A Study of the Variations Found in Plutonium Urinary Data

Wd, Moss; Ee, Campbell; Hf, Schulte; Gl, Tietjen

doi:10.1097/00004032-196910000-00006

Cited by 23 publications

(3 citation statements)

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“…This GSD is smaller than the 'lognormal scattering factor (SF)' recommended in the guidelines produced from the IDEAS Project (29) . The default GSD value for a spot sample in the IDEAS General Guidelines is 2.0, however that was determined by Moss et al (30) based on urine plutonium, not uranium, measurements. For the Fernald mortality study internal dose assessment (7) , a GSD of 1.8 was used to describe the uncertainty in the urine bioassay data for the cohort.…”

Section: Resultsmentioning

confidence: 99%

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

Anderson

Apostoaei

Thomas

2012

Radiation Protection Dosimetry

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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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Section: Resultsmentioning

confidence: 99%

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

Anderson

Apostoaei

Thomas

2012

Radiation Protection Dosimetry

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“…At this point, a lognormal form is assumed for the distributions A and B for background types 1, 2 and 3. The lognormal assumption seems a good choice for two reasons: experimentally in agreeing with data (7) and also theoretically in that the product of independent lognormal random variables is again lognormal, allowing the covariance terms between the background and the normalisation coefficient to be evaluated with closed form expressions.…”

Section: Lognormal Distributionsmentioning

confidence: 99%

Poisson mixture model for measurements using counting

Miller

Justus

Востротин

et al. 2009

Radiation Protection Dosimetry

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Starting with the basic Poisson statistical model of a counting measurement process, 'extraPoisson' variance or 'overdispersion' are included by assuming that the Poisson parameter representing the mean number of counts itself comes from another distribution. The Poisson parameter is assumed to be given by the quantity of interest in the inference process multiplied by a lognormally distributed normalising coefficient plus an additional lognormal background that might be correlated with the normalising coefficient (shared uncertainty). The example of lognormal environmental background in uranium urine data is discussed. An additional uncorrelated background is also included. The uncorrelated background is estimated from a background count measurement using Bayesian arguments. The rather complex formulas are validated using Monte Carlo. An analytical expression is obtained for the probability distribution of gross counts coming from the uncorrelated background, which allows straightforward calculation of a classical decision level in the form of a gross-count alarm point with a desired false-positive rate. The main purpose of this paper is to derive formulas for exact likelihood calculations in the case of various kinds of backgrounds.

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“…However, the uncertainties in collection of a true 24-hr sample, possibilities of sample contamination, errors in chemical analysis and statistical variations in the extremely low level alpha counting introduce serious additional uncertainties in the final result (BEACH and DOLPHIN, 1964; Moss et al, 1969). However, the uncertainties in collection of a true 24-hr sample, possibilities of sample contamination, errors in chemical analysis and statistical variations in the extremely low level alpha counting introduce serious additional uncertainties in the final result (BEACH and DOLPHIN, 1964; Moss et al, 1969).…”

Section: Measurements On the Individual Workermentioning

confidence: 99%

Plutonium

Schulte¹

1975

Health Physics

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In evaluating the occupational environment to assess its hazard potential from the presence of plutonium, measurements must be made on the physical environment and on the worker. The most significant of the former are measurements of plutonium air concentration supplemented by particle size and duration of exposure estimates. These can only be very approximately estimated because of various compromises which must be made and are most useful as indicators of the effectiveness of the containment. Measurements on the worker such as urine assay and chest counting for plutonium also involve compromises and their interpretation involves assumptions based on limited and variable data. Information from analysis of tissue samples shows only a rough correlation with calculations based on urine assay data. Nevertheless, assemblage of all pertinent information from these measurements does permit real control of potential health hazards from work with plutonium.

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A Study of the Variations Found in Plutonium Urinary Data

Cited by 23 publications

References 0 publications

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

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

Poisson mixture model for measurements using counting

Plutonium

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