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Thursday, November 12, 2020 | History

4 edition of Probabilistic accident consequence uncertainty analysis found in the catalog.

Probabilistic accident consequence uncertainty analysis

Probabilistic accident consequence uncertainty analysis

uncertainty assessment for internal dosimetry

by

  • 332 Want to read
  • 19 Currently reading

Published by Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Commission of the European Communities, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC, Brussels, Belgium .
Written in English

    Subjects:
  • Nuclear power plants -- Risk assessment,
  • Nuclear power plants -- Accidents,
  • Radioactive pollution of the atmosphere

  • Edition Notes

    Other titlesUncertainty assessment for internal dosimetry.
    Statementprepared by L.H.J. Goossens ... [et al.].
    SeriesEUR -- 16773., EUR (Series) -- 16773.
    ContributionsGoossens, L. H. J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., Sandia National Laboratories.
    The Physical Object
    FormatMicroform
    Pagination2 v.
    ID Numbers
    Open LibraryOL17838742M
    OCLC/WorldCa41399333


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Probabilistic accident consequence uncertainty analysis Download PDF EPUB FB2

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. [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 leboostcamp.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 Probabilistic accident consequence uncertainty analysis book 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 to 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 leboostcamp.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 leboostcamp.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 leboostcamp.com by: 2.

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. 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 leboostcamp.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 leboostcamp.com: L.

Goossens, F. Harper, G. Kelly, C. Lui. leboostcamp.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 leboostcamp.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: May 27,  · Climate change uncertainty quantification: Lessons learned from the joint EU-USNRC project on uncertainty analysis of probabilistic accident consequence codes. Washington, DC: Resources for the Future. Google ScholarCited by: 3. Summary not available for this title. Record Details Catalog Search.

Jan 10,  · While requiring some fundamental background in risk assessment, as well as a basic knowledge of probability theory and statistics, Uncertainty in Risk Assessment can be read profitably by a broad audience of professionals in the field, including researchers and graduate students on courses within risk analysis, statistics, engineering, and the.

D.A. Meneley, in Infrastructure and Methodologies for the Justification of Nuclear Power Programmes, PSA methods, structures, and limitations. The INSAG report Probabilistic Safety Assessment (INSAG-6, ) presents a sound description of the probabilistic leboostcamp.com is a systematic risk-based analytical method that combines fault trees and event sequence diagrams of.

Probabilistic Risk Assessment: Applications for the Oil & Gas Industry. of numeric values in the assessment of probability and consequence, and commonly follows many quantitative approaches may not support detailed analysis of uncertainty, common cause failures, and human reliability, in contrast to Probabilistic Risk Assessment (PRA).

I PROBABILISTIC RISK ASSESSMENT. PRA is a process of probabilistic evidential and inferential analysis of the response of events, systems, or activities to different challenges based on the fundamental rules of logic and plausible reasoning.

The risk measure is most often a frequency whose uncertainty is represented by a probability Author: Division on Earth. Probabilistic Risk Assessment (PRA) plays an important role in the nuclear reactor regulatory process, and the assessment of uncertainties associated with PRA results is widely recognized as an important part of the analysis process.

However, uncertainty analysis and sensitivity analysis in the context of PRA are relatively immature leboostcamp.com: Ronald L. Iman. atic for at least three reasons. First, the determination of what constitutes an influential risk assessment may be unclear at the outset.

Although some agencies may be able to identify an influential risk assessment at the onset of the analysis, 1 others may not be able to. 2 The impact of an agency activity that led to the development of the risk assessment may not be known a priori.Probabilistic risk assessment (PRA) is a systematic and comprehensive methodology to evaluate risks associated with a complex engineered technological entity (such as an airliner or a nuclear power plant) or the effects of stressors on the environment (Probabilistic Environmental Risk Assessment - .Books Peer Reviewed Contract Research Reports - Joint CEC/USNRC Uncertainty Analysis of Accident Consequence Codes.

Probabilistic Accident Consequence Uncertainty Study: Uncertainty Assessment For Deposited Material And External Doses. NUREG/CR Washington/USA,