Benchmarking Severe Accident Computer Codes For Heavy Water Reactor Applications eBook Download PDF

Download Benchmarking Severe Accident Computer Codes For Heavy Water Reactor Applications full books in PDF, epub, and Kindle. Read online Benchmarking Severe Accident Computer Codes For Heavy Water Reactor Applications ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Author: International Atomic Energy Agency

Publisher:

Published: 2014-02-19

Total Pages: 311

ISBN-13: 9789201144133

DOWNLOAD EBOOK

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.

Book Synopsis Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications by : International Atomic Energy Agency

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.

Pressurized Heavy Water Reactors

Author:

Publisher: Elsevier

Published: 2021-10-02

Total Pages: 546

ISBN-13: 0128232595

DOWNLOAD EBOOK

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

Book Synopsis Pressurized Heavy Water Reactors by :

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

Intercomparison and Validation of Computer Codes for Thermohydraulic Safety Analysis of Heavy Water Reactors. IAEA TECDOC Series

Author: International Atomic Energy Agency

Publisher:

Published: 2004

Total Pages: 130

ISBN-13:

DOWNLOAD EBOOK

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.

Book Synopsis Intercomparison and Validation of Computer Codes for Thermohydraulic Safety Analysis of Heavy Water Reactors. IAEA TECDOC Series by : International Atomic Energy Agency

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.

Severe Accidents in Nuclear Reactors

Author: Arun K. Nayak

Publisher: Woodhead Publishing

Published: 2021-08-02

Total Pages: 392

ISBN-13: 0128223057

DOWNLOAD EBOOK

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

Book Synopsis Severe Accidents in Nuclear Reactors by : Arun K. Nayak

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

Review of the Status of Validation of the Computer Codes Used in the Severe Accident Source Term Reassessment Study (BMI-2104)

Author:

Publisher:

Published: 1985

Total Pages: 514

ISBN-13:

DOWNLOAD EBOOK

Book Synopsis Review of the Status of Validation of the Computer Codes Used in the Severe Accident Source Term Reassessment Study (BMI-2104) by :

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:

Analysis of Severe Accidents in Pressurized Heavy Water Reactors

Author: Author)

Publisher:

Published: 2008

Total Pages: 146

ISBN-13:

DOWNLOAD EBOOK

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.

Book Synopsis Analysis of Severe Accidents in Pressurized Heavy Water Reactors by : Author)

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.

Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 243

ISBN-13: 9789201337108

DOWNLOAD EBOOK

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

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

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

Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2003

Total Pages: 64

ISBN-13:

DOWNLOAD EBOOK

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.

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

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.

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Author: Jyeshtharaj Joshi

Publisher: Woodhead Publishing

Published: 2019-06-15

Total Pages: 888

ISBN-13: 0081023375

DOWNLOAD EBOOK

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

Book Synopsis Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by : Jyeshtharaj Joshi

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

Independent Assessment of MELCOR as a Severe Accident Thermal-hydraulic

Author:

Publisher:

Published: 1994

Total Pages: 11

ISBN-13:

DOWNLOAD EBOOK

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.

Book Synopsis Independent Assessment of MELCOR as a Severe Accident Thermal-hydraulic by :

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.