Literature DB >> 22683620

Estimation of internal exposure to uranium with uncertainty from urinalysis data using the InDEP computer code.

Jeri L Anderson1, A Iulian Apostoaei, Brian A Thomas.   

Abstract

The National Institute for Occupational Safety and Health (NIOSH) is currently studying mortality in a cohort of 6409 workers at a former uranium processing facility. As part of this study, over 220 000 urine samples were used to reconstruct organ doses due to internal exposure to uranium. Most of the available computational programs designed for analysis of bioassay data handle a single case at a time, and thus require a significant outlay of time and resources for the exposure assessment of a large cohort. NIOSH is currently supporting the development of a computer program, InDEP (Internal Dose Evaluation Program), to facilitate internal radiation exposure assessment as part of epidemiological studies of both uranium- and plutonium-exposed cohorts. A novel feature of InDEP is its batch processing capability which allows for the evaluation of multiple study subjects simultaneously. InDEP analyses bioassay data and derives intakes and organ doses with uncertainty estimates using least-squares regression techniques or using the Bayes' Theorem as applied to internal dosimetry (Bayesian method). This paper describes the application of the current version of InDEP to formulate assumptions about the characteristics of exposure at the study facility that were used in a detailed retrospective intake and organ dose assessment of the cohort.

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Year:  2012        PMID: 22683620      PMCID: PMC4547353          DOI: 10.1093/rpd/ncs097

Source DB:  PubMed          Journal:  Radiat Prot Dosimetry        ISSN: 0144-8420            Impact factor:   0.972


  21 in total

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3.  A study of the variations found in plutonium urinary data.

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5.  Influences of parameter uncertainties within the ICRP-66 respiratory tract model: particle clearance.

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6.  Influences of parameter uncertainties within the ICRP-66 respiratory tract model: regional tissue doses for 239PuO2 and 238UO2/238U3O8.

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8.  Uncertainties in dose coefficients from ingestion of 131I, 137Cs, and 90Sr.

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9.  Voiding frequency in a sample of asymptomatic American men.

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  2 in total

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2.  Internal exposure to uranium in a pooled cohort of gaseous diffusion plant workers.

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  2 in total

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