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Part of the book series: Advances in Risk Analysis ((AIRA,volume 4))

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Abstract

CRAC2 is a computer code for estimating the health effects and economic costs that might result from a release of radioactivity from a nuclear reactor to the environment. This paper described 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 on 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 and 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 were 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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References

  • Bernard, S.R., and Snyder, W.S. 1975. “Metabolic Models for Estimation of Internal Radiation Exposure Received by Human Subjects from the Inhalation of Noble Gases,” p. 197 in Health Physics Division Annual Progress Report for Period Ending June 30, 1975, ORNL-5046, Oak Ridge National Laboratory.

    Google Scholar 

  • Dunning, D.E., Jr., Bernard, S.R., Walsh, P.J., Killough, G.G., and

    Google Scholar 

  • Pleasant, J.C., 1978. Estimates of Internal Dose Equivalent to 22 Target Organs for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities, Vol. II, NUREG/CR-0150 Vol. 2, ORNL/NUREG/TM-190/V2, Oak Ridge National Laboratory.

    Google Scholar 

  • Dunning, D.E., Leggett, R.W., and Yalcintas, M.G., 1980. A Combined Methodology for Estimating Dose Rates and Health Effects from Exposure to Radioactive Pollutants ORNL/TM-7105, Oak Ridge National Laboratory.

    Google Scholar 

  • Dunning, D.E., Jr., Killough, G.G., Bernard, S.R., Pleasant, J.C., and Walsh, P.J., 1981. Estimates of Internal Dose Equivalent to 22 Target Organs for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities Vol. III, NUREG/CR-0150 Vol. 3, ORNL/NUREG/TM190/V3, Oak Ridge National Laboratory.

    Google Scholar 

  • Dunning, D.E., Jr., and Eckerman, K.F., 1984. Estimates of Radiation Dose at Selected Times Following Acute Inhalation and Ingestion of Radionuclides NUREG/CR-3799, ORNL/TM-9192, Oak Ridge National Laboratory (in press).

    Google Scholar 

  • Iman, R.L., Conover, W.J., and Campbell, J.E., 1980. Risk Methodology for Geologic Disposal of Radioactive Waste: Small Sample Sensitivity Analysis Techniques for Computer Models, with an Application to Risk Assessment NUREG/CR-1397, SAND80–0020, Sandia National Laboratories.

    Google Scholar 

  • International Commission on Radiological Protection, 1972. The Metabolism of Compounds of Plutonium and Other Actinides ICRP Publication 19, Pergamon Press, Oxford.

    Google Scholar 

  • International Commission on Radiological Protection, 1975. Report of the Task Group on Reference Man, ICRP Publication 23, Oxford, Pergamon Press.

    Google Scholar 

  • International Commission on Radiological Protection, 1977. ICRP Publication 26, Ann. ICRP 1 (3), 1–47.

    Google Scholar 

  • International Commission on Radiological Protection, 1979. Limits for Intake of Radionuclides by Workers, ICRP Publication 30 Part 1, Ann. ICRP 2 (3/4), 1–116.

    Google Scholar 

  • International Commission on Radiological Protection, 1980. Statement and Recommendations of the 1980 Brighton Meeting of the ICRP - Limits for Intakes of Radionuclides by Workers ICRP Publication 30 Part 2, Ann. ICRP 4(3/4), 1–71.

    Google Scholar 

  • International Commission on Radiological Protection, 1981a. Limits for Intakes of Radionuclides by Workers, ICRP Publication 30 Supplement to Part 2, Ann. ICRP 5 (1–6), 1–751.

    Google Scholar 

  • International Commission on Radiological Protection, 1981b. Limits for Intakes of Radionuclides by Workers, ICRP Publication 30 Part 3 Including Addendum to Parts 1 and 2, Ann. ICRP 6 (2/3), 1–124.

    Google Scholar 

  • Killough, G.G., Dunning, D.E., Jr., and Pleasant, J.C., 1978a. INREM II: A Computer Implementation of Recent Models for Estimating the Dose Equivalent to Organs of Man from an Inhaled or Ingested RadionuclideNUREG/CR-0114, ORNL/NUREG/TM-84, Oak Ridge National Laboratory.

    Google Scholar 

  • Killough, G.G., Dunning, D.E., Jr.. Bernard, S.R., and Pleasant, J.C., 1978b. Estimates of Internal Cose Equivalent to 22 Target Organs for Radionuclides Occurring in Routine Releases from Nuclear Fuel-Cycle Facilities Vol. 1, íUREG/CR-0150. ORNL/NUREG;TM-190, Oak Ridge National Laboratory.

    Google Scholar 

  • Morrow, P.E., Bates, D.V., Fish. B.R., Hatch, T.F., and Mercer, T.T., 1966. “Deposition and Retention Models for Internal Dosimetry of the human Respiratory Tract,” Health Phys. 12 (2), 173.

    CAS  Google Scholar 

  • Ritchie., L.T., Johnson, J.D., and Blond, R.M., 1983. Calculations of Reactor Accident Consequences, Version 2, CRAC2: Computer Code User’s Guide NUREG/CR-2326, SAND81–1994, Sandia National Laboratories.

    Google Scholar 

  • Ritchie, L.T., Alpert, D.J., Burke, R.P., Johnson, J.D., Ostmeyer, R.M., Aldrich, D.C., and Blond, R.M., 1984. CRAC2 Model Description NUREG/CR-2552, SAND82–0342, Sandia National Laboratories.

    Google Scholar 

  • U.S. Nuclear Regulatory Commission, 1975. Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power PlantsWASH-1400, NUREG 75/014.

    Google Scholar 

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© 1987 Plenum Press, New York

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Killough, G.G., Dunning, D.C. (1987). Analysis of Uncertainties in CRAC2 Calculations: The Inhalation Pathway. In: Covello, V.T., Lave, L.B., Moghissi, A., Uppuluri, V.R.R. (eds) Uncertainty in Risk Assessment, Risk Management, and Decision Making. Advances in Risk Analysis, vol 4. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-5317-1_23

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  • DOI: https://doi.org/10.1007/978-1-4684-5317-1_23

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4684-5319-5

  • Online ISBN: 978-1-4684-5317-1

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