Analysis for actinides in tissue samples from plutonium workers of two countries

Filipy, R.E.; Khokhryakov, V. F.; Суслова, К. Г.; Романов, С. А.; Stuit, D. B.; Aladova, E. E.; Kathren, R.L.

doi:10.1007/bf02389767

Cited by 17 publications

(5 citation statements)

References 5 publications

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“…Additionally, any workers who were involved in documented accidents were excluded from the study. A complete description of the autopsy program, including the analytical methods, can be found in Filipy et al (1998) and Suslova et al (1996Suslova et al ( , 2003Suslova et al ( , 2006. The characteristics of the cases used in this study are presented in Table 1.…”

Section: Characteristics Of Casesmentioning

confidence: 99%

Development of an Inhalation Intake Model for 241Am Based on Mayak Production Association Worker Data

Sokolova¹,

Суслова²,

Khokhryakov³

et al. 2013

Health Physics

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VAmericium-241 is a significant radiation hazard at facilities that handle or reprocess spent nuclear fuels. An inhalation intake model for 241 Am was developed using autopsy data obtained from former workers at the Radiochemical and Plutonium Production Plants at the Mayak Production Association (Mayak PA), Ozyorsk, Russia. Accumulation of 241 Am in the body can occur though direct exposure to 241 Am (termed here ''exogenous'' exposures), usually as an inhaled aerosol, or though exposure to 241 Pu that decays inside the body to 241 Am (termed here ''endogenous'' exposures). Metabolism of endogenous and exogenous 241 Am can differ, with endogenous 241 Am being initially related to the behavior of 241 Pu. For the model, it was assumed that intakes of 241 Am and 241 Pu were functionally associated with intakes of 239 Pu. The current Mayak Worker Dosimetry System model (MWDS-2008) was used to describe metabolism of plutonium and americium in the respiratory tract. The ICRP-30 model was used for the gastrointestinal tract, the ICRP-67 model was used for metabolism after absorption into the blood for americium, and the ''Leggett modification'' of the ICRP-67 model for plutonium was used for systemic, non-pulmonary organs. The proposed inhalation intake model for americium provides estimates for internal doses from 241 Am from both exogenous and endogenous sources. Health Phys. 105(1):21Y30; 2013

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Section: Characteristics Of Casesmentioning

confidence: 99%

Development of an Inhalation Intake Model for 241Am Based on Mayak Production Association Worker Data

Sokolova¹,

Суслова²,

Khokhryakov³

et al. 2013

Health Physics

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“…From 1998 to 2008, the assays were done using more sensitive alpha-spectrometry methods. The radiochemical procedures and associated limitations and uncertainties for these methods have been described in greater detail [ 13 , 18 – 20 ].…”

Section: Methodsmentioning

confidence: 99%

“…methods. The radiochemical procedures and associated limitations and uncertainties for these methods have been described in greater detail [13,[18][19][20].…”

Section: Plos Onementioning

confidence: 99%

The effects of chronic diseases on plutonium urinary excretion in former workers of the Mayak Production Association

et al. 2020

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The radiochemical analysis of plutonium activity in urine is the main method for indirect estimation of doses of internal exposure from plutonium incorporation in professional workers. It was previously shown that late-in-life acute diseases, particularly those that affect the liver, can promote accelerated rates of release of plutonium from the liver with enhanced excretion rates. This initial study examines the relationships of some chronic diseases on plutonium excretion as well as the terminal relative distribution of plutonium between the liver and skeleton. Fourteen cases from former workers at the Mayak Production Association (Mayak PA) who provided from 4–9 urine plutonium bioassays for plutonium, had an autopsy conducted after death, and had sufficient clinical records to document their health status were used in this study. Enhanced plutonium excretion was associated with more serious chronic diseases, including cardiovascular diseases and other diseases that involved the liver. These chronic diseases were also associated with relatively less plutonium found in the liver relative to the skeleton determined by analyses conducted after autopsy. These data further document health conditions that affect plutonium biokinetics and organ deposition and retention patterns and suggest that health status should be considered when conducting plutonium bioassays as these may alter subsequent dosimetry and risk models.

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“…Pu) and americium ( 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 Association (DRMIA), require dry/wet ashing and dissolution in mineral acids followed by radiochemical separation and alpha-spectrometric detection of the actinides 8 . A similar method was used to measure the plutonium content of tissues and bones from residents of Tokyo (Japan) 9 .…”

Section: 239+240mentioning

confidence: 99%

“…Traditionally, the measurement of plutonium ( 238,239+240 Pu) and americium ( 241 Am) in biological samples has relied upon radiometric analysis. Radiochemical methods for the analysis of human tissues, previously reported by both the USTUR and the Russian Dosimetry Registry of the Mayak Industrial Association (DRMIA), require dry/wet ashing and dissolution in mineral acids followed by radiochemical separation and α-spectrometric detection of the actinides . A similar method was used to measure the plutonium content of tissues and bones from residents of Tokyo (Japan) …”

mentioning

confidence: 99%

Elemental Bio-imaging of Thorium, Uranium, and Plutonium in Tissues from Occupationally Exposed Former Nuclear Workers

et al. 2010

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Internal exposure from naturally occurring radionuclides (including the inhaled long-lived actinides (232)Th and (238)U) is a component of the ubiquitous background radiation dose (National Council on Radiation Protection and Measurements. Ionizing radiation exposure of the population of the United States; NCRP Report No. 160; NCRP: Bethesda, MD, 2009). It is of interest to compare the concentration distribution of these natural alpha-emitters in the lungs and respiratory lymph nodes with those resulting from occupational exposure, including exposure to anthropogenic plutonium and depleted and enriched uranium. This study examines the application of laser ablation-inductively coupled plasma-mass spectrometry (LA-ICPMS) to quantifying and visualizing the mass distribution of uranium and thorium isotopes from both occupational and natural background exposure in human respiratory tissues and, for the first time, extends this application to the direct imaging of plutonium isotopes. Sections of lymphatic and lung tissues taken from deceased former nuclear workers with a known history of occupational exposure to specific actinide elements (uranium, plutonium, or americium) were analyzed by LA-ICPMS. Using a previously developed LA-ICPMS protocol for elemental bio-imaging of trace elements in human tissue and a new software tool, we generated images of thorium ((232)Th), uranium ((235)U and (238)U), and plutonium ((239)Pu and (240)Pu) mass distributions in sections of tissue. We used a laboratory-produced matrix-matched standard to quantify the (232)Th, (235)U, and (238)U concentrations. The plutonium isotopes (239)Pu and (240)Pu were detected by LA-ICPMS in 65 mum diameter localized regions of both a paratracheal lymph node and a sample of lung tissue from a person who was occupationally exposed to refractory plutonium (plutonium dioxide). The average (overall) (239)Pu concentration in the lymph node was 39.2 ng/g, measured by high purity germanium (HPGe) gamma-spectrometry (Lynch, T. P.; Tolmachev, S. Y.; James, A. C. Radiat. Prot. Dosim. 2009, 134, 94-101). Localized mass concentrations of thorium ((232)Th) and uranium ((238)U) in lymph node tissue from a person not occupationally exposed to these elements (chronic natural background inhalation exposure) ranged up to 400 and 375 ng/g, respectively. In lung samples of occupationally nonexposed to thorium and uranium workers, (232)Th and (238)U concentrations ranged up to 200 and 170 ng/g, respectively. In a person occupationally exposed to air-oxidized uranium metal (Adley, F. E.; Gill, W. E.; Scott, R. H. Study of atmospheric contaminiation in the melt plant buiding. HW-23352(Rev.); United States Atomic Energy Commission: Oakridge, TN, 1952, p 1-97), the maximum (235)U and (238)U isotopic mass concentrations in a lymph node, measured at higher resolution (with a 30 mum laser spot diameter), were 70 and 8500 ng/g, respectively. The ratio of these simultaneously measured mass concentrations signifies natural uranium. The current technique was not sufficiently sensitive...

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Analysis for actinides in tissue samples from plutonium workers of two countries

Cited by 17 publications

References 5 publications

Development of an Inhalation Intake Model for 241Am Based on Mayak Production Association Worker Data

Development of an Inhalation Intake Model for 241Am Based on Mayak Production Association Worker Data

The effects of chronic diseases on plutonium urinary excretion in former workers of the Mayak Production Association

Elemental Bio-imaging of Thorium, Uranium, and Plutonium in Tissues from Occupationally Exposed Former Nuclear Workers

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