Safety of Sodium-Cooled Fast Reactors

Safety of Sodium-Cooled Fast Reactors
Author: Songbai Cheng
Publisher: Springer
Total Pages: 0
Release: 2022-09-29
Genre: Science
ISBN: 9789811661181

This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems. Its safety is a critical issue during its R&D process. The book elaborates on research progresses in particle bed-related phenomena in terms of the molten-pool mobility, the molten-pool sloshing motion, the debris bed formation behavior, and the debris bed self-leveling behavior. The book serves as a good reference for researchers, professionals, and postgraduate students interested in sodium-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and light water reactors.

Verification, Validation and Uncertainty Quantification of Multi-Physics Modeling of Nuclear Reactors

Verification, Validation and Uncertainty Quantification of Multi-Physics Modeling of Nuclear Reactors
Author: Maria Avramova
Publisher: Woodhead Publishing Series in
Total Pages: 300
Release: 2018-09-15
Genre: Technology & Engineering
ISBN: 9780128149546

Verification, Validation and Uncertainty Quantification in Multi-Physics Modeling of Nuclear Reactors is a key reference for those tasked with ensuring the credibility and reliability of engineering models and simulations for the nuclear industry and nuclear energy research. Sections discuss simulation challenges and revise key definitions, concepts and terminology. Chapters cover solution verification, the frontier discipline of multi-physics coupling verification, model validation and its applications to single and multi-scale models, and uncertainty quantification. This essential guide will greatly assist engineers, scientists, regulators and students in applying rigorous verification, validation and uncertainty quantification methodologies to the M&S tools used in the industry. The book contains a strong focus on the verification and validation procedures required for the emerging multi-physics M&S tools that have great potential for use in the licensing of new reactors, as well as for power uprating and life extensions of operating reactors. Uniquely--and crucially for nuclear engineers--demonstrates the application of verification, validation and uncertainty methodologies to the modeling and simulation (M&S) of nuclear reactors Equips the reader to develop a rigorously defensible validation process irrespective of the particular M&S tool used Brings the audience up-to-speed on validation methods for traditional M&S tools Extends the discussion to the emerging area of validation of multi-physics and multi-scale nuclear reactor simulations

Development of a Lumped Parametric Model for Scoping Investigations of Uncertainties in Fast Reactor Probabilistic Safety Analysis. Progress Report, October 10, 1974--October 10, 1975

Development of a Lumped Parametric Model for Scoping Investigations of Uncertainties in Fast Reactor Probabilistic Safety Analysis. Progress Report, October 10, 1974--October 10, 1975
Author:
Publisher:
Total Pages:
Release: 1975
Genre:
ISBN:

The objective of the researh reported is to explore the possibility of the development of a novel reactor safety analysis methodology suitable for a parametric investigation of uncertainties in the progression of severe fast reactor accidents. The essential feature of this approach is a description of the reactor state by means of volumetric distributions (the distribution of volume of reactor materials, such as coolant, clad, and fuel, with temperature and in the case of fuel material, also with power). Stationary volumetric distributions are computed from detailed spatial temperature and power distributions of materials in the steady state reactor. Stationary volumetric distributions and other reactor physics quantities form the input for the reactor transient calculations in which the accident progression is described by the behavior of transient volumetric distributions. The report discusses the representation of spatial temperature distributions, the theory and calculation of stationary volumetric distributions, and includes examples of single subassembly and reactor distributions. The status of reactor neutronic code development and application is discussed and results are displayed.

Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors
Author: Igor Pioro
Publisher: Woodhead Publishing
Total Pages: 1112
Release: 2022-12-07
Genre: Technology & Engineering
ISBN: 0128226536

Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors

Safety of Sodium-Cooled Fast Reactors: Molten-pool Mobility.-Chapter 3 Molten-pool Sloshing Motion.-Chapter 4: Debris Bed Formation Behavior

Safety of Sodium-Cooled Fast Reactors: Molten-pool Mobility.-Chapter 3 Molten-pool Sloshing Motion.-Chapter 4: Debris Bed Formation Behavior
Author: Songbai Cheng
Publisher:
Total Pages: 0
Release: 2021
Genre:
ISBN: 9789811661174

This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems. Its safety is a critical issue during its R&D process. The book elaborates on research progresses in particle bed-related phenomena in terms of the molten-pool mobility, the molten-pool sloshing motion, the debris bed formation behavior, and the debris bed self-leveling behavior. The book serves as a good reference for researchers, professionals, and postgraduate students interested in sodium-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and light water reactors.