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Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors

IAEA TECDOC No. 1872
English IAEA-TECDOC-1872 978-92-0-102919-5
96 3 18.00 2019

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Description

Accurate prediction of source term and modelling of severe accident progression by severe accident analysis codes are integral to the safe operation of water cooled reactors. The source term released to the environment during severe accidents, calculated by these codes, is used in specialized atmospheric transport models to evaluate the transport of radionuclides in the environment. Although severe accident codes are comprehensively validated based on experiments, there is disagreement among calculations performed using different codes for the same scenarios. Such differences and their causes are being explored by a number of organizations, including cooperation by developers through code to code benchmarks. Furthermore, severe accident phenomena model improvements are being made on the basis of insights from experiments and with the development of models to account for previously less understood phenomena. This publication summarizes the current status of severe accident analysis codes and identifies possible areas for research and development. The information is detailed in terms of major findings, identified gaps and recommended future actions.

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Keywords

Nuclear Reactor Accidents, Computer Simulation, Water Cooled Reactors, Accident Codes, Models, Member States, Transport Codes, Radionuclides, Severe Accidents Simulation Codes, Evaluation, Fukushima Daiichi Accident, Accident Analyses, Organizations, Computer Codes, Recommendations, Source Term, Atmospheric Transport, Coolant Accidents, Probabilistic Risk Assessment, Forensics Application

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