsruhe GmbH, Institut für Strahlenforschung (ISF) Monday, April 6 th , 2009. Examples of Critical U.S. Transuranium & Uranium Registries (USTUR) Cases Involving Chelation Therapy. Anthony C. James, PhD, CRadP USTUR Director, Research Professor
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EURADOS WG7 Meeting Forschungszentrum Karlsruhe GmbH, Institut für Strahlenforschung (ISF) Monday, April 6th, 2009 Examples of Critical U.S. Transuranium & Uranium Registries (USTUR) Cases Involving Chelation Therapy Anthony C. James, PhD, CRadP USTUR Director, Research Professor College of Pharmacy Richland, WA 99354-4959, USA tjames@tricity.wsu.edu www.ustur.wsu.edu “Learning from Plutonium and Uranium Workers”
Explosion of ion-exchange column containing ~ 100 g 241Am Chemical operator injured – acid burns, superficial cuts (face and upper body) From 1 to 5 Ci (~ 40 – 200 GBq!) deposited on injured worker and his clothing Major USTR Landmark: 1976 Hanford 241Am Incident USTUR: Learning from Plutonium and Uranium Workers
USTUR Whole-body Case # 0269[James et al., 2007 (Montpellier, 2006)]
USTUR Case #0269 – Decorporation Treatments • Within a day of the accident, patient treated with i.v. Ca-EDTA: • 1 g per injection – per day. • Injection regimen 1-week-on, 1-week-off. • Continued for following 6 months. • Oral administration of Ca-EDTA – and various other “experimental” chelating agents – attempted over following years. • Intravenous Ca-DTPA: • 869 d – 0.2 g 2 • 870 d – 0.4 g 2 • 871 d – 0.6 g 2 • 872 → 952 d – 0.8 g 2 per day – intermittently. • 954 → 963 d – 1.0 g 2 per day – intermittently. • 1031 → 1642 d – 1.0 g 1 per day – intermittently.
USTUR Whole-body Case # 0269 – EDTA Modeling Results EDTA Flush Build-up Time Constant (Tissues) = 145 EDTA Excretion Build-up Time Constant (Urine) = 240 EDTA Excretion Enhancement Factor (to Urinary Path) = 5.100 EDTA Excretion Enhancement Factor (to Bladder) = 14.900 EDTA Tissue Uptake Factor = 1.000 EDTA Liver Clearance Factor = 1.370 EDTA Marrow Clearance Factor = 1.370 EDTA ST0 Clearance Factor = 1.370 EDTA ST1 Clearance Factor = 1.370 EDTA ST2 Clearance Factor = 1.370 EDTA Bone Surface Clearance Factor = 1.370
USTUR Whole-body Case # 0269 – DTPA Modeling Results DTPA Excretion Enhancement Factor (to Urinary Path) = 1.000 DTPA Urinary Path Flush Factor (to Bladder) = 1.000 DTPA Excretion Enhancement Factor (to Bladder) = 15.500 DTPA Tissue Uptake Factor = 0.000 DTPA Liver 2 Clearance Factor = 1.000 DTPA Liver 1 to Liver 2 Clearance Factor = 0.056 DTPA Liver 1 Fecal Factor = 0.500 DTPA Marrow Clearance Factor = 18.000 DTPA ST0 Clearance Factor = 1.440 DTPA ST1 Clearance Factor = 1.440 DTPA ST2 Clearance Factor = 1.440 DTPA Bone Surface Clearance Factor = 6.660
Autoradiographic Visualization of Bone Growth/Chelation Dynamics in the Weanling Rat • From James and Taylor, 1971 • Key • i.v. injection of citrate-buffered (monomeric) 239Pu(NO3)4 – 5 µCi/kg • 21 d untreated • DTPA at 7 d • DTPA at 30 min • From [b] - untreated • From [c] – DTPA 7 d • 1 d untreated
Web Publication of Tissue Analysis Results USTUR: Learning from Plutonium and Uranium Workers
SF/ICP-MS: Determination of 241Pu • 241Pu • T1/2 = 14.1 y, b-emitter • not detectable by a-spectrometry • 241Pu was detected in: • 269.003 (liver) • 269.031 (femur, PE) • 269.052 (humerus, PE) • 720.001 (lung) • 720.004 (liver) ICP-MS in USTUR Program
SF/ICP-MS (at NAU) vsa-spectrometry ICP-MS in USTUR Program
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: Learning from Plutonium and Uranium Workers
USTUR Web Site – Case Narrative for Registrant 0846 USTUR: Learning from Plutonium and Uranium Workers
USTUR Web Site – Case Narrative for Registrant 0846 USTUR: Learning from Plutonium and Uranium Workers
USTUR Web Site – File Downloads for Registrant 0846 USTUR: Learning from Plutonium and Uranium Workers
Case #0846 Urine Data – First Year USTUR: Learning from Plutonium and Uranium Workers
Case #0846 Urine Data – Second Year USTUR: Learning from Plutonium and Uranium Workers
Case #0846 Urine Data – Years 2-3 USTUR: Learning from Plutonium and Uranium Workers
Post Mortem 241Am External Counts (PNNL) – With and Without Lungs USTUR: Learning from Plutonium and Uranium Workers
External Counts Pre- and Post-Autopsy USTUR: Learning from Plutonium and Uranium Workers
NHRTR – FY2008: THEMIS Bar-coded Sample Inventory Chain of Custody/Database System USTUR: Learning from Plutonium and Uranium Workers
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). USTUR: Learning from Plutonium and Uranium Workers
Radiochemistry: Tissue Sample Actinide Separation and Measurement • 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. HPA/CRCE Seminar – ACJ – April 2nd, 2009
Comparison of Analytical Performance: USTUR-150-220-310 vs. TEVA-TRU-DGA Radiochemistry
Benefits & Limitations of ICP-MS • Rapid analysis (10 min vs 42 hr for a-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 ICP-MS in USTUR Program
New Frontier: Laser Ablation ICP-MS Phillip Doble, Ph.D., Senior Lecturer, Department of Chemistry & Forensic Science, University of Technology, Sydney, Australia LA-ICP-MS in USTUR Program
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? Application of LA-ICP-MS to USTUR/NHRTR
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!) Major USTR Landmark: 1st Whole Body Donation (1979) USTUR: Learning from Plutonium and Uranium Workers
Voxel Modeling of DOE 241Am Phantom (USTUR Case #0102) George Tabatadze M.S. (UNLV Medical Physics) - ISU Ph.D. Project USTUR: Learning from Plutonium and Uranium Workers
Voxel Modeling of DOE 241Am Phantom (USTUR Case #0102) George Tabatadze M.S. (ISU Graduate Student) USTUR: Learning from Plutonium and Uranium Workers
Voxel Modeling of DOE 241Am Phantom (USTUR Case #0102) George Tabatadze M.S. (ISU Graduate Student) USTUR: Learning from Plutonium and Uranium Workers
Potential ‘Phantom’ Resource? - Whole Limbs from Case #0846 USTUR: Learning from Plutonium and Uranium Workers
12th International Congress of the International Radiation Protection Association (IRPA) Buenos Aires, Argentina October 8th- 24th, 2008 Uncertainty in Internal Doses: Using Bayes to Transfer Information from One Worker to Another James, A.C.,1 Birchall, A.2 and Puncher, M.2 1United States Transuranium and Uranium Registries, 1854 Terminal Drive, Richland, WA 99354, USA 2 Health Protection Agency-Radiation Protection Division, Chilton, Oxon OX11 0RQ, UK • 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