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Title: Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices

Abstract

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA internal dosimetry models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on internal dosimetry, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Authors:
; ;  [1];  [2];  [3];  [4]
  1. Delft Univ. of Technology (Netherlands)
  2. National Radiological Protection Board (United Kingdom)
  3. Sandia National Labs., Albuquerque, NM (United States)
  4. Univ. of Hawaii, Hilo, HI (United States)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Div. of Systems Technology, Washington, DC (United States); Commission of the European Communities, Brussels (Belgium); Delft Univ. of Technology (Netherlands); National Radiological Protection Board (United Kingdom); Sandia National Labs., Albuquerque, NM (United States); Univ. of Hawaii, Hilo, HI (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
291005
Report Number(s):
NUREG/CR-6571-Vol.2-App.; EUR-16773-Vol.2-App.; SAND-98-0119-Vol.2-App.
ON: TI99001183; IN: CG-NA-16-774-EN-C; TRN: AHC29901%%210
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Apr 1998
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 56 BIOLOGY AND MEDICINE, APPLIED STUDIES; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; M CODES; C CODES; DOSIMETRY; RADIATION DOSES; PROBABILITY; REACTOR ACCIDENTS; NUCLEAR POWER PLANTS; NUMERICAL DATA; DATA COVARIANCES; INTERNATIONAL COOPERATION

Citation Formats

Goossens, L H.J., Kraan, B C.P., Cooke, R M, Harrison, J D, Harper, F T, and Hora, S C. Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices. United States: N. p., 1998. Web. doi:10.2172/291005.
Goossens, L H.J., Kraan, B C.P., Cooke, R M, Harrison, J D, Harper, F T, & Hora, S C. Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices. United States. https://doi.org/10.2172/291005
Goossens, L H.J., Kraan, B C.P., Cooke, R M, Harrison, J D, Harper, F T, and Hora, S C. Wed . "Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices". United States. https://doi.org/10.2172/291005. https://www.osti.gov/servlets/purl/291005.
@article{osti_291005,
title = {Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices},
author = {Goossens, L H.J. and Kraan, B C.P. and Cooke, R M and Harrison, J D and Harper, F T and Hora, S C},
abstractNote = {The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA internal dosimetry models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on internal dosimetry, (4) short biographies of the experts, and (5) the aggregated results of their responses.},
doi = {10.2172/291005},
url = {https://www.osti.gov/biblio/291005}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1998},
month = {4}
}