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作 者:戴涛 黄洪文[1] 马纪敏[1] 丁文杰[1] 郭海兵[1] 王少华[1] Dai Tao;Huang Hongwen;Ma Jimin;Ding Wenjie;Guo Haibing;Wang Shaohua(Institute of Nuclear Physics and Chemistry,CAEP,Mianyang 621900,China)
机构地区:[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900
出 处:《强激光与粒子束》2019年第3期74-80,共7页High Power Laser and Particle Beams
基 金:国家磁约束核聚变能发展研究专项(2015GB108003)
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。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.
关 键 词:CFETR 高增益包层 全包层模型 RELAP5 失流事故
分 类 号:TL36[核科学技术—核技术及应用]
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