Some Suggested Maximum Permissible Single in Takes of Uranium

Is, Eve

doi:10.1097/00004032-196411000-00001

Cited by 7 publications

(3 citation statements)

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“…Guidance for a maximum single acute intake of 2.5-mg uranium in any one day was provided in ICRP 6 (1964), based on work by Eve (1964). However, Eve's analysis was derived from the assumption that a daily intake of 2.5 mg of uranium could be tolerated without harm (i.e., chronic exposure of 2.5 mg/d).…”

Section: Chemical Toxicitymentioning

confidence: 99%

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Carbaugh¹,

Bihl²,

MacLellan³

2003

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PrefaceThis manual provides the scientific and technical foundations for bioassay program design and interpretation, and for the assessment of occupational intakes and internal doses. The Hanford Internal Dosimetry Project Manual (PNNL-MA-552) (a) applies these foundations to define the recommended worker bioassay monitoring programs and internal dose assessment efforts at the Hanford Site.According to the DOE Internal Dosimetry Program Guide (DOE G 441.1-3, 03-17-99), a technical basis document should record the approach to evaluating internal doses from bioassay data, and where appropriate, from workplace monitoring data. It should also describe the physical and chemical characteristics of radioactive materials encountered in the workplace; methods for calculating internal doses and dose equivalents and the methods for documenting those calculations; dose evaluation quality assurance; recording and reporting practices for internal dosimetry; selection of workers for monitoring; and establishment of the type and frequency of measurements to be used. Furthermore, statistical methods for evaluating bioassay data, identifying bioassay results above environmental background values, using appropriate blanks, and analyzing trends should be described.This manual describes the basic methods and biokinetic models used for bioassay program design, interpretation, and internal dose assessment. These methods and models are combined with good practices and professional judgment to give the operational recommendations for routine and special bioassay monitoring contained in the Hanford Internal Dosimetry Project Manual (PNNL-MA-552). The actual selection of workers for monitoring and the characterization of the physical, chemical, and radiological properties of contaminants in the many Hanford facilities are the domain of the individual Hanford contractors.The recommendations in this manual are provided as guidance, not requirements, to personnel responsible for designing and operating bioassay monitoring programs and evaluating bioassay results. Commitments by contractors to use these recommendations may be found in the contractor radiation protection plans. This manual is on a 3-year revision schedule, however individual sections are revised as necessary, and upon revision, commence their own 3-year revision cycle.

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Section: Chemical Toxicitymentioning

confidence: 99%

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Carbaugh¹,

Bihl²,

MacLellan³

2003

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“…Guidance f o r a maximum s i n g l e acute i n t a k e of uranium has been provided i n ICRP 6 (1964), based on work by Eve (1964). Eve's a n a l y s i s was derived from t h e assumption t h a t a d a i l y i n t a k e of 2.5 mg of uranium could be t o l e rated without harm.…”

Section: Acute Exposurementioning

confidence: 99%

Technical basis for internal dosimetry at Hanford

Sula¹,

Carbaugh²,

Bihl³

1991

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The Hanford Internal Dosimetry Program, administered by Pacific Northwest ~aborator~(~) for the U.S. Department o f Energy, provides routine bioassay monitoring for employees who are potenti a1 ly exposed to radionucl ides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of 58 concern include tri t i um, corrosion products (Co, 60~o, 54~n, and 59~e), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mi tigation; and bioassay follow-up treatment. (a) Pacific Northwest Laboratory is operated by Battell e Memorial Institute for the U.S. Department of Energy under Contract DE-AC06-76RLO 1830. ACKNOWLEDGMENTS In the production of this report, the authors gratefully acknowledge the invaluable support of R. J. Traub as peer reviewer, S. K. Ennor as editor, and Marge Johnston, Marianna Cross, Rose Moreno, and Margot White as word processors.

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“…(1962). Ten mg inhaled is suggested as a maximum emergency planned occupational dose (Eve 1964). Little information is available on fatal inhalation or ingestion levels.…”

Section: Health Effectsmentioning

confidence: 99%

Analysis of the risk of transporting uranium ore concentrates by truck

Geffen¹

1981

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This report evaluates the risks involved with shipping uranium ore concentrates by truck in an attempt to provide some perspective on the system safety issues. The basic probabilistic risk evaluation methodology used in this study is similar to that employed by Pacific Northwest Laboratory (PNL) in a series of risk analyses on the transportation of potentially hazardous energy materials. The risk model has been constructed as a series of separate analysis steps to allow the system risk to be readily reevaluated as additional data become available or as postulated system characteristics change. The results of this analysis show that the risks to the public health and safety from yellowcake releases during a transportation accident are insignificant. Accidents involving truck shipments of yellowcake are expected to occur at a rate of about ten a year. However, only one-fifth of these accidents, or about two a year, are expected to cause a release of yellowcake to the environment. None of these accidents was estimated to produce any potential fatalities. The low concentration of radioactivity distributed throughout the material resulted in no significant increase in radiation doses above normal background levels to members of the general public.

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Some Suggested Maximum Permissible Single in Takes of Uranium

Cited by 7 publications

References 0 publications

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Technical basis for internal dosimetry at Hanford

Analysis of the risk of transporting uranium ore concentrates by truck

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