Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system
- 1. State Key Laboratory on Power Engineering and Multiphase Flow, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049 (China)
- 2. Southwestern Institute of Physics, Chengdu 610041 (China)
Description
Highlights: ► The CH HCSB TBM cooling system has been investigated using RELAP/Mod3.4. ► Two design basis accidents are investigated. ► The natural circulation heat removal capability is discussed. ► The influence of the break location in the ex-vessel LOCA is studied. ► The TBM is designed with sufficient capability heat removal for the accidents. - Abstract: The thermal–hydraulic behavior and safety performance of the Chinese helium-cooled solid breeder (CH HCSB) test blanket module (TBM) with helium cooling system (HCS) has been studied using RELAP5/Mod3.4 code. According to accident analysis specification for TBM, two design basis accidents including loss of off-site power and TBM first wall (FW) ex-vessel coolant pipe break are investigated. The influences of different break locations and plasma termination behaviors are analyzed comprehensively. The results show that natural circulation is established in helium cooling circuit and the TBM can be cooled effectively after loss of off-site power. It is much more critical when the pipe break occurs at the downstream side of the circulator compared with that of upstream side of the circulator. In case of a more serious accident that the ex-vessel break extends to the TBM FW, the results reveal that TBM could be cooled down by natural circulation and radiation. In addition, at the beginning of ex-vessel loss of coolant accident (LOCA), large temperature difference between break and intact TBM FW pipes is found. The accidental results finally show that the integrity of the FW can be guaranteed if the plasma is terminated with a 3 s delay time by fusion power shutdown system (FPSS) in the case of ex-vessel LOCA.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2012.10.001Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2012.10.001;
- PII
- S0920-3796(12)00435-8;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 88
- Journal Issue
- 1
- Journal Page Range
- p. 33-41
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44038874
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; COOLING; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; FERRITIC STEELS; FIRST WALL; HELIUM; LOSS OF COOLANT; MARTENSITIC STEELS; NATURAL CONVECTION; SAFETY ANALYSIS; SHUTDOWN; THERMAL HYDRAULICS; TIME DELAY; TOKAMAK DEVICES
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CONVECTION; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; FLUIDS; GASES; HEAT TRANSFER; HYDRAULICS; IRON ALLOYS; IRON BASE ALLOYS; MASS TRANSFER; MECHANICS; NONMETALS; RARE GASES; REACTOR ACCIDENTS; REACTOR COMPONENTS; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.