Design Basis Accident Analysis Methods For Light Water Nuclear Power Plants

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Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants

Author : Robert Martin,Cesare Frepoli
Publisher : World Scientific
Page : 717 pages
File Size : 54,9 Mb
Release : 2019-02-13
Category : Technology & Engineering
ISBN : 9789813275676

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Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants by Robert Martin,Cesare Frepoli Pdf

This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Accident Analysis for Nuclear Power Plants with Graphite Moderated Boiling Water RBMK Reactors

Author : International Atomic Energy Agency
Publisher : IAEA
Page : 74 pages
File Size : 40,6 Mb
Release : 2005
Category : Business & Economics
ISBN : UOM:39015062434439

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Accident Analysis for Nuclear Power Plants with Graphite Moderated Boiling Water RBMK Reactors by International Atomic Energy Agency Pdf

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. This publication contains guidance on the specific design features of graphite moderated boiling water reactors (RBMKs), including advice regarding categorisation of initiating events, selection of acceptance criteria, and initial and boundary conditions.

Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 106 pages
File Size : 44,9 Mb
Release : 1998
Category : Business & Economics
ISBN : UOM:39015042759202

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Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards by International Atomic Energy Agency Pdf

This Safety Report complements Safety Guide No. 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994). It provides practical information for the safety assessment and judgement process for operating nuclear power plants built to earlier standards, on the basis of a comparison with current safety standards and operational practices.

Radionuclide Source Terms from Severe Accidents to Nuclear Power Plants with Light Water Reactors

Author : International Nuclear Safety Advisory Group
Publisher : Bernan Press(PA)
Page : 32 pages
File Size : 51,5 Mb
Release : 1987
Category : Business & Economics
ISBN : UOM:39015011997056

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Radionuclide Source Terms from Severe Accidents to Nuclear Power Plants with Light Water Reactors by International Nuclear Safety Advisory Group Pdf

This report presents the views of the IAEA's International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety.

Design of the Reactor Core for Nuclear Power Plants

Author : IAEA
Publisher : International Atomic Energy Agency
Page : 87 pages
File Size : 42,8 Mb
Release : 2019-12-31
Category : Technology & Engineering
ISBN : 9789201076229

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Design of the Reactor Core for Nuclear Power Plants by IAEA Pdf

The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.

Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors

Author : International Atomic Energy Agency
Publisher : IAEA
Page : 64 pages
File Size : 51,9 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.

Approaches and Tools for Severe Accident Analysis for Nuclear Power Plants

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 205 pages
File Size : 47,7 Mb
Release : 2008
Category : Nature
ISBN : 9201016085

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Approaches and Tools for Severe Accident Analysis for Nuclear Power Plants by International Atomic Energy Agency Pdf

This publication is a companion to the IAEA Safety Report on Accident Analysis for Nuclear Power Plants. It is specifically devoted to the analysis of severe accidents. Although the publication does not explicitly differentiate between various reactor types, it has been written on the basis of the available knowledge and databases developed for light water reactors (LWRs). Its application is therefore oriented mainly towards pressurized water reactors (PWRs) and boiling water reactors (BWRs) and, to a more limited extent, water cooled water moderated power reactors (WWERs) and pressurized heavy water reactors (PHWRs).

Accident Analysis for Nuclear Power Plants

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 144 pages
File Size : 41,9 Mb
Release : 2002
Category : Business & Economics
ISBN : UOM:39015052302166

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Accident Analysis for Nuclear Power Plants by International Atomic Energy Agency Pdf

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.

Design Extension Conditions and the Concept of Practical Elimination in the Design of Nuclear Power Plants

Author : IAEA
Publisher : International Atomic Energy Agency
Page : 81 pages
File Size : 44,7 Mb
Release : 2024-02-06
Category : Technology & Engineering
ISBN : 9789201305237

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Design Extension Conditions and the Concept of Practical Elimination in the Design of Nuclear Power Plants by IAEA Pdf

The objective of this Safety Guide is to provide recommendations for the design of new nuclear power plants related to defense in depth and the practical elimination of plant event sequences that could lead to an early radioactive release or a large radioactive release. It also provides recommendations in relation to design aspects of defense in depth, in particular on those aspects associated with design extension conditions. Since the introduction of the term "practical elimination" in the early 90's and the recognition that accident conditions could include design extension conditions without significant fuel degradation and design extension conditions with core melting, those topics have been the subject of extensive discussions and several publications. The purpose of this publication is to facilitate international consensus on the understanding of those topics among regulators and designers and to provide recommendations for their consistent implementation in relevant nuclear power plant designs. In particular, this Specific Safety Guide gives recommendations related to the demonstration of the implementation of the practical elimination concept for those plant event sequences that could lead to an early radioactive release or a large radioactive release, which relies on the physical impossibility or on the high-level confidence that they are extremely unlikely to arise.

Design of the Reactor Containment and Associated Systems for Nuclear Power Plants

Author : IAEA
Publisher : International Atomic Energy Agency
Page : 86 pages
File Size : 48,7 Mb
Release : 2019-12-09
Category : Technology & Engineering
ISBN : 9789201072221

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Design of the Reactor Containment and Associated Systems for Nuclear Power Plants by IAEA Pdf

This Safety Guide provides recommendations on meeting the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) relevant to reactor containment and associated systems. The publication addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications, such as for district heating or desalination.

Risk and Safety Analysis of Nuclear Systems

Author : John C. Lee,Norman J. McCormick
Publisher : John Wiley & Sons
Page : 504 pages
File Size : 42,7 Mb
Release : 2012-01-12
Category : Technology & Engineering
ISBN : 9781118043455

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Risk and Safety Analysis of Nuclear Systems by John C. Lee,Norman J. McCormick Pdf

The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems. The second half of the book covers the safety analysis of nuclear energy systems, an analysis of major accidents and incidents that occurred in commercial nuclear plants, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical PRA examples, and emerging techniques in the structure of dynamic event trees and fault trees that can provide a more realistic representation of complex sequences of events. The book concludes with a discussion on passive safety features of advanced nuclear energy systems under development and approaches taken for risk-informed regulations for nuclear plants.

Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants

Author : IAEA
Publisher : International Atomic Energy Agency
Page : 117 pages
File Size : 50,7 Mb
Release : 2020-03-03
Category : Technology & Engineering
ISBN : 9789201064226

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Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants by IAEA Pdf

This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9, which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed respectively for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors.

Safety of Nuclear Power Plants: Design

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 82 pages
File Size : 53,9 Mb
Release : 2000
Category : Business & Economics
ISBN : UOM:39015053504166

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Safety of Nuclear Power Plants: Design by International Atomic Energy Agency Pdf

Establishes design requirements for safety functions and associated structures, systems and components important to the safe operation of nuclear power plants. This publication also establishes requirements for a comprehensive safety assessment to identify the potential hazards that may arise in the operation of plants.

Basic Safety Principles for Nuclear Power Plants

Author : International Nuclear Safety Advisory Group,International Atomic Energy Agency
Publisher : Unknown
Page : 118 pages
File Size : 47,8 Mb
Release : 1999
Category : Business & Economics
ISBN : UOM:39015042637481

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Basic Safety Principles for Nuclear Power Plants by International Nuclear Safety Advisory Group,International Atomic Energy Agency Pdf

The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.

Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors

Author : International Atomic Energy Agency
Publisher : IAEA
Page : 84 pages
File Size : 51,7 Mb
Release : 2003
Category : Business & Economics
ISBN : UOM:39015052977132

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

This report contains practical guidance for performing accident analysis for nuclear power plants with pressurised 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.