Benchmarking Severe Accident Computer Codes For Heavy Water Reactor Applications

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 311 pages
File Size : 43,6 Mb
Release : 2014-02-19
Category : Science
ISBN : 920114413X

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Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications by International Atomic Energy Agency Pdf

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 : International Atomic Energy Agency
Publisher : Unknown
Page : 139 pages
File Size : 41,7 Mb
Release : 2008
Category : Heavy water reactors
ISBN : 9201059086

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Analysis of Severe Accidents in Pressurized Heavy-water Reactors by International Atomic Energy Agency Pdf

This report instructs the reader on how to perform deterministic analysis of severe accidents in pressurized heavy water reactors (PHWRs) by means of available computer codes. The analysis of accident phenomena should assist in the development of practicable preventive or mitigatory measures. In addition to providing a framework for data collection and analysis relevant to both the in- and ex-vessel phases of severe accidents, the publication also provides guidance for severe accident management.

Author : Arun K. Nayak,Parimal Pramod Kulkarni
Publisher : Woodhead Publishing
Page : 392 pages
File Size : 43,8 Mb
Release : 2021-08-02
Category : Technology & Engineering
ISBN : 9780128223055

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Severe Accidents in Nuclear Reactors by Arun K. Nayak,Parimal Pramod Kulkarni Pdf

Severe Accidents in Nuclear Reactors: Corium Retention Technologies and Insights presents an authoritative and practical analysis of the latest severe accident management strategies based on previous events and experiments. Written for utilities and industries operating and researching nuclear cooled reactor power plants, this book presents the exponential growth in research since major nuclear accidents and acts as a guide to retaining molten corium, both inside and outside the reactor vessel. Sections cover the physics behind several complex phenomena occurring during corium coolability, providing the reader with an in-depth understanding by presenting the insights obtained from simulated severe accidents. In addition, the book validates several severe accident codes and provides evidence on the termination of severe accident progressions to help the reader evaluate the safety of existing reactors and design the next generation of nuclear reactors. Provides a step-by-step guide to various severe accident management experiments Includes evidence on the termination of severe accident progressions Validates several severe accident codes

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 83 pages
File Size : 46,8 Mb
Release : 2019
Category : Computer simulation
ISBN : 9201630190

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Heavy Water Reactor Moderator Effectiveness as a Backup Heat Sink During Accidents by International Atomic Energy Agency Pdf

Author : Jyeshtharaj Joshi,Arun K Nayak
Publisher : Woodhead Publishing
Page : 888 pages
File Size : 55,8 Mb
Release : 2019-06-15
Category : Science
ISBN : 9780081023372

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by Jyeshtharaj Joshi,Arun K Nayak Pdf

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 34 pages
File Size : 52,7 Mb
Release : 2007
Category : Business & Economics
ISBN : UOM:39015068765661

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Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants by International Atomic Energy Agency Pdf

This publication summarizes the results of the Technical Meeting on "Progress in development and use of coupled codes for accident analysis". The significantly increased capacity of new computation technology has made it possible to proceed the code coupling not only between neutronics and thermal hydraulics but also between thermal hydraulics and one or more other disciplines. This publication contains a review of state-of-the-art technologies in code coupling and its application to the accident analysis of nuclear power plants. The presentations and the papers given at the Technical Meeting are enclosed on the attached CD.--Publisher's description.

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 243 pages
File Size : 42,8 Mb
Release : 2012
Category : Science
ISBN : 9201337108

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Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data by International Atomic Energy Agency Pdf

Intercomparison and Validation of Computer Codes for Thermalhydraulics Safety Analyses is an International Atomic Energy Agency (IAEA) activity designed to facilitate international cooperative research and promote information exchange on computer codes for thermalhydraulic safety analyses. The objective is to enhance the safety analysis capabilities of the participants and the effective use of their resources through this international cooperation. This report provides a comparison of the results obtained from eight participating organisations from six countries, utilizing four different computer codes. General conclusions are reached and recommendations made

Author : Anonim
Publisher : Elsevier
Page : 546 pages
File Size : 41,9 Mb
Release : 2021-10-02
Category : Science
ISBN : 9780128232590

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Pressurized Heavy Water Reactors by Anonim Pdf

Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs. Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties. Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation

Author : International Atomic Energy Agency
Publisher : IAEA
Page : 64 pages
File Size : 40,8 Mb
Release : 2003
Category : Business & Economics
ISBN : UOM:39015052977124

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Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors by International Atomic Energy Agency Pdf

This report contains practical guidance for performing accident analysis for nuclear power plants with pressurised heavy water reactors, based on current international good practice. It covers key aspects required including selection of initiating events and acceptance criteria, computer codes and modelling assumptions, the preparation of input data, presentation of results and quality assurance.

Author : International Atomic Energy Agency
Publisher : International Atomic Energy Agency
Page : 96 pages
File Size : 41,8 Mb
Release : 2019-07-23
Category : Technology & Engineering
ISBN : 9201029195

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Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors by International Atomic Energy Agency Pdf

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 : Anonim
Publisher : Unknown
Page : 0 pages
File Size : 53,7 Mb
Release : 2022
Category : CANDU reactors
ISBN : 9201084226

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Numerical Benchmarks for Multiphysics Simulation of Pressurized Heavy Water Reactor Transients by Anonim Pdf

"The IAEA organizes International Collaborative Standard Problems (ICSPs) to facilitate co-operation on advancing reactor technology related activities. These activities include the development, assessment and validation of computer codes for design and safety analysis of nuclear power plants. The objective of this ICSP was to develop and facilitate open access to a set of standardized numerical test problems for selected postulated transients in pressurized heavy water reactors (PHWRs). These manufactured test problems are different from typical benchmark problems in that the specification is designed for a stylized model of a generic CANDU-6 PHWR and a reference solution is not postulated. The set of standardized numerical test problems supports the development of simulation codes, methods, and coupling frameworks. This publication provides a description of four numerical test problems, the participants' individual multi-physics methodologies applied, and simulations carried out, an independent synthesis of the results, and the lessons learned from the exercise."--Publisher's description.

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 0 pages
File Size : 46,8 Mb
Release : 2020-03-09
Category : Technology & Engineering
ISBN : 9201629192

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Heavy Water Reactor Moderator Effectiveness as a Backup Heat Sink During Accidents by International Atomic Energy Agency Pdf

The IAEA organizes international collaborative standard problems (ICSP) to facilitate the development and validation of computer codes for design and safety analysis of nuclear power plants, which usually includes an experimental investigation of important phenomena and simulation of the experiment with computer codes. This ICSP investigated phenomena that determine the thermo-mechanical behaviour of heavy water reactor fuel channels during a fuel overheating scenario. The publication summarizes the experiment, the complex and transient nature of phenomena interactions that ultimately determine fuel channel behaviour, the simulation methods and results, and the lessons learned from the ICSP. It provides a comparison of the results obtained from eight participating organizations from five countries, utilizing different methods and computer codes. General conclusions drawn and recommendations made for future developments are also included.

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 0 pages
File Size : 46,7 Mb
Release : 2010
Category : Technology & Engineering
ISBN : 9201022107

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Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants by International Atomic Energy Agency Pdf

The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; References; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

Author : Anonim
Publisher : Unknown
Page : 906 pages
File Size : 49,5 Mb
Release : 1993
Category : Power resources
ISBN : MINN:30000006337335

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Energy Research Abstracts by Anonim Pdf

Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Author : Bal Raj Sehgal
Publisher : Academic Press
Page : 732 pages
File Size : 52,8 Mb
Release : 2012-01-05
Category : Technology & Engineering
ISBN : 9780123884466

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Nuclear Safety in Light Water Reactors by Bal Raj Sehgal Pdf

La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.