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The Resource Genshiryoku Kyokasho

Genshiryoku Kyokasho

Label
Genshiryoku Kyokasho
Title
Genshiryoku Kyokasho
Creator
Subject
Language
eng
Member of
Cataloging source
MiAaPQ
Literary form
non fiction
Nature of contents
dictionaries
Series statement
An Advanced Course in Nuclear Engineering Ser.
Series volume
v.8
Genshiryoku Kyokasho
Label
Genshiryoku Kyokasho
Link
http://libproxy.rpi.edu/login?url=https://ebookcentral.proquest.com/lib/rpi/detail.action?docID=4816312
Publication
Copyright
Related Contributor
Related Location
Related Agents
Related Authorities
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Related Items
Carrier category
online resource
Carrier category code
cr
Carrier MARC source
rdacarrier
Color
multicolored
Content category
text
Content type code
txt
Content type MARC source
rdacontent
Contents
  • Series Aims and Scopes -- Preface -- Contents -- Editor, Authors, and Collaborators -- Author and Editor -- Authors -- Collaborators -- Chapter 1: Designing a New Reactor -- 1.1 Thinking Process and Design Methods for a New Reactor -- 1.1.1 New Technology Creation and Design Methodology -- 1.1.2 Thinking Process on New Reactor Design -- 1.1.3 Actual Design and Constraints -- 1.2 Research and Development -- 1.2.1 Roles of Reactors in Research and Development -- 1.2.2 Basic and Mock-Up Tests -- 1.2.3 Using Numerical Simulation -- 1.3 Design, Construction and Operation -- 1.3.1 Design Standards and Design -- 1.3.2 Construction and Operation Experience -- 1.3.3 Development Organizations and Systems -- Further Readings -- References -- Chapter 2: Purpose and History of Fast Reactors -- 2.1 Continual Use of Nuclear Energy -- 2.1.1 Release from the Restrictions of Uranium Resources -- 2.1.2 Reduction of Environmental Burden of High-Level Radioactive Waste -- 2.1.3 Targets of FR Development -- 2.2 Development History of FRs -- 2.2.1 Changes in Coolant -- 2.2.2 Changes in Core and Fuel -- 2.2.3 Major Accident/Trouble Experiences -- 2.3 Present Development Situations of FRs -- 2.3.1 Situations by Country -- 2.3.2 International Cooperation -- Further Readings -- References -- Chapter 3: Plant Concepts and Mechanisms -- 3.1 Mechanism of Breeding -- 3.1.1 Fission and Plutonium Generation by Fast Neutrons -- 3.1.2 Mechanism of Fast Neutron Utilization -- 3.2 Mechanism for the Reduction of Toxicity in High-Level Radioactive Waste -- 3.3 Heat Transport for Core Cooling and Power Generation Using Liquid Metal Sodium -- 3.3.1 Liquid Metal Coolant Suitable for the Use of Fast Neutrons -- 3.3.2 Sodium-Cooled Fast Reactor Plant System: Heat Transport from Reactor Core to Steam Turbine -- 3.3.3 Plant System Suitable for Liquid Metal Coolant with a High Boiling Point
  • Reference -- Chapter 4: Policy of Safety Assurance (Design Constraints and Additional Functional Requirements) -- 4.1 Fundamental Philosophy of Safety Assurance for Nuclear Reactor Facilities -- 4.1.1 Safety Goals and Risk Management -- 4.1.2 Policy of Safety Assurance (Defense in Depth and Fundamental Safety Function) -- 4.1.3 Measures against Severe Accident -- 4.2 Characteristics of Fast Reactors and Basic Policy of Safety Assurance -- 4.2.1 Safety Characteristics of Fast Reactors [7] -- 4.2.2 Safety Approach of Fast Reactors -- 4.2.3 Safety Requirements and Safety Evaluation of Fast Reactors -- 4.3 Measures to Satisfy the Requirements of Safety Functions Specific to Fast Reactors -- 4.3.1 Characteristics of Core Fuels and Associated Safety Measures -- 4.3.2 Safety Measures Associated with Usage of Sodium -- 4.3.3 Severe Accident Measures of Fast Reactors -- References -- Chapter 5: Mind-Set Required to Ensure Structural Integrity (Design Constraints) -- 5.1 Mind-Set Required to Ensure the Structural Integrity of Reactor Facilities -- 5.1.1 Integrated Management in Terms of Material, Design, Manufacturing, Inspection and Maintenance -- 5.1.2 Structural Design Methods for Nuclear Components -- 5.2 Features of Structural Design Conditions of FRs -- 5.2.1 Loading Conditions Specific to the Use of Sodium -- 5.2.2 Types and Prediction of Thermal Loads -- 5.2.3 Failure Modes Assumed in FRs -- 5.3 Measures for Ensuring Structural Integrity of FRs -- 5.3.1 Approaches from Material, Design, Manufacturing, Inspection, and Maintenance Perspectives and the Resulting Constraints -- 5.3.2 Structural Design for High Temperatures and Thermal Stress -- 5.3.3 Aseismic Design of Thin-Walled Structures -- 5.4 Measures for the Mitigation of Loads -- 5.4.1 Thermal Load Mitigation Method -- 5.4.2 Seismic Isolation Structure -- Further Readings -- References
  • Chapter 6: System Conceptual Design (From Function to Mechanism) -- 6.1 System Conceptual Design -- 6.2 Major System Configuration -- 6.2.1 Core Configuration -- 6.2.2 Reactor Structure Configuration -- 6.2.3 Main Cooling System Configuration -- 6.2.4 Configurations of Fuel Handling and Storage Facilities -- 6.2.5 Auxiliary Sodium Equipment Configuration -- 6.2.6 Safety System Configuration -- 6.2.7 Instrumentation and Control System -- 6.2.8 Power Supply Equipment -- 6.3 Various Factors of System Integration -- 6.3.1 Factors Determined by Heat Balance -- 6.3.2 Factors Determined by Balance Between Functional Requirements and Safety and Structural Integrity Constraints -- 6.3.3 Factors for Achieving Physical Consistency Among Systems -- 6.3.4 Factors Determined by Cost and Technological Level -- Further Readings -- References -- Chapter 7: Core and Fuel Design (From Mechanism to Structure) -- 7.1 Core Components (Fuel Assembly, Control Rod Assembly, Neutron Shield Assembly, Neutron Source Assembly, Surveillance Assem... -- 7.2 Core and Fuel Structure -- 7.3 Blanket Fuel and Breeding Characteristic -- 7.4 Brief Flow of Core Design -- 7.4.1 Determination of Thermal Output -- 7.4.2 Determination of the Number of Fuel Assemblies -- 7.4.3 Determination of the Number of Fuel Pins -- 7.4.4 Determination of Fuel Stack Length and LHR -- 7.4.5 Determination of Fuel Burnup -- 7.4.6 Determination of Fast Neutron Flux and Plutonium Content -- 7.4.7 Determination of Coolant Flow Rate -- 7.4.8 Determination of Basic Fuel Specifications -- 7.5 Core Design -- 7.5.1 Activities Related to Core Design (What Is Core Design?) -- 7.5.2 Trend of Core Design -- 7.5.3 Fundamentals of Reactor Physics for Nuclear Design -- 7.5.4 Nuclear Design -- 7.5.5 Thermal Hydraulic Design -- 7.5.6 Plant Dynamics Analysis -- 7.6 Fuel Design -- 7.6.1 Characteristics of FR Fuel
  • 7.6.2 Trend of Fast Reactor Fuel Design -- 7.6.3 Fast Reactor Fuel Design -- 7.7 Fuel Research and Development -- 7.7.1 Development of Cladding Material for Increased Burnup -- 7.7.2 Basic Research and Physical Property Measurement of Fast Reactor Fuel -- 7.7.3 Fuel Irradiation Test -- 7.8 Integrity Evaluation of Control Rod Assembly -- 7.9 Control of Plutonium Content in Fuel Fabrication Process -- Further Readings -- References -- Chapter 8: Plant Component Design (from Mechanism to Structure) -- 8.1 Thinking Process of Plant Component Design -- 8.2 Reactor System Component Design -- 8.2.1 Reactor Vessel and Primary Tank -- 8.2.2 Shield Plug and Roof-Deck -- 8.2.3 Upper Core Structure and Control Rod Drive Mechanism -- 8.3 Design of Main Cooling System Components -- 8.3.1 Main Circulation Pump -- 8.3.2 Intermediate Heat Exchanger -- 8.3.3 Main Cooling System Piping -- 8.3.4 Steam Generator -- 8.4 Fuel Handling System Design -- 8.5 Instrumentation and Control System Design -- References -- Chapter 9: Maintenance -- 9.1 Relationship Between Design and Maintenance -- 9.2 NPP Maintenance [1] -- 9.2.1 What Is Maintenance? -- 9.2.2 Major Features of the NPP from the Perspective of Maintenance -- 9.2.3 Deterioration and Maintenance -- 9.2.4 PDCA Cycle of Maintenance Program -- 9.2.5 Maintenance Technology -- 9.3 Maintenance of Fast Reactors -- 9.3.1 Features of Fast Reactors from the Perspective of Maintenance -- 9.3.2 FR Maintenance and Operation [2] -- 9.3.3 Activities Necessary for FR Maintenance [7] -- 9.3.4 In-Service Inspection (ISI) -- 9.3.5 FR Repair Technology -- 9.3.6 Reflection to Design -- Further Readings -- References -- Chapter 10: Actual Monju Design -- 10.1 Policy for the Development of Monju -- 10.1.1 Background and Technical Level at the Time of Monju Design -- 10.1.2 Monju Design Policy and Procedures -- 10.1.3 History of Monju Design
  • 10.1.4 Relation Between the Flow to Decide Main Specifications and Design Thinking Process -- 10.2 Flow of Monju Conceptual Design -- 10.2.1 Design Step 1: Philosophy -- 10.2.2 Design Step 2: Function -- 10.2.3 Design Step 3: From Function to Mechanism -- 10.2.4 Design Step 4 : From Mechanism to Structure -- 10.3 Research and Development (RandD) Activities for Monju -- 10.3.1 Design and RandD -- 10.3.2 Important RandD Items -- 10.4 Monju Design Process Flow and Adjustment of Specifications -- 10.4.1 Design Process Flow of Each System -- 10.4.2 Features of Design Flow and the Summary -- 10.5 Design Limits of Monju -- 10.6 Key Items in Monju Design -- 10.6.1 Policy of Safety Design -- 10.6.2 High-Temperature Structural Design Guide and Material Strength Standards -- 10.6.3 Heat Generation and Removal Capabilities in Reactor -- 10.6.4 Reliability of Reactor Shutdown System -- 10.6.5 Decay Heat Removal Function -- 10.6.6 Design of Containment Vessel -- 10.6.7 Function to Suppress Fire Due to Leaked Sodium -- 10.7 Verification of Monju Design Technology -- Further Readings -- References
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{'f': 'http://opac.lib.rpi.edu/record=b4393439'}
Extent
1 online resource (307 pages)
Form of item
online
Isbn
9789811028212
Media category
computer
Media MARC source
rdamedia
Media type code
c
Sound
unknown sound
Specific material designation
remote

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