BIO Web Conf.
Volume 14, 2019The 12th International Conference on the Health Effects of Incorporated Radionuclides (HEIR 2018)
|Number of page(s)||2|
|Section||Biokinetics and Bioaccumulation of Radionuclides: Oral presentations|
|Published online||07 May 2019|
Biokinetics of soluble plutonium after wound injury treated with Ca-DTPA
U.S. Transuranium and Uranium Registries, College of Pharmacy, Washington State University, 1845 Terminal Drive, Suite 201 Richland 99354 WA USA
* Corresponding author: firstname.lastname@example.org
The mission of the United States Transuranium and Uranium Registries (USTUR) is to study the uptake, translocation, retention and excretion (biokinetics), and tissue dosimetry of uranium, plutonium, americium, and other actinides in occupationally exposed volunteer Registrants (tissue donors). These individuals were mainly exposed to various types of plutonium material with inhalation and wound as primary routes of intake. The USTUR holds records on exposure history and bioassay measurements, as well as post-mortem tissue radiochemical analysis results for 19 individuals who had documented intakes of 239Pu due to contaminated wounds. For 8 individuals, internal deposition resulted from a single wound injury, and three of them were treated with decorporation therapy. In this study, USTUR Case 0303 was used to study biokinetics of soluble Pu after wound intake.
The USTUR whole-body donor (Case 0303) was employed at nuclear defence facility for 30 years. While working in a glove-box, he accidentally punctured his finger on a sharp object contaminated with plutonium nitrate. The contaminated tissue was surgically excised and found to contain approximately 2.33 kBq of 239Pu. A wound count performed four weeks later indicated that 59 Bq of 239Pu still remained in the finger. Worksite personnel estimated systemic deposition of 239Pu due to this accident as 85 Bq. This individual was medically treated with intravenous injections of Ca-DTPA. A total of 16 g Ca-DTPA was administered in 18 treatments during two months following the accident. Eighty-seven urine samples were collected and analysed over 14 years following the accident. This individual died 40 years post-intake at age 87.
Thirty-two soft tissue and 8 bone samples collected at autopsy were radiochemically analysed for 238Pu, 239Pu and 241Am. A complete description of the radiochemical analysis protocol has been described elsewhere . To estimate the plutonium intake, late urine measurements (past 100 days after the last Ca-DTPA injection), which were unaffected by chelation, and post-mortem radiochemical analysis results were evaluated using the IMBA Professional Plus® software .
Post-mortem radiochemical analysis of autopsy tissues indicated that forty years post-accident 12.2±0.3 Bq of 239Pu was retained in the liver and 17.5±0.7 Bq in the skeleton. Activity measured in the skin and muscle tissue sample from the wound site was 0.26±0.01 Bq while activity in the finger bone adjacent to the wound was measured as 1.09±0.03 Bq. Thus, a total of 1.35 Bq of 239Pu was retained in the wound.
Activity in the lungs including thoracic lymph nodes was estimated to be 0.14±0.01 Bq, two orders of magnitude lower than activity in the liver. This observation confirmed the assumption of the soluble plutonium intake via wound injury to be the major source of internal contamination for this individual.
Application of the NCRP 156 wound model  with default parameters for soluble strong material resulted in a credible fit to the data (p > 0.05) (Fig. 1). The residual intake was estimated to be 47.6 Bq and estimated committed effective dose was 24.1 mSv. By accounting for ~77.8 Bq of 239Pu excreted during Ca-DTPA treatment, the total intake was estimated to be 125 Bq. Without Ca-DTPA treatment, this individual would have received committed effective dose of 63.3 mSv. Chelation therapy reduced radiation dose by a factor of 2.6.
239Pu daily urinary excretion and Ca-DTPA treatment data
- S. Y. Tolmachev, M. E. Ketterer, D. Hare, P. Doble, A. C. James. Proc Radiochimica Acta 1, 173 (2011). [Google Scholar]
- A. Birchall, M. Puncher, J. W. Marsh, K. Davis, M. R. Bailey, N. S. Jarvis, A. D. Peach, M. D. Dorrian, A. C. James. Radiat Prot Dosim 125, 194 (2007). [Google Scholar]
- National Council on Radiation Protection and Measurements. NCRP Report 156, (2007). [Google Scholar]
© The Authors, published by EDP Sciences, 2019
This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.