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Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors

Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors PDF Author: Alexey I. Soldatov
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 720

Book Description
In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and Reactor Control System shadowing. The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). This section also includes discussion of the parameters important for safety and evaluation of Reactor Control System options for the proposed core design. An evaluation of the sensitivity of the proposed design to uncertainty in calculated parameters is presented in chapter 4-5. The results presented in this dissertation cover a new area of reactor design and operational parameters, and may be applicable to other small and large pressurized water reactor designs.

Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors

Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors PDF Author: Alexey I. Soldatov
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 720

Book Description
In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and Reactor Control System shadowing. The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). This section also includes discussion of the parameters important for safety and evaluation of Reactor Control System options for the proposed core design. An evaluation of the sensitivity of the proposed design to uncertainty in calculated parameters is presented in chapter 4-5. The results presented in this dissertation cover a new area of reactor design and operational parameters, and may be applicable to other small and large pressurized water reactor designs.

Nuclear Reactor Design

Nuclear Reactor Design PDF Author: Yoshiaki Oka
Publisher: Springer
ISBN: 443154898X
Category : Technology & Engineering
Languages : en
Pages : 337

Book Description
This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Nuclear Power Reactor Designs

Nuclear Power Reactor Designs PDF Author: Jun Wang
Publisher: Elsevier
ISBN: 0323999468
Category : Science
Languages : en
Pages : 465

Book Description
Nuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear reactor designs of today and the future. Focused on the structure, systems and relevant components of each reactor design, this book provides the readers with answers to key questions to help them understand the benefits of each design. Each reactor design is introduced, their origin defined, and the relevant research presented before an analysis of its successes, what was learned, and how research and technology advanced as a result are presented. Students, researchers and early career engineers will gain a solid understanding of how nuclear designs have evolved, and how they will continue to develop in the future. Presents reactor designs through history to present day, focusing on key structures, systems and components Provides readers with quick answers about various design principles and rationales Includes new approaches such as the micro-reactor and small-modular reactors

Super Light Water Reactors and Super Fast Reactors

Super Light Water Reactors and Super Fast Reactors PDF Author: Yoshiaki Oka
Publisher: Springer
ISBN: 9781441960511
Category : Technology & Engineering
Languages : en
Pages : 651

Book Description
Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.

Handbook of Small Modular Nuclear Reactors

Handbook of Small Modular Nuclear Reactors PDF Author: Daniel T. Ingersoll
Publisher: Woodhead Publishing
ISBN: 0128239174
Category : Technology & Engineering
Languages : en
Pages : 648

Book Description
Handbook of Small Modular Nuclear Reactors, Second Edition is a fully updated comprehensive reference on Small Modular Reactors (SMRs), which reflects the latest research and technological advances in the field from the last five years. Editors Daniel T. Ingersoll and Mario D. Carelli, along with their team of expert contributors, combine their wealth of collective experience to update this comprehensive handbook that provides the reader with all required knowledge on SMRs, expanding on the rapidly growing interest and development of SMRs around the globe. This book begins with an introduction to SMRs for power generation, an overview of international developments, and an analysis of Integral Pressurized Water Reactors as a popular class of SMRs. The second part of the book is dedicated to SMR technologies, including physics, components, I&C, human-system interfaces and safety aspects. Part three discusses the implementation of SMRs, covering economic factors, construction methods, hybrid energy systems and licensing considerations. The fourth part of the book provides an in-depth analysis of SMR R&D and deployment of SMRs within eight countries, including the United States, Republic of Korea, Russia, China, Argentina, and Japan. This edition includes brand new content on the United Kingdom and Canada, where interests in SMRs have increased considerably since the first edition was published. The final part of the book adds a new analysis of the global SMR market and concludes with a perspective on SMR benefits to developing economies. This authoritative and practical handbook benefits engineers, designers, operators, and regulators working in nuclear energy, as well as academics and graduate students researching nuclear reactor technologies. Presents the latest research on SMR technologies and global developments Includes new case study chapters on the United Kingdom and Canada and a chapter on global SMR markets Discusses new technologies such as floating SMRs and molten salt SMRs

Thermal Hydraulic and Fuel Performance Analysis for Innovative Small Light Water Reactor Using VIPRE-01 and FRAPCON-3

Thermal Hydraulic and Fuel Performance Analysis for Innovative Small Light Water Reactor Using VIPRE-01 and FRAPCON-3 PDF Author: Anh T. Mai
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 151

Book Description
The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity. The MASLWR design is geared toward providing electricity to small communities in remote locations in developing countries where constructions of large nuclear power plants are not economical. The MASLWR reactor is designed to operate for five years without refueling and with fuel enrichment up to 8 %. In 2003, an experimental thermal hydraulic research facility also known as the OSU MASLWR Test Facility was constructed at Oregon State University to examined the performance of new reactor design and natural circulation reactor design concepts. This thesis is focused on the thermal hydraulics analysis and fuel performance analysis of the MASLWR prototypical cores with fuel enrichment of 4.25 % and 8 %. The goals of the thermal hydraulic analyses were to calculate the departure nucleate boiling ratio (DNBR) values, coolant temperature, cladding temperature and fuel temperature profiles in the hot channel of the reactor cores. The thermal hydraulic analysis was performed for steady state operation of the MASLWR prototypical cores. VIPRE Version 01 is the code used for all the computational modeling of the prototypical cores during thermal hydraulic analysis. The hot channel and hot rod results are compared with thermal design limits to determine the feasibility of the prototypical cores. The second level of analysis was performed with a fuel performance code FRAPCON for the limiting MASLWR fuel rods identified by the neutronic and thermal hydraulic analyses. The goals of the fuel performance analyses were to calculate the oxide thickness on the cladding and fission gas release (FGR). The oxide thickness results are compared with the acceptable design limits for standard fuel rods. The results in this research can be helpful for future core designs of small light water reactors with natural circulation.

Boiling Water Reactors

Boiling Water Reactors PDF Author: Koji Nishida
Publisher: Elsevier
ISBN: 012821368X
Category : Business & Economics
Languages : en
Pages : 618

Book Description
Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered. The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs. Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers societal impacts and sustainability concerns and goals throughout the discussion Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource

Design of the Reactor Core for Nuclear Power Plants: IAEA Safety Standards Series No. Ssg-52

Design of the Reactor Core for Nuclear Power Plants: IAEA Safety Standards Series No. Ssg-52 PDF Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201038197
Category : Technology & Engineering
Languages : en
Pages : 69

Book Description
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 SSR-2/1 (Rev. 1) 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.

Neutronic Analysis For Nuclear Reactor Systems

Neutronic Analysis For Nuclear Reactor Systems PDF Author: Bahman Zohuri
Publisher: Springer
ISBN: 303004906X
Category : Technology & Engineering
Languages : en
Pages : 663

Book Description
This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors – reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today’s modern energy spectrum. Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory; Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors; Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.

Design of the Reactor Core for Nuclear Power Plants

Design of the Reactor Core for Nuclear Power Plants PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 82

Book Description
This publication makes recommendations concerning safety features for incorporation into the design of the reactor core for a nuclear power plant, taking account of recent developments in the design of the reactor core and including guidance on general and specific design considerations. It supersedes IAEA Safety Series No. 50-SG-D14.