Table Of ContentMechanical Engineering Raj Sodium Fast Reactors
Chellapandi
Rao
“A comprehensive source book providing information about various aspects of fast
Closed Fuel Cycle
reactors and their associated fuel cycles.”
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—R.K. Sinha, Secretary, Department of Atomic Energy and Chairman, Atomic with
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Energy Commission, Mumbai, India
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“… covers the full fuel cycle for sodium-cooled fast reactors and includes valuable u
construction experience.” m
—Dr. Alan E. Waltar, Director, Nuclear Energy, Pacific Northwest National Lab,
Richland, Washington, USA (Retired) and Professor and Head, Nuclear Engineering, F
Texas A&M University, College Station, USA (Retired) a
s
t
R
Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of
an important technology that is being harnessed for commercial energy production e
in many parts of the world. Presenting the state of the art of sodium-cooled fast a
reactors with closed fuel cycles, this book c
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• Offers in-depth coverage of reactor physics, materials, design, safety
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analysis, validations, engineering, construction, and commissioning aspects
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• Features a special chapter on allied sciences to highlight advanced reactor w
core materials, specialized manufacturing technologies, chemical sensors, i
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in-service inspection, and simulators h
C
• Addresses design essentials with a focus on reactor assembly including
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core and coolant circuits, fuel handling, instrumentation and control, energy o
conversion, and containment systems s
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• Provides design codes and standards with sufficient background information d
to ensure a solid understanding of the underlying mechanics
F
• Supplies guidelines for concept selection, design, analysis, and validation u
e
Sodium Fast Reactors with Closed Fuel Cycle is a valuable reference for l
industry professionals involved in the construction of fast-reactor power plants,
C
as well as graduate-level engineering students of the design and development of
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sodium-cooled fast-reactor systems and components.
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e
K20354
Baldev Raj | P. Chellapandi | P.R. Vasudeva Rao
ISBN: 978-1-4665-8767-0
90000
9 781466 587670
K20354_COVER_final.indd 1 3/4/15 11:02 AM
Sodium Fast Reactors
Closed Fuel Cycle
with
Sodium Fast Reactors
Closed Fuel Cycle
with
Baldev Raj
P. Chellapandi
P.R. Vasudeva Rao
CRC Press
Taylor & Francis Group
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Boca Raton, FL 33487-2742
© 2015 by Taylor & Francis Group, LLC
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Version Date: 20150223
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Contents
Foreword ........................................................................................................................................xxv
Preface..........................................................................................................................................xxvii
Authors ..........................................................................................................................................xxix
Section i Basis and concepts
Chapter 1 Nuclear Fission and Breeding ......................................................................................3
1.1 Introduction .......................................................................................................3
1.2 About the Neutron .............................................................................................3
1.3 Nucleus Stability ................................................................................................4
1.4 Energy from Fission ..........................................................................................4
1.5 Fission Neutrons and Energy Spectrum ............................................................6
1.6 Chain Reaction ..................................................................................................7
1.7 Fissile and Fertile Materials ..............................................................................7
1.8 About Breeding .................................................................................................8
1.9 Working of Nuclear Reactors ..........................................................................10
1.10 Reactor Control and Safety: Reactor Physics ..................................................11
References ..................................................................................................................14
Chapter 2 Fast Spectrum Reactor vis-à-vis Pressurized Water Reactors ...................................15
2.1 Introduction .....................................................................................................15
2.2 Neutronic Characteristics ................................................................................15
2.3 Safety Characteristics ......................................................................................17
2.4 Geometric Features of Core ............................................................................19
References ..................................................................................................................22
Chapter 3 Description of a Fast Spectrum Reactor ....................................................................23
3.1 Introduction .....................................................................................................23
3.2 Core and Reactor Assembly ............................................................................23
3.3 Main Heat Transport System ...........................................................................24
3.4 Component Handling ......................................................................................24
3.5 Steam–Water System .......................................................................................25
3.6 Electrical Power Systems ................................................................................25
3.7 Instrumentation and Control ...........................................................................25
Chapter 4 Unique Worthiness of SFR .........................................................................................27
4.1 Introduction .....................................................................................................27
4.2 Uranium Utilization in the Open Fuel Cycle Mode ........................................27
4.3 Uranium Utilization in the Closed Fuel Cycle Mode ......................................29
4.4 Fuel Utilization in the Fast Breeder Reactor: A Case Study ...........................31
v
vi Contents
4.5 High-Level Radioactive Waste Management and Environmental Issues ........32
4.6 Minor Actinide Burning Design Concepts ......................................................33
4.7 Typical Minor Actinide Burning Scenario in Fast Spectrum Reactors (FSRs) .....35
References ..................................................................................................................35
Chapter 5 Design Objectives for the Efficient Use of Natural Uranium and Plutonium ............37
5.1 Introduction .....................................................................................................37
5.2 Growth .............................................................................................................37
5.2.1 Sustainability ......................................................................................38
5.2.2 Economics ..........................................................................................38
5.2.3 Safety and Reliability .........................................................................39
5.2.4 Proliferation Resistance and Physical Protection ...............................39
5.3 Performance and Fuel Consumption Aspects .................................................43
References ..................................................................................................................43
Chapter 6 Prospect of Various Types of FSRs ............................................................................45
6.1 Introduction .....................................................................................................45
6.2 Sodium-Cooled Fast Reactors .........................................................................45
6.3 Lead-Cooled Fast Reactors .............................................................................45
6.4 Molten Salt Reactors........................................................................................46
6.5 Gas-Cooled Fast Reactors ...............................................................................48
6.6 Comparison of Advanced Fast Reactors with SFRs........................................50
6.7 Fast Reactors That Evolved Post-Fukushima ..................................................50
6.7.1 Advanced Sodium Technological Reactor for Industrial
Demonstration ....................................................................................50
6.7.2 Japan Sodium-Cooled Fast Reactor ...................................................50
6.7.3 Advanced Fast Reactor .......................................................................52
6.7.4 European Lead-Cooled Fast Reactor .................................................53
References ..................................................................................................................53
Section ii Design of Sodium Fast Reactors
Chapter 7 Choice of Materials and Their Performance ..............................................................57
7.1 Introduction .....................................................................................................57
7.2 Fuel ..................................................................................................................57
7.2.1 Oxide Fuel ..........................................................................................57
7.2.1.1 Physical Properties .............................................................58
7.2.1.2 Swelling ..............................................................................58
7.2.1.3 Fission Gas Release ............................................................59
7.2.1.4 Fuel Clad Compatibility .....................................................59
7.2.1.5 Fuel-Coolant Compatibility ................................................60
7.2.1.6 Performance at Higher Burnup ...........................................60
7.2.2 Metal Fuel ..........................................................................................60
7.2.2.1 Physical Properties .............................................................61
7.2.2.2 Fission Gas Release ............................................................61
7.2.2.3 Swelling ..............................................................................62
7.2.2.4 Fuel-Cladding Chemical Interaction .................................63
Contents vii
7.2.3 Carbide Fuels ......................................................................................63
7.2.3.1 Physical Properties .............................................................63
7.2.3.2 Fission Gas Release ............................................................63
7.2.3.3 Swelling ..............................................................................63
7.2.4 Nitride Fuel.........................................................................................64
7.2.5 Cermet Fuel ........................................................................................65
7.2.6 General Intercomparison ....................................................................65
7.3 Core Structural Materials ................................................................................65
7.3.1 Environment .......................................................................................66
7.3.2 Effects of Irradiation ..........................................................................67
7.3.3 Irradiation Damage ............................................................................67
7.3.3.1 Phase Stability ....................................................................68
7.3.3.2 Void Swelling ......................................................................68
7.3.3.3 Irradiation Creep.................................................................69
7.3.3.4 Mechanical Properties ........................................................70
7.3.4 Choice of Materials ............................................................................72
7.3.5 Advanced Materials and Improvements .............................................76
7.3.5.1 Advanced Austenitic Stainless Steels .................................77
7.3.5.2 Ferritic Steels ......................................................................77
7.3.5.3 ODS Steels ..........................................................................79
7.3.5.4 Accelerator as a Means of Material Development ..............80
7.3.6 Safety Limits with Respect to Materials ............................................81
7.3.7 Structural Design Criteria ..................................................................82
7.4 Reactor Structures ...........................................................................................85
7.4.1 Materials for the Reactor Systems Including Piping ..........................86
7.4.2 Welding Consumables and Properties of Welds ................................90
7.4.3 Materials for Steam Generator ...........................................................92
7.4.4 Welding Consumables for Modified 9Cr–1Mo Steel .........................96
7.4.4.1 Use of Modified 9Cr–1Mo Steel for Thick Sections ..........96
7.4.5 Tri-Metallic Transition Joint ..............................................................96
7.5 Coolant ............................................................................................................97
7.5.1 Physical Properties .............................................................................98
7.5.2 Nuclear Properties ..............................................................................98
7.5.2.1 Radiological ........................................................................98
7.5.2.2 Reactivity Coefficients of Sodium Coolant and
Reactor Safety .....................................................................98
7.5.2.3 Temperature Reactivity Coefficient and Sodium Void
Coefficient ...........................................................................99
7.5.3 Chemical Properties ...........................................................................99
7.5.3.1 Specifications and Chemical Quality Control ..................100
References ................................................................................................................100
Chapter 8 System and Components ..........................................................................................103
8.1 Introduction ...................................................................................................103
8.2 Reactor Core ..................................................................................................103
8.2.1 Design Constraints ...........................................................................103
8.2.2 Major Steps in the Core Design .......................................................106
8.2.3 Selection of Fuel Pin Diameter ........................................................107
8.2.4 Fuel Pin Constitutions ......................................................................109
8.2.5 Spacing of Pins .................................................................................109
viii Contents
8.2.6 Concept of Subassembly ..................................................................112
8.2.7 SA Composition ...............................................................................112
8.2.8 Flow Distribution to the Core ...........................................................113
8.3 Nuclear Steam Supply System .......................................................................116
8.3.1 Pool versus Loop Concepts ..............................................................116
8.3.2 Conceptual Design of NSSS Components .......................................119
8.3.2.1 Reactor Assembly Components in the Pool-Type Concept ....120
8.3.2.2 Reactor Block in the Loop-Type Concept.........................122
8.3.2.3 Reactor Assembly Support Arrangements .......................123
8.3.2.4 Design Features of Reactor Assembly Components .........123
8.3.2.5 Secondary Sodium Circuit ................................................139
8.3.2.6 Decay Heat Removal Circuit ............................................149
8.3.2.7 Reactor Vessel Auxiliary Cooling System .......................152
8.3.2.8 Sodium Purification Circuit ..............................................156
8.3.2.9 Reactor Vault ....................................................................160
8.3.2.10 Operating Temperatures and Design Life ........................161
8.4 Reactor Mechanisms .....................................................................................162
8.4.1 Shutdown Systems ............................................................................163
8.4.1.1 Absorber Materials ...........................................................163
8.4.1.2 Description of a Typical Shutdown System ......................163
8.4.1.3 Diversity of Shutdown Systems ........................................164
8.4.1.4 Essential Safety Criteria ...................................................165
8.4.1.5 Passive Design Features ....................................................166
8.4.2 Fuel Handling System ......................................................................167
8.4.2.1 Fuel Handling Operations.................................................167
8.4.2.2 Fuel Handling System Components .................................173
8.4.2.3 Major Safety Requirements during Fuel Handling ..........177
8.4.2.4 Fuel Handling Experiences and R&D Requirements .......179
8.5 Instrumentation and Control System .............................................................181
8.5.1 Basic Functions of I&C ....................................................................181
8.5.2 General Design Features ..................................................................182
8.5.3 Type of Instrumentation ...................................................................183
8.5.3.1 Nuclear Instruments ..........................................................183
8.5.3.2 Sodium Instruments ..........................................................184
8.5.3.3 Conventional Instruments .................................................190
8.5.4 Signal Processing .............................................................................190
8.5.4.1 Safety-Critical Systems ....................................................190
8.5.5 Safety-Related Systems ....................................................................191
8.5.6 Nonnuclear Safety ............................................................................191
8.5.7 Control Architecture ........................................................................191
8.5.8 Control Room ...................................................................................191
8.5.9 Process Computer .............................................................................191
8.5.10 Reactor Protection System ...............................................................192
8.5.11 Postaccident Monitoring ..................................................................192
8.5.12 Main Control Loops .........................................................................193
8.5.12.1 Reactor Power Control ......................................................193
8.5.12.2 Primary and Secondary Coolant Flow Controls ..............193
8.5.13 Grounding ........................................................................................193
8.5.14 I&C Power Supply ............................................................................193
8.5.15 Seismic Instrumentation ...................................................................194
8.5.16 Future Directions ..............................................................................194
