Thermal safety analysis on high tritium breeding blanket for loss of flow accident
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摘要: 利用系统分析程序RELAP5/Mod 3.4对基于中国聚变工程实验堆(CFETR)的高增益包层聚变堆进行了全堆尺度的安全分析。针对包层结构复杂、部件众多的特点,提出了对包层两套冷却系统的复杂流动和传热结构的等效建模方法,并建立了两套冷却系统间的传热模型。在此基础上完成全包层模型,对稳态运行工况进行了计算验证,并选取燃料区全部失流事故进行安全分析。计算结果表明:在事故过程中,第一壁-产氚区冷却系统能够带走燃料区的部分衰变热,高增益包层的各项热工参数均未超过限值。这表明包层能够有效地抵御此类事故,具有良好的热工安全特性。Abstract: Safety analysis in reactor scale on high tritium breeding blanket based on China Fusion Engineering Test Reactor (CFETR) was carried out with system analysis code RELAP5/Mod 3.4. In view of the complexity of blanket internal structure, an equivalent modeling method for complex flow and heat transfer structures of two cooling systems was proposed, and a heat transfer model between two cooling systems was established. The intact reactor model was completed on the basis, and verified the parameters on the steady-state operation. Then the analysis of loss of flow accident LOFA in fuel zone was performed. The computational results indicate that the sectional decay heat generated by the zone can be taken away by the FW-Tritium breeding zone cooling system, and every thermal-hydraulic parameter is under the limit. The blanket can resist this accident efficiently, and possess excellent thermal safety characteristics. The study also provides a reference for the safety analysis of other blankets in reactor scale.
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Key words:
- CFETR /
- high tritium breeding blanket /
- intact reactor model /
- RELAP5 /
- LOFA
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表 1 RELAP5与主要热工水力参数设计值对比
Table 1. Main thermal-hydraulic parameters comparison of RELAP5 results and design values
parameter coolant temperatures at the inlet/outlet of the FW-tritium breeding zone cooling system/℃ coolant temperatures at the inlet/outlet of the fuel zone cooling system/℃ coolant mass flow of the FW-tritium breeding zone cooling system /(kg·s-1) RELAP5 279.65/319.41 279.84/319.26 959.68 designed value 280/320 280/320 961.71 parameter coolant mass flow of the fuel zone cooling system/(kg·s-1) pressure of the FW-tritium breeding zone cooling system/MPa pressure of the fuel zone cooling system/MPa RELAP5 3 302.50 15.50 15.50 Designed value 3 302.94 15.50 15.50 表 2 改变热构件后主要热工水力参数
Table 2. Main thermal-hydraulic parameters after heat structures changed
parameter coolant temperatures at the inlet/outlet of the FW-tritium breeding zone cooling system/℃ coolant temperatures at the inlet/outlet of the fuel zone cooling system/℃ coolant mass flow of the FW-tritium breeding zone cooling system /(kg·s-1) RELAP5 280.35/326.62 279.35/316.85 959.68 parameters coolant mass flow of the fuel zone cooling system/(kg·s-1) pressure of the FW-tritium breeding zone cooling system/MPa pressure of the fuel zone cooling system/MPa RELAP5 3 302.50 15.72 15.47 表 3 全部主泵失电事件序列
Table 3. Sequence of all main pumps lose efficacy
event time/s main pumps loss of off-site power supply 100.00 plasma shutdown 100.77 Minimum departure from nucleate boiling ratio(MDNBR) reaches the minimum value 102.00 system pressure reaches the maximum value 138.00 coolant temperature reaches the peak value 142.00 -
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