10 MW固态燃料熔盐实验堆安全分析关键技术初步研究  

Preliminary research of safety analysis for 10-MW thorium-based molten salt reactor-solid fuel

作　　者：左嘉旭[1] 高新力[1] 李朝君[1] 宋维[1] 王昆鹏[1] 刘巧凤[1] 靖剑平[1] 张春明[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核技术》2017年第4期55-64,共10页Nuclear Techniques

基　　金：国家自然科学基金(No.11505076);中国科学院战略性先导科技专项(No.XDA02050500)资助~~

摘　　要：钍基熔盐反应堆(Thorium Molten Salt Reactor,TMSR)项目是中国科学院科技先导项目之一。基于10 MW热功率熔盐反应堆-固体燃料(Thorium Molten Salt Reactor-Solid Fuel,TMSR-SF)的设计,对TMSR的关键技术安全分析进行了初步研究。TMSR-SF与现有反应堆之间的差异对核安全审查提出挑战,TMSR-SF审查方法的研究将准备其安全审查的技术和要求。固态燃料熔盐实验堆安全分析关键技术初步研究包含4个方面:堆芯核设计关键安全限值、事故序列及验收准则、源项及其审评方法和验收准则、概率安全评价方法和始发事件。首先对其它类型反应堆的安全审查方法进行了研究,对其关键参数和重要规定做了概述,并借鉴了高温气体冷堆和钠冷却快堆的审评要求和方法;然后使用蒙特卡罗和其他方法、模型来计算TMSR-SF的关键参数。应用逻辑图方法讨论概率风险评价(Probabilistic Risk Assessment,PRA)方法和始发事件清单。在本研究中,计算了核心核设计安全限值,研究和讨论事故列表和分类,讨论了TMSR-SF的PRA框架和始发事件清单,该研究将支持TMSR-SF的安全审查和安全设计。Background： Thorium Molten Salt Reactor （TMSR） project is one of the Strategic Priority Program projects of Chinese Academy of Sciences. Based on the design of 10-MW Thermal Molten Salt Reactor-Solid Fuel （TMSR-SF）, the preliminary study on safety analysis of TMSR about the key technology are done. Purpose： This study aims to prepare the technology and requirements for TMSR-SF safety review, and show the guidance and support to the design. Methods： The study includes four areas： core nuclear design safety limits, accident analysis and acceptance criteria, the source term and the review methods and acceptance criteria, probabilistic risk assessment （PRA） methods and initiating events： The safety review methods of other type reactors have been studied and compared. The key parameters and important regulations have been summary. From review and summary of the high temperature gas coolant reactor and sodium cooled fast reactor, based on the logic diagram methods, the PRA framework of TMSR-SF and initiating events list are discussed. The Monte Carlo and other methods and models are used to calculate the key core nuclear design safety parameters limits of TMSR-SF. The accident list and classification are studied and discussed from computational fluid dynamics （CFD） calculation. Results： The core design of TMSR-SF has sufficient negative reactivity coefficients under operating conditions. The temperature limit could reference high temperature gas cooled reactor and could be set to 1 495 ℃. The shutdown margin should not be less than 0.2 for TMSR-SF. Conclusion： The preliminary accident type and accident event list of design basis have been setup, and the initialing events list has been discussed. The study will support the safety review and safety design of TMSR-SF.

关 键 词：固态燃料熔盐堆 安全分析 堆芯核设计 事故序列 源项 概率风险评价 

分 类 号：TL99[核科学技术—核技术及应用]