INREM II: a computer implementation of recent models for estimating the dose equivalent to organs of man from an inhaled or ingested radionuclide

Killough, G.G.; Dunning, D.E.; Pleasant, J.C.

doi:10.2172/6787367

Cited by 8 publications

(6 citation statements)

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“…By Donald E. Dunning, Jr., George G. Killough, and H. Robert Meyer An im portant step in assessing the radiological impacts resulting from the operation of nuclear-related facilities is the estimation of doses received by indi viduals and populations working at a facility or residing nearby. Estimates of the 50-year committed dose equivalents resulting from inhalation and ingestion of various radionuclides determined to be of potential importance in nuclear fuel cycles are compiled from recent documents by Killough et al (1978) and Dun ning et al (1979,1981). The estimates are computed with the computer code IN R E M II (Killough, Dunning, and Pleasant, 1978), which approximates the solutions of differential equations th at model intake, translocation, and metabo lism of a radionuclide and its progeny.…”

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

“…Estimates of the 50-year committed dose equivalents resulting from inhalation and ingestion of various radionuclides determined to be of potential importance in nuclear fuel cycles are compiled from recent documents by Killough et al (1978) and Dun ning et al (1979,1981). The estimates are computed with the computer code IN R E M II (Killough, Dunning, and Pleasant, 1978), which approximates the solutions of differential equations th at model intake, translocation, and metabo lism of a radionuclide and its progeny.…”

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

“…Formation and decay of radioactive daughters is treated explicitly by IN R E M II with each radionuclide in the decay chain having its own uptake and retention parameters. Detailed discussion of these models and assumptions is available in publications by Kil lough et al (1978), Dunning et al (1979 and, and Killough, Dunning, and Pleasant (1978).…”

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

“…5.0E-432 3.4E-10 7.3E-10 3.4E-10 1.6E-10 3.4E-10 1.5B-08 7.9E-09 "Bi 5.0E-02 l.lB -13 2.7E-13 2.7E-14 4.0E-14 2.4E-14 9.6E-15 (Table continues on 6.3E-12 next page.) equivalent for a more extensive set of organs may be found in references by Killough et al (1978) and Dunning et al (1979 and.…”

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

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Models and parameters for environmental radiological assessments

Miller¹

1984

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Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

Section: Estimates Of Committed Dose Equivalent From Internal Exposuresmentioning

confidence: 99%

See 2 more Smart Citations

Models and parameters for environmental radiological assessments

Miller¹

1984

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“…The RADPUR code contains subroutines for handling atmospheric dispersion (calculating x/0 values) as well as for calculating external gamma dose using either semi-infinite or finite plume models. It can and should be modified by Turner et al • 1968;Ki 11 ough et al 1975;Killough et al 1978Eckert 1964r.ouchman et al 1964 ~inford 1967 Strenge et al 1971Cooper 1967nahherdt et al • 1982U.S. NRC 1982Anno et al 1963Strenge et al 1975Scherpelz et al 1980 Chester 1974 the user to include site-specific information if availahle.…”

Section: Radpurmentioning

confidence: 99%

Dose-projection considerations for emergency conditions at nuclear power plants

Stoetzel¹,

Ramsdell²,

Poeton³

et al. 1983

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Analysis of Uncertainties in CRAC2 Calculations: The Inhalation Pathway

Killough

Dunning

1987

Uncertainty in Risk Assessment, Risk Management, and Decision Making

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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and °P'"' ons °f authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.CRAC2 is a computer code for estimating the health effects and economic costs that night result from a release of radioactivity from a nuclear reactor to the environment. This paper describes tests of sensitivity of the predicted health effects to uncertainties in parameters associated with inhalation of the released radionuclides. These parameters are the particle size of the carrier aerosol and, for each element in the release, the clearance parameters for the lung model en which the code's dose conversion factors for inhalation are based. CRAC2 uses hourly meteorological data and a straight-line Gaussian plume model to predict the transport of airborne radioactivity; it includes models for plume depletion and population evacuation, and data for the distributions of population and land use. The code can compute results for single weather sequences, or it can perform random sampling of weather sequences from the meteorological data file rmd compute results for each weather sequence in the sample. For the work described in this paper, we concentrated on three fixed weather sequences that represent a range of conditions. For each fixed weather sequence, we applied random sampling to joint distributions of the inhalation parameters in order to estimate the sensitivity of the predicted health effects. All sampling runs produced coefficients of variation that were less than 50%, but some differences of means between weather sequences were substantial, as werv> some differences between means and the corresponding CRAC2 results without random sampling. Early injuries showed differences of as much as 1-2 orders of magnitude, while the differences in early fatalities were less than a factor of 2. Latent cancer fatalities varied by less than 10%.

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INREM II: a computer implementation of recent models for estimating the dose equivalent to organs of man from an inhaled or ingested radionuclide

Abstract: NOTICEThis document contains information of a preliminary nature. It is subject to revision or correction and therefore does not represent a final report.

Cited by 8 publications

References 0 publications

Models and parameters for environmental radiological assessments

Models and parameters for environmental radiological assessments

Dose-projection considerations for emergency conditions at nuclear power plants

Analysis of Uncertainties in CRAC2 Calculations: The Inhalation Pathway

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