Author: International Atomic Energy Agency Publisher: International Atomic Energy Agency ISBN: 9789201029195 Category : Technology & Engineering Languages : en Pages : 96
Book Description
Accurate prediction of source term and modelling of severe accident progression by severe accident analysis codes is integral to the safe operation of water cooled reactors in both developing and developed Member States. The source term released to the environment during severe accidents, calculated by these codes, is utilized by specialized atmospheric transport codes to evaluate the transport of radionuclides in the environment. Though severe accident codes are comprehensively validated based on experiments, there remains 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 with 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 recommends areas for research and development. The information is detailed in terms of major findings, identified gaps, and recommended future actions.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201144133 Category : Science Languages : en Pages : 311
Book Description
This publication reports on the results of an IAEA cooperated research project (CRP) on benchmarking severe accident computer codes for heavy water reactor applications. The CRP scope included the identification and selection of a severe accident sequence, selection of appropriate geometrical and boundary conditions, conduct of benchmark analyses, comparison of the results of all code outputs, evaluation of the capabilities of computer codes to predict important severe accident phenomena, and the proposal of necessary code improvements and/or new experiments to reduce uncertainties. The summary report provides a comparison of key results obtained from five participating countries and concludes with lessons learned and recommendations for the future.
Author: IAEA Publisher: ISBN: 9789201220240 Category : Languages : en Pages : 0
Book Description
The IAEA facilitated collaborative research among its Member States, in advancing the state of the practice in uncertainty and sensitivity methodologies for severe accident analysis in water cooled reactors. The primary aim was to evaluate the uncertainty and sensitivity associated with severe accident calculations, particularly concerning the progression and consequences of accidents in a generic CANDU type nuclear power plant under a postulated station blackout scenario. Key parameters considered in these analyses included hydrogen generation, event timings, and the release of fission products into the environment. The resulting publication showcases contributions from three institutions across three Member States, providing insights into their methodologies for uncertainty and sensitivity analysis in severe accidents.
Author: Publisher: ISBN: Category : Languages : en Pages : 54
Book Description
This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the experienced user-base and the experimental validation base was decaying away quickly.
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency
Author: Timothy J. Tautges
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Author: J. B. Rivard
Author: M. H. Fontana
Author: IAEA
Author: IAEA.
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