Download or read book Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications written by International Atomic Energy Agency and published by . This book was released on 2014-02-19 with total page 311 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 243 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2003 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Pressurized Heavy Water Reactors written by and published by Elsevier. This book was released on 2021-10-02 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Intercomparison and Validation of Computer Codes for Thermohydraulic Safety Analysis of Heavy Water Reactors IAEA TECDOC Series written by International Atomic Energy Agency and published by . This book was released on 2004 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt: Intercomparison and validation of computer codes used in different countries for thermal hydraulics safety analysis of heavy water reactors (HWRs) enhances the confidence in the predictions made by these codes. A set of reliable experimental data is necessary for conducting such intercomparison and validation exercises. Experimental results from a large-loss of coolant accident (LOCA) test simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd. (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participat.
Download or read book Review of the Status of Validation of the Computer Codes Used in the Severe Accident Source Term Reassessment Study BMI 2104 written by and published by . This book was released on 1985 with total page 514 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Severe Accidents in Nuclear Reactors written by Arun K. Nayak and published by Woodhead Publishing. This book was released on 2021-08-02 with total page 392 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Analysis of Severe Accidents in Pressurized Heavy Water Reactors written by Author) and published by . This book was released on 2008 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment written by Jyeshtharaj Joshi and published by Woodhead Publishing. This book was released on 2019-06-15 with total page 888 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Independent Assessment of MELCOR as a Severe Accident Thermal hydraulic written by and published by . This book was released on 1994 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC called ''MELCOR Verification, Benchmarking, and Applications, '' whose aim is to provide independent assessment of MELCOR as a severe accident thermal-hydraulic/source term analysis tool. The scope of this program is to perform quality control verification on all released versions of MELCOR, to benchmark MELCOR against more mechanistic codes and experimental data from severe fuel damage tests, and to evaluate the ability of MELCOR to simulate long-term severe accident transients in commercial LWRs, by applying the code to model both BWRs and PWRs. Under this program, BNL provided input to the NRC-sponsored MELCOR Peer Review, and is currently contributing to the MELCOR Cooperative Assessment Program (MCAP). This paper presents a summary of MELCOR assessment efforts at BNL and their contribution to NRC goals with respect to MELCOR.
Download or read book Melcor Benchmarking Against Integral Severe Fuel Damage Tests written by and published by . This book was released on 1994 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC to provide independent assessment of MELCOR, and a very important part of this program is to benchmark MELCOR against experimental data from integral severe fuel damage tests and predictions of that data from more mechanistic codes such as SCDAP or SCDAP/RELAP5. Benchmarking analyses with MELCOR have been carried out at BNL for five integral severe fuel damage tests, namely, PBF SFD 1-1, SFD 1-4, and NRU FLHT-2, FLHT-4, and FLHT-5. This paper presents a summary of these analyses, and their role in identifying areas of modeling strengths and weaknesses in MELCOR.
Download or read book Heavy Water New Production Reactor Design Review Guidelines written by K. D. Bergeron and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The first step in Sandia's program to support the Heavy Water New Production Reactor program in the area of severe accident prevention and mitigation was to perform a thorough review of all related technical information. This report is the product of that forst step; it is a compendium of key information on core melt accidents written by nineteen specialists in a broad range of scientific and engineering fields. Topics covered include: (a) In-Vessel Melt Progression; (b) Molten Debris-Concrete Interactions; (c) Fuel-Coolant Interactions; (d) Hydrogen Combustion and Distribution; (e) Mitigation Strategies; and (f) Computer Simulation Codes and Accident Analysis. These reviews cover relevant work by specialists at Sandia as well as many other laboratories and institutes throughout the world. For each topic area, annotated bibliographies of key references are also provided.
Download or read book Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2019-07-23 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Industrial Applications of Sealed Radioactive Sources written by International Atomic Energy Agency and published by . This book was released on 2021-01-30 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: In industrial processes, it is useful to have a range of non-intrusive techniques that can effectively 'look' through vessel and pipe walls to measure process parameters and to identify plant problems. Sealed radioactive sources, specifically those that emit gamma radiation and neutron particles, are ideally suited for these purposes and have been used for industrial applications for many years. This publication describes several available techniques with sealed radioactive sources, by showing examples of their use in industrial applications and by demonstrating how they can be used to improve process efficiency and to save money. The focus of the publication corresponds to two major techniques with sealed radioactive sources: gamma scanning and neutron backscattering, which are largely applied for diagnosis and troubleshooting in processing vessels, columns and in pipes.
Download or read book Nuclear Safety in Light Water Reactors written by Bal Raj Sehgal and published by Academic Press. This book was released on 2012-01-05 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2010 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Accident Analysis for Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2002 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accident analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). The purpose of the report is to provide the necessary practical guidance for performing adequate accident analysis in the light of current good practice worldwide.
