Computation And Analysis Of Nuclear Data Relevant To Nuclear Energy And Safety
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Computation And Analysis Of Nuclear Data Relevant To Nuclear Energy And Safety by M K Mehta,J J Schmidt Pdf
This book focuses on the modern nuclear models and computer codes used in nuclear model calculations of nuclear data required for nuclear technology and nuclear safety applications.
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.
Best Estimate Safety Analysis for Nuclear Power Plants by Anonim Pdf
Deterministic safety 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). IAEA Safety Standards Series No. NS-R-1.2 and Safety Reports Series No. 23 recommend, as one of the options for demonstrating the inclusion of adequate safety margins, the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. The evaluation of uncertainties is an issue of considerable complexity, and this Safety Report has been developed to complement the existing publications. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis of NPPs and practical guidance in the use of these methods.
Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop by Pavol Oblozinsky,A Gandini Pdf
This volume provides the up-to-date information behind nuclear reactor calculations, focusing on a key role of nuclear reaction data, down to the physics of nuclear interactions. It is divided into three parts. Part 1 deals with nuclear reaction models, including neutron resonances, fission, the optical model, statistical and preequilibrium models as well as nuclear level densities. Part 2 is devoted to nuclear data filling and processing; it includes lectures on nuclear data evaluation and formatting, data libraries and services, with emphasis on nuclear-data-processing codes. Part 3 presents applications in nuclear reactor calculations, emphasizing physics, design and safety.
Nuclear Data Needs for Generation IV Nuclear Energy Systems by P. Rullhusen Pdf
This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems. The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems. The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems. Contents: Nuclear Data Needs for Generation IV Systems: Future of Nuclear Energy and the Role of Nuclear Data (P Finck); Nuclear Data Needs for Generation IV Nuclear Energy Systems OCo Summary of US Workshop (T A Taiwo & H S Khalil); Innovative Fuel Types for Minor Actinides Transmutation (D Haas et al.); Benchmarks, Sensitivity Calculations, Uncertainties: Sensitivity of Advanced Reactor and Fuel Cycle Performance Parameters to Nuclear Data Uncertainties (G Aliberti et al.); Computer Model of an Error Propagation Through Micro-Campaign of Fast Neutron Gas Cooled Nuclear Reactor (E Ivanov); Generating Covariance Data with Nuclear Models (A J Koning); Experiments: INL Capabilities for Nuclear Data Measurements Using the Argonne Intense Pulsed Neutron Source Facility (J D Cole et al.); Cross-Section Measurements in the Fast Neutron Energy Range (A Plompen); Recent Measurements of Neutron Capture Cross Sections for Minor Actinides by an JNC and Kyoto University Group (H Harada et al.); Evaluated Data Libraries: Nuclear Data Evaluation for Generation IV (G Nogu re et al.); Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes (P Talou et al.); and several other important contributions. Readership: Graduate students and nuclear physicists interested in experimental nuclear physics, nuclear reactions modeling, and reactor physics, especially the development of Generation IV reactors."
Best Estimate Safety Analysis for Nuclear Power Plants by IAEA. Pdf
Deterministic safety 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). IAEA Safety Standards Series No. NS-R-1.2 and Safety Reports Series No. 23 recommend, as one of the options for demonstrating the inclusion of adequate safety margins, the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. The evaluation of uncertainties is an issue of considerable complexity, and this Safety Report.
Nuclear Power Plant Design and Analysis Codes by Jun Wang,Xin Li,Chris Allison,Judy Hohorst Pdf
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Safety of Nuclear Power Plants by International Atomic Energy Agency Pdf
On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.
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.
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.
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.
Benchmarking Against Experimental Data of Neutronics and Thermohydraulic Computational Methods and Tools for Operation and Safety Analysis of Research Reactors by International Atomic Energy Agency Pdf
This publication presents the results of an IAEA coordinated research project (CRP). The benchmark analysis performed under this CRP covered steady state and transient conditions for research reactors across a range of designs, power levels, operating regimes and experimental facilities. The results obtained by the individual CRP participants are consolidated for each benchmark specification and conclusions are drawn on the specifications, modelling approaches and user effects, and computer codes used in the analysis. This publication supplements IAEA Technical Report Series No. 480, Research Reactor Benchmarking Database: Facility Specification and Experimental Data, which was developed within the same CRP. The publication is intended for use by operating organizations, researchers, regulatory bodies, designers and other interested parties involved in the safety, operation and utilization of research reactors. The individual country reports are available on the attached CD¬ROM.
