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E-raamat: High Temperature Gas-cooled Reactors

Edited by (Graduate Faculty of Interdisciplinary Research, Research Faculty of Engineering, Department of Mechanical Engineering,
University of Yamanashi, Yamanashi, Japan), Edited by (Department of Hydrogen and Heat Application Research and Development,)
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High Temperature Gas-cooled ReactorsSuurem pilt
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High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant.The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection.This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations.
List of contributors
xi
About the authors xv
Preface of JSME Series in Thermal and Nuclear Power Generation xxix
Preface to Volume 5: High-Temperature Gas-Cooled Reactors xxxiii
1 Overview of high temperature gas-cooled reactor
1(16)
Jin Iwatsuki
Kazuhiko Kunitomi
Hideaki Mineo
Tetsuo Nishihara
Nariaki Sakaba
Masayuki Shinozaki
Yukio Tachibana
Xing Yan
1.1 Features of high temperature gas-cooled reactor
1(6)
1.1.1 Structure and materials
1(2)
1.1.2 Heat application
3(1)
1.1.3 Safety
4(2)
1.1.4 Adaptability to environment
6(1)
1.2 History of research and development in world
7(4)
1.3 History of research and development in Japan
11(6)
References
15(2)
2 Design of High Temperature Engineering Test Reactor (HTTR)
17(162)
Yusuke Fujiwara
Minora Goto
Kazuhiko ligaki
Tatsuo Iyoku
Hai Quan Ho
Taiki Kawamoto
Makoto Kondo
Kazuhiko Kunitomi
Keisuke Morita
Satoru Nagasumi
Shigeaki Nakagawa
Tetsuo Nishihara
Naoki Nojiri
Masato Ono
Akio Saikusa
Nariaki Sakaba
Taiju Shibata
Yosuke Shimazaki
Atsushi Shimizu
Masayuki Shinozaki
Junya Sumita
Yukio Tachibana
Shoji Takada
Daisuke Tochio
Takahiro Uesaka
Shohei Ueta
2.1 Overview of HTTR design features
18(14)
2.1.1 Introduction
18(1)
2.1.2 History and future plan of HTTR project
19(4)
2.1.3 Major design features of HTTR
23(6)
2.1.4 R&D programs for HTTR
29(3)
2.2 Nuclear design
32(9)
2.2.1 Introduction
32(1)
2.2.2 Design requirement
32(2)
2.2.3 Analytical method
34(1)
2.2.4 Evaluation of nuclear characteristics
35(6)
2.3 Core thermal-hydraulics
41(7)
2.3.1 Introduction
41(1)
2.3.2 Design requirements
41(1)
2.3.3 Design details
42(2)
2.3.4 Evaluation results of design
44(1)
2.3.5 Reevaluation of maximum fuel temperature with operational data
45(3)
2.4 Graphite components
48(10)
2.4.1 Introduction
48(1)
2.4.2 In-core graphite and carbon structure in high temperature engineering test reactor
48(2)
2.4.3 Concepts of graphite design criteria
50(8)
2.4.4 Quality control
58(1)
2.5 Metallic components
58(13)
2.5.1 Introduction
58(1)
2.5.2 Development of Hastelloy XR
59(2)
2.5.3 Identification of failure modes
61(1)
2.5.4 Developments of design limits and rules
61(10)
2.6 Core components and reactor internals
71(18)
2.6.1 Introduction
71(1)
2.6.2 Fuel
71(3)
2.6.3 Hexagonal graphite blocks
74(5)
2.6.4 Core support structures
79(6)
2.6.5 Core support metallic structures
85(2)
2.6.6 Shielding blocks
87(2)
2.7 Seismic design
89(13)
2.7.1 Introduction
89(1)
2.7.2 Seismic design
90(4)
2.7.3 Geological composition and seismometry
94(1)
2.7.4 Structure of core components
94(5)
2.7.5 Development of evaluation method
99(1)
2.7.6 Structural integrity of graphite components
100(2)
2.8 Cooling system
102(11)
2.8.1 Introduction
102(1)
2.8.2 Primary cooling system
103(7)
2.8.3 Secondary helium cooling system
110(2)
2.8.4 Pressurized water-cooling system
112(1)
2.8.5 Residual heat removal system
113(1)
2.9 Reactivity control system
113(14)
2.9.1 Introduction
113(1)
2.9.2 Control rod system
114(12)
2.9.3 Reserve shutdown system
126(1)
2.10 Instrumentation and control system
127(11)
2.10.1 Introduction
127(1)
2.10.2 Instrumentation system
128(3)
2.10.3 Process instrumentation
131(1)
2.10.4 Control system
132(2)
2.10.5 Safety protection system
134(1)
2.10.6 Performance test results
135(3)
2.11 Containment structures
138(13)
2.11.1 Introduction
138(1)
2.11.2 Reactor containment vessel
138(8)
2.11.3 Service area
146(1)
2.11.4 Emergency air purification system
147(4)
2.12 Other systems
151(7)
2.12.1 Introduction
151(1)
2.12.2 Auxiliary helium systems
151(4)
2.12.3 Fuel system
155(3)
2.13 Safety design
158(21)
2.13.1 Introduction
158(1)
2.13.2 Basic safety design philosophy
158(2)
2.13.3 Safety classification
160(4)
2.13.4 Fundamental safety functions unique to HTTR
164(1)
2.13.5 Acceptance criteria
165(2)
2.13.6 Selection of events
167(2)
2.13.7 Safety evaluation technologies
169(4)
2.13.8 New safety criteria
173(1)
References
173(6)
3 R&D on components
179(78)
Jun Aihara
Minoru Goto
Yoshiyuki Inagaki
Tatsuo Iyoku
Kazuhiko Kunitomi
Tetsuo Nishihara
Nariaki Sakaba
Taiju Shibata
Junya Sumita
Yukio Tachibana
Shoji Takada
Tetsuaki Takeda
Shohei Ueta
3.1 Fuel
180(11)
3.1.1 Introduction
180(1)
3.1.2 Related research and development for fuel design
181(4)
3.1.3 Fabrication technologies for HTTR fuel
185(4)
3.1.4 Performance of HTTR fuel during long-term high temperature operation
189(2)
3.2 Core components and reactor internals
191(12)
3.2.1 Introduction
191(1)
3.2.2 Tests on core components
191(5)
3.2.3 Tests on reactor internals
196(7)
3.3 Passive cooling system
203(14)
3.3.1 Introduction
203(2)
3.3.2 Experiment
205(3)
3.3.3 Numerical method
208(5)
3.3.4 Evaluation of hot spot by natural convection
213(2)
3.3.5 Evaluation of local hot spot around standpipes
215(2)
3.4 Intermediate heat exchanger
217(13)
3.4.1 Introduction
217(1)
3.4.2 Creep collapse of the tube against external pressure
218(2)
3.4.3 Creep fatigue of tube against thermal stress
220(3)
3.4.4 Seismic behavior of tube bundle
223(3)
3.4.5 Thermal hydraulic behavior of tube bundle
226(2)
3.4.6 In-service inspection technology of tube
228(2)
3.5 Basic feature of air ingress during primary pipe rupture accident
230(27)
3.5.1 Introduction
230(3)
3.5.2 Basic feature of air ingress phenomena in a reverse U-shaped channel
233(10)
3.5.3 Basic feature of air ingress phenomena in a simulated reactor apparatus
243(10)
References
253(4)
4 Operation of HTTR
257(56)
Yuji Fukaya
Minoru Goto
Hiroyuki Inoi
Etsuo Ishitsuka
Tatsuo lyoku
Kazuhiko Kunitomi
Shigeaki Nakagawa
Tetsuo Nishihara
Hai Quan Ho
Akio Saikusa
Nariaki Sakaba
Hiroaki Sawahata
Taiju Shibata
Masayuki Shinozaki
Yukio Tachibana
Shoji Takada
Kuniyoshi Takamatsu
Daisuke Tochio
4.1 Unexpected incidents under construction and operation
258(11)
4.1.1 Introduction
258(1)
4.1.2 Temperature rise of primary upper shielding
258(6)
4.1.3 Temperature rise of core support plate
264(5)
4.2 Characteristic test of initial core
269(9)
4.2.1 Introduction
269(1)
4.2.2 General description
270(1)
4.2.3 Critical approach
271(1)
4.2.4 Excess reactivity and shutdown margin
272(2)
4.2.5 Control rod characteristics
274(1)
4.2.6 Reactivity coefficient
275(1)
4.2.7 Neutron flux and power distribution
276(2)
4.3 Performance test
278(9)
4.3.1 Introduction
278(1)
4.3.2 Major test items
279(1)
4.3.3 Heat balance of reactor cooling system
280(1)
4.3.4 Heat exchanger performance
281(1)
4.3.5 Reactor control system performance
282(2)
4.3.6 Residual heat removal performance at manual reactor scram
284(1)
4.3.7 Thermal expansion performance of high temperature components
285(1)
4.3.8 Fuel and fission product behavior
286(1)
4.4 High temperature operation
287(11)
4.4.1 Introduction
287(1)
4.4.2 Main test results of long-term high temperature operation
288(4)
4.4.3 Validation using high temperature engineering test reactor burnup data
292(6)
4.5 Safety demonstration test
298(15)
4.5.1 Introduction
298(2)
4.5.2 High temperature engineering test reactor control system
300(2)
4.5.3 Safety demonstration test plan
302(1)
4.5.4 Analysis code and model
303(1)
4.5.5 Reactivity insertion test
304(3)
4.5.6 Coolant flow reduction test--gas circulators trip test
307(2)
4.5.7 Loss of forced cooling test
309(1)
References
310(3)
5 R&D on commercial high temperature gas-cooled reactor
313(138)
Jun Aihara
Takeshi Aoki
Yuji Fukaya
Minoru Goto
Yoshiyuki Imai
Yoshitomo Inaba
Yoshiyuki Inagaki
Tatsuo Iyoku
Yu Kamiji
Seiji Kasahara
Shinji Kubo
Kazuhiko Kunitomi
Naoki Mizuta
Odtsetseg Myagmarjav
Tetsuo Nishihara
Hiroki Noguchi
Hirofumi Ohashi
Nariaki Sakaba
Koei Sasaki
Hiroyuki Sato
Taiju Shibata
Junya Sumita
Yukio Tachibana
Shoji Takada
Tetsuaki Takeda
Hiroaki Takegami
Nobuyuki Tanaka
Shohei Ueta
Xing Yan
5.1 System design for power generation
314(15)
5.1.1 Introduction
314(1)
5.1.2 HTR50S: HTGR steam cycle power plant
315(4)
5.1.3 GTHTR300: HTGR gas turbine power plant
319(10)
5.2 System design for cogeneration
329(12)
5.2.1 Introduction
329(1)
5.2.2 Hydrogen cogeneration
330(6)
5.2.3 Seawater desalination
336(2)
5.2.4 HTGR renewable hybrid system
338(3)
5.3 System design for steelmaking
341(8)
5.3.1 Introduction
341(1)
5.3.2 Flow diagram of steelmaking systems
341(5)
5.3.3 CO2 emission
346(1)
5.3.4 Steelmaking cost
346(3)
5.4 Safety design for connection of heat application system and high temperature gas-cooled reactor
349(10)
5.4.1 Introduction
349(1)
5.4.2 Roadmap for safety standard establishment
349(2)
5.4.3 Safety requirements
351(2)
5.4.4 Basic concept of safety guides
353(2)
5.4.5 HTTR cogeneration demonstration
355(4)
5.5 Gas turbine technology for power generation
359(11)
5.5.1 Introduction
359(1)
5.5.2 Helium gas compressor
360(6)
5.5.3 Magnetic bearing
366(4)
5.6 Iodine--sulfur process technology for hydrogen production
370(17)
5.6.1 Introduction
370(1)
5.6.2 Bench-scale test
371(1)
5.6.3 Elemental technologies
371(1)
5.6.4 Industrial material component test
372(5)
5.6.5 Hydrogen production test
377(2)
5.6.6 Improvement of hydrogen production efficiency
379(4)
5.6.7 Component materials
383(4)
5.7 System integration technology for connection of heat application system and high temperature gas-cooled reactor
387(12)
5.7.1 Introduction
387(2)
5.7.2 Control technology
389(4)
5.7.3 Tritium permeation
393(3)
5.7.4 Explosion of combustible gas
396(1)
5.7.5 High temperature isolation valves
397(2)
5.8 Prevention technology for air ingress during a primary pipe rupture accident
399(22)
5.8.1 Introduction
399(1)
5.8.2 Prevention technology of air ingress in a reverse U-shaped channel
399(16)
5.8.3 Basic feature of air ingress phenomena during a horizontal pipe break accident
415(6)
5.9 Advanced fuel technology for high bumup
421(8)
5.9.1 Introduction
421(1)
5.9.2 Design of high burnup fuel
422(2)
5.9.3 Upgrade technologies for high bumup
424(5)
5.9.4 Future study plan
429(1)
5.10 Advanced fuel for plutonium burner
429(8)
5.10.1 Introduction
429(1)
5.10.2 Fuel fabrication process of Clean Burn
430(2)
5.10.3 Core design
432(4)
5.10.4 Future study plan
436(1)
5.11 Advanced fuel technology for reduction of high-level radioactive waste
437(14)
5.11.1 Introduction
437(1)
5.11.2 Calculation for repository design
437(4)
5.11.3 Evaluation of waste package
441(4)
References
445(6)
Index 451
Tetsuaki Takeda has been a professor of Graduate Faculty of Interdisciplinary Research, Research Faculty of Engineering, Department of Mechanical Engineering, University of Yamanashi since 2008. He was graduated from Kobe University, majored in nuclear engineering in 1982, and received his doctoral degree at The University of Tokyo in 1997. He stayed at University of California Los Angeles (UCLA) as a visiting researcher from 1993 to 1994. He has transferred his field of academic goal from Japan Atomic Energy Agency to University of Yamanashi in 2008. His research field is the thermo-hydraulics related in not only nuclear energy but also renewable energy. During his service in JAEA, he performed the experiments and analyses of the safety studies regarding the VHTR systems and the nuclear hydrogen production systems developments. Afterward, he has also performed experiment and analysis regarding a ground source heat pump system, solar thermal collector system, heat utilization system using thermoelectric devices, and so on. He served Chairman of Power and Energy Systems Division of Japan Society of Mechanical Engineers (JSME). Yoshiyuki Inagaki is Researcher of Department of Hydrogen and Heat Application Research and Development, HTGR Research and Development Center, Oarai Research and Development Institute, Sector of Fast Reactor and Advanced Reactor Research and Development in JAEA. He received his PhD degree from Kyushu University in 1996. He started his research career at JAERI in 1981 for the HTGR technology such as reactor internals and high temperature components. He then worked in Juelich Research Center in Germany from 1994 to 1995 for a hydrogen production process. He also researched HTGR heat application systems such as hydrogen production and nuclear steelmaking systems and the system integration technology for safe connection between a reactor and a hydrogen production system.
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