Accident Analysis of China Helium Cooled Ceramic Breeder Tes
發(fā)布時(shí)間:2021-08-15 23:56
Breeding blanket is a key component in a fusion reactor with main functions of tritium self-sufficiency,electricity production and radiation shielding.Tritium self-sufficiency breeding blanket is a compulsory key component in fusion power deal with these two challenges:producing tritium with equal tritium consumption rate,meanwhile,extraction of high grade heat from blanket at high pressure high temperature coolant.The Helium cooled Ceramic Breeder(HCCB)Test Blanket Module(TBM)is the primary can...
【文章來源】:中國科學(xué)技術(shù)大學(xué)安徽省 211工程院校 985工程院校
【文章頁數(shù)】:91 頁
【學(xué)位級(jí)別】:博士
【文章目錄】:
ABSTRACT
1 INTRODUCTION
1.1 TBM Concepts
1.1.1 Fusion principle (D-T reaction)
1.1.2 The necessity of Tritium Breeder Blanket for fusion reactor
1.1.3 The aim of TBM
1.1.4 Test program strategy
1.1.5 Six TBMs has been decided to be tested on ITER
1.2 Objective of research
1.3 Accident Analysis Method
1.4 Brief description of the performed activity
1.5. Framework and Brief Structure of the thesis
2 Engineering design descriptions of the HCCB Test Blanket System (TBS)
2.1 Overall description of TBS (TBM, Port Cell,AEU, HCS, TES,CPS)
2.2 Detailed description of CN HCCB TBM
2.2.1 Breeding Sub-module
2.3 Helium Cooling System overall arrangements
2.3.1 Overall arrangement of HCS
2.4 Heat Source
3 Modeling of the cooling system with RELAP5MOD4.0
3.1 The scope of RELAP5/MOD4.0
3.2 Modeling theory
3.3 Hydrodynamic modeling and nodalization of TBM
3.4 HCS component hydrodynamic models
3.5 Heat structure of HCCB TBM and component
3.6 Source of heat structure
3.7 Validation of models (steady state analysis)
4 Accident analysis
4.1 In-Vessel LOCA analysis for HCCB TBM
4.2 Ex-Vessel LOCA analysis for HCCB TBM
4.3 Loss of Flow Accident (LOFA) analysis
4.4 Loss of Heat Sink Accident (LHSA) analysis
5 Summary considerations and discussion and conclusion
REFERENCES
ACKNOWLEDGEMENTS
【參考文獻(xiàn)】:
期刊論文
[1]Tumor Molecular Imaging with Nanoparticles[J]. Zhen Cheng,Xuefeng Yan,Xilin Sun,Baozhong Shen,Sanjiv Sam Gambhir. Engineering. 2016(01)
[2]Neutronic Calculation Analysis for CN HCCB TBM-Set[J]. 曹啟祥,趙奉超,趙周,武興華,栗再新,王曉宇,馮開明. Plasma Science and Technology. 2015(07)
[3]Thermal-Hydraulic System Study of the Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) for ITER Using System Code RELAP5[J]. 金雪舟,R.Meyder. Plasma Science & Technology. 2005(02)
本文編號(hào):3345171
【文章來源】:中國科學(xué)技術(shù)大學(xué)安徽省 211工程院校 985工程院校
【文章頁數(shù)】:91 頁
【學(xué)位級(jí)別】:博士
【文章目錄】:
ABSTRACT
1 INTRODUCTION
1.1 TBM Concepts
1.1.1 Fusion principle (D-T reaction)
1.1.2 The necessity of Tritium Breeder Blanket for fusion reactor
1.1.3 The aim of TBM
1.1.4 Test program strategy
1.1.5 Six TBMs has been decided to be tested on ITER
1.2 Objective of research
1.3 Accident Analysis Method
1.4 Brief description of the performed activity
1.5. Framework and Brief Structure of the thesis
2 Engineering design descriptions of the HCCB Test Blanket System (TBS)
2.1 Overall description of TBS (TBM, Port Cell,AEU, HCS, TES,CPS)
2.2 Detailed description of CN HCCB TBM
2.2.1 Breeding Sub-module
2.3 Helium Cooling System overall arrangements
2.3.1 Overall arrangement of HCS
2.4 Heat Source
3 Modeling of the cooling system with RELAP5MOD4.0
3.1 The scope of RELAP5/MOD4.0
3.2 Modeling theory
3.3 Hydrodynamic modeling and nodalization of TBM
3.4 HCS component hydrodynamic models
3.5 Heat structure of HCCB TBM and component
3.6 Source of heat structure
3.7 Validation of models (steady state analysis)
4 Accident analysis
4.1 In-Vessel LOCA analysis for HCCB TBM
4.2 Ex-Vessel LOCA analysis for HCCB TBM
4.3 Loss of Flow Accident (LOFA) analysis
4.4 Loss of Heat Sink Accident (LHSA) analysis
5 Summary considerations and discussion and conclusion
REFERENCES
ACKNOWLEDGEMENTS
【參考文獻(xiàn)】:
期刊論文
[1]Tumor Molecular Imaging with Nanoparticles[J]. Zhen Cheng,Xuefeng Yan,Xilin Sun,Baozhong Shen,Sanjiv Sam Gambhir. Engineering. 2016(01)
[2]Neutronic Calculation Analysis for CN HCCB TBM-Set[J]. 曹啟祥,趙奉超,趙周,武興華,栗再新,王曉宇,馮開明. Plasma Science and Technology. 2015(07)
[3]Thermal-Hydraulic System Study of the Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) for ITER Using System Code RELAP5[J]. 金雪舟,R.Meyder. Plasma Science & Technology. 2005(02)
本文編號(hào):3345171
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