Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
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.

Severe Accidents in Nuclear Reactors
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

Pressurized Heavy Water Reactors
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

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

Author: Jyeshtharaj Joshi

Publisher: Woodhead Publishing

Published: 2019-06-11

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.

Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants
Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher:

Published: 2010

Total Pages: 0

ISBN-13: 9789201022103

DOWNLOAD EBOOK

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.

Nuclear Safety in Light Water Reactors
Nuclear Safety in Light Water Reactors

Author: Bal Raj Sehgal

Publisher: Academic Press

Published: 2012-01-05

Total Pages: 732

ISBN-13: 0123884462

DOWNLOAD EBOOK

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.

Status of Research and Technology Development for Supercritical Water Cooled Reactors
Status of Research and Technology Development for Supercritical Water Cooled Reactors

Author: International Atomic Energy Agency

Publisher: International Atomic Energy Agency

Published: 2019-05-22

Total Pages: 74

ISBN-13: 9789201019196

DOWNLOAD EBOOK

There is considerable interest in both developing and developed countries in the design of innovative water cooled reactors (WCRs) and, owing to the higher thermal efficiency and significant system simplifications, supercritical water cooled reactors (SWCRs). Compared to conventional WCRs the SCWR concept requires extensive, comprehensive research and development (R&D). Fundamental research in understanding important phenomena has been completed successfully in providing information required for the next step of development. Currently, a few concepts have been assessed as being technical feasible, and several other concepts are under development. These concepts are described in this publication, together with detailed analysis of remaining gaps requiring future R&D.

Accident Analysis for Nuclear Power Plants
Accident Analysis for Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher:

Published: 2002

Total Pages: 144

ISBN-13:

DOWNLOAD EBOOK

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.

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

Author: International Atomic Energy Agency

Publisher:

Published: 2020-07-30

Total Pages: 218

ISBN-13: 9789201080202

DOWNLOAD EBOOK

This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.