Probabilistic accident consequence uncertainty analysis

Uncertainty assessment for deposited material and external doses (EUR)
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Open LibraryOL12909651M
ISBN 109282767000
ISBN 139789282767009

Probabilistic accident consequence uncertainty analysis: External exposure from deposited material uncertainty assessment, Report NUREG/CR-EURWashington,DC/USA, and Brussels-Luxembourg, NUREG/CR EUR CG-NAEN-C ISBN SAND Vol. 1 Probabilistic Accident Consequence Uncertainty Analysis Late Health Effects Uncertainty.

Get this from a library. Probabilistic accident consequence uncertainty analysis: uncertainty assessment for internal dosimetry.

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[L H J Goossens; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; Sandia National Laboratories.;].

We use cookies to make interactions with our website easy and meaningful, to better understand the use of our services, and to tailor advertising. Get this from a library. Probabilistic accident consequence uncertainty analysis: dispersion and deposition uncertainty assessment.

[U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; Commission.

Probabilistic Accident Consequence Uncertainty Analysis Dispersion and Deposition Uncertainty Assessment Main Report Manuscript Completed: November Date Published: January Prepared by F. Harper Sandia National Laboratories, USA S.

Hora University of Hawau at Hilo, USA M. Young Sandia National Laboratories, USA. Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty asses.

COSYMA is a system of programs and data bases, rather than a single program. The mainframe version contains three main accident consequence assessment programs together with a number of preprocessing and evaluation programs.

The three main sub-systems of COSYMA are known as the NE, NL, and FL sub-systems (Figure A-4). probabilistic accident consequence codes: MACCS(1) in the United States and COSYMA(2) in Europe.

Uncertainty analyses have been performed with predecessors of both codes, whereby the probability distributions utilised were assigned primarily by the consequence.

Aug 01,  · The development of two probabilistic accident consequence codes sponsored by the European Commission and the United States Nuclear Regulatory Commiss We use cookies to enhance your experience on our dsc-sports.com continuing to Cited by: Jow H-N, Sprung J L, Chanin D I, Helton J C and Rollstin J A Reactor Accident Consequence Analysis Code (MACCS) SANDC (Albuquerque, NM: Sandia National Laboratories) Little M P, Muirhead C R, Goossens L H J, Kraan B C P, Cooke R M, Harper F T and Hora S C Probabilistic Accident Consequence Uncertainty Analysis.

Late Health Author: M P Little. probabilistic accident consequence assessment system COSYMA 3 Probabilistic accident consequence uncertainty analysis book provide an input to identifying future R&D priorities.

This report describes the analysis of the uncertainty in the model predictions resulting from uncertainty in the values to be assigned to the input parameters describing internal and external dosimetry and consumption rates.

Aug 01,  · Uncertainty analysis of the dose calculation module of the COSYMA accident consequence assessment code has been undertaken, involving the following s We use cookies to enhance your experience on our dsc-sports.com continuing to Author: J.D.

Harrison, J. Boardman, J.A. Jones, A. Khursheed, B.C.P. Kraan, A.W. Phipps (Invited). Aug 01,  · A set of model parameters was identified which contribute most to the uncertainties of endpoints.

Probabilistic accident consequence assessments with weather sequences were performed for each of sample sets derived from the uncertainty distributions of these parameters by Latin hypercube dsc-sports.com by: 3.

A study to perform an uncertainty analysis of the European accident consequence assessment system, COSYMA, has been carried out under contract to the European Commission. The study involved a series of analyses of the uncertainty in different sections of the system, followed by a final analysis of the uncertainty in the whole system.

@article{osti_, title = {Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, appendices A and B}, author = {Harper, F.T.

and Young, M.L. and Miller, L.A. and Hora, S.C. and Lui, C.H. and Goossens, L.H.J. and Cooke, R.M. and Paesler-Sauer, J. and Helton, J.C.}, abstractNote = {The development of two new probabilistic accident. The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in These codes estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents.

Aug 01,  · The aggregated uncertainty distributions from the experts for the elicited variables were used in an uncertainty analysis of the food chain module of COSYMA.

The main aim of the module analysis was to identify those parameters whose uncertainty makes large contributions to the overall uncertainty and so should be included in the overall dsc-sports.com by: 2.

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The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. Uncertainty analyses of probabilistic accident consequence codes provide large insight in the range of output of the models analysed.

Particularly, when such codes are used to meet the requirements of safety and environmental laws, the robustness of the uncertainty analysis is of vital importance. Get this from a library. Probabilistic accident consequence uncertainty analysis: uncertainty assessment for deposited material and external doses.

[L H J Goossens; Sandia National Laboratories.; Commission of the European Communities.; U.S. Nuclear Regulatory Commission.

Description Probabilistic accident consequence uncertainty analysis FB2

Office of Nuclear Regulatory Research. Division of Systems Technology.;]. Probabilistic Safety Analysis (PSA) determines the probability and consequences of accidents, hence, the risk.

This subject concerns policy makers, regulators, designers, educators and engineers working to achieve maximum safety with operational efficiency. Risk is analyzed using methods for achieving reliability in the space program. In PSA, MCM can be used for uncertainty assessment of failure rate data, propagation of uncertainty in FTAs, and consequence estimates of accident sequences in ETAs.

For instance, MCM can be used to find incidents that lead to a major accident, selecting the probabilistic parameters that affect the accident dsc-sports.com by: 1.

Aug 01,  · Read "Probabilistic Accident Consequence Uncertainty Analysis of the Food Chain Module in the COSYMA Package, Radiation Protection Dosimetry" on DeepDyve, the largest online rental service for scholarly research with thousands of academic publications available at your fingertips.

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations.

Inthe US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis Cited by: 1. Get this from a library. Probabilistic accident consequence uncertainty analysis: late health effects uncertainty assessment.

[M P Little; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; Commission of the European Communities.;].

Aug 01,  · Probabilistic Accident Consequence Uncertainty Analysis of the Early Health Effects Module in the COSYMA Package Probabilistic Accident Consequence Uncertainty Analysis of the Early Health Effects Module in the.

This paper describes the results of an ongoing EC/USNRC joint project on the uncertainty analysis of probabilistic accident consequence codes for nuclear applications. The uncertainty distributions are obtained using a formal expert elicitation procedure based on methods from Delft University of Technology and NUREG experience in the dsc-sports.com: L.

Goossens, F. Harper, G. Kelly, C. Lui. dsc-sports.com Conference: Summary of uncertainty analysis of dispersion and deposition modules of the MACCS and COSYMA consequence codes: A joint USNRC/CEC study. Summary of uncertainty analysis of dispersion and deposition modules of the MACCS and COSYMA consequence codes: A joint USNRC/CEC study.

Abstract. MACCS2 [1] is a probabilistic accident consequence code that estimates the risks from the operation of nuclear installations, based on the postulated Cited by: 1. This site uses cookies. By continuing to use this site you agree to our use of cookies. To find out more, see our Privacy and Cookies dsc-sports.com by: Probabilistic risk assessment (PRA), sometimes called probabilistic safety analysis, quantifies the risk of undesired events in industrial facilities.

However, one of the weaknesses that undermines the credibility and usefulness of this technique is the uncertainty in PRA results. Fault tree analysis (FTA) and event tree analysis (ETA) are the most important PRA techniques for evaluating Cited by: 1.Jan 07,  · Uncertainty in compartmental models for hazardous materials — a case study.

Author links open overlay panel B.C.P. Kraan R.M. Cooke. Show moreCited by: