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基于空气冷却的熔盐堆非能动余热排出系统优化设计

Optimization Design of Passive Residual Heat Removal System for MSR Based on Air Cooling
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摘要 上海应用物理研究所基于TRISO包覆球形颗粒燃料与液态氟盐提出了基于钍基熔盐固态试验堆(TMSR-SF1)技术方案,其中一个重要的工作是非能动余热排出系统(PRHRS)设计。由于熔盐与水的不兼容特性,以及其高运行温度,采用空气作为最终热阱来设计PRHRS成为必然。为实现系统最简化、体积最小化以及排热与保温兼顾的设计目标,本文从MSR堆芯活性区到外界空气热阱传热过程的模型入手,建立了PRHRS优化设计模型,获得了优化设计方案,并基于改进的RELAP5/MOD4.0程序(针对TMSR-SF1的专门改进程序)开展了PRHRS容量论证评价,经计算分析,PRHRS容量设计合理,可确保反应堆全厂断电(SBO)后排热安全。 Shanghai Institute of Applied Physics proposed a technical solution based on the Thorium-based Molten Salt Solid-state Test Reactor(TMSR-SF1) based on TRISO-coated spherical particulate fuel and liquid fluoride salt. One of the most important works is the design of passive residual heat removal system(PRHRS). Because of the incompatibility between molten salt and water and its high operating temperature, it is necessary to use air as the final heat sink to design PRHRS. In order to achieve the design objectives of system simplification, volume minimization and consideration of heat removal and insulation, starting with the model of heat transfer process from MSR core active zone to external air heat sink, this paper establishes the PRHRS optimization design model, obtains the optimization design scheme, and based on the improved RELAP5/MOD4.0 code(special improved code for TMSR-SF1) carries out the demonstration and evaluation of PRHRS capacity. Calculation and analysis show that the design of PRHRS capacity is reasonable, which can ensure the heat removal safety after the reactor SBO.
作者 张卓华 付瑶 孙微 冉旭 李峰 鲜麟 苏东川 何晓强 Zhang Zhuohua;Fu Yao;Sun Wei;Ran Xu;Li Feng;Xian Lin;Su Dongchuan;He Xiaoqiang(Science and Technology on Reactor System Design Technology,NPIC,Chengdu,610213,China;Shanghai Institute of Applied Physics,CAS,Shanghai,201800,China;Nuclear and Radiation Safety Center,MEE,Beijing,100082,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2022年第1期226-231,共6页 Nuclear Power Engineering
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  • 1杨红义,徐銤,黄祥瑞.中国实验快堆一级概率安全评价初因事件的确定与分组[J].核科学与工程,2004,24(3):211-217. 被引量:7
  • 2马明泽,曹勇,尹志刚,等.核电厂概率安全分析及其应用[M].北京:原子能出版社,2010.
  • 3郑恒,周海京.概率风险评价[M].北京:国防工业出版社.2011:4-16.
  • 4TMSR-SF1堆物理部.10MW固态钍基熔盐实验堆概念设计报告[R].上海:中国科学院上海应用物理研究所,2014.
  • 5Forsberg C, Hu L W, Peterson P F, et al. Fluoride-salt-cooled High-temperature reactors (FHRs) for base-load and peak electricity, grid stabilization, and process heat[R]. America: Massachusetts Institute of Technology, University of California at Berkeley, and University of Wisconsin, 2013.
  • 6梅牡丹,邵世威,左嘉旭,禹志臻,陈堃.熔盐堆丧失厂外电源事故的概率安全评价[J].核技术,2013,36(12):54-61. 被引量:4

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