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Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide
The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significantExpand
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CRAC2 model description
The CRAC2 computer code is a revised version of CRAC (Calculation of Reactor Accident Consequences) which was developed for the Reactor Safety Study. This document provides an overview of the CRAC2Expand
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Regulatory impact of nuclear reactor accident source term assumptions. Technical report
This report addresses the reactor accident source term implications on accident evaluations, regulations and regulatory requirements, engineered safety features, emergency planning, probabilisticExpand
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Findings of the Peer Review Panel on the Draft Reactor Risk Reference Document, NUREG-1150
This report contains the finding of the /open quotes/NUREG-1150 Peer Review Panel/close quotes/ on the methodology and results presented in the Draft Reactor Risk Reference Study (NUREG-1150) andExpand
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Model of public evacuation for atmosphric radiological releases
A model of public evacuation is developed for use in evaluating the efficacy of evacuation as a protective measure in response to atmospheric releases of radioactive material. Differences betweenExpand
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Variability of Site‐Reactor Risk
Reactor accident consequence models have been developed (for example, the CRAC model of the Reactor Safety Study (RSS), WASH†1400) to predict the offsite health and economic consequences of severeExpand
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Assessment of consequences from airborne releases of radioactive material
Over the past several years, the manner in which assessments have been made of the consequences of large airborne releases of radioactive material has not changed much conceptually. The models toExpand
International standard problem for consequence modeling
To better understand differences in consequence modeling techniques, a comparison study was organized under the auspices of the Committee on the Safety of Nuclear Installations. About 30Expand
Overview of the reactor safety study consequence model
The Reactor Safety Study (WASH-1400) is a comprehensive assessment of the potential risk to the public from accidents in light water power reactors. The engineering analysis of the plants isExpand
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Recent developments in consequence modeling
A number of recent developments have occurred in the area of nuclear reactor accident consequence analysis, including improvements in modeling capabilities, model evaluation studies, and applicationExpand
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