基于确定论的ADANES堆芯稳态中子学分析及瞬态事故模拟研究  

The steady-state neutronic analysis and transient simulation of ADANES reactor design based on deterministic method

作　　者：杜夏楠 王永平[1] 郑友琦[1] 曹良志[1] 张延师 闫雪松[2,3] 杨磊 DU Xianan;WANG Yongping;ZHENG Youqi;CAO Liangzhi;ZHANG Yanshi;YAN Xuesong;YANG Lei(School of Nuclear Science and Technology,Xi'an Jiaotong Univeristy,Xi'an 710049,China;Institute of Morden Physics,Chinese Academy of Sciences,Lanzhou 730030,China;Guangdong Provincial Laboratory of Advanced Energy Science and Technology,Huizhou 516000,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国科学院近代物理研究所,兰州730030 [3]先进能源科学与技术广东省实验室,惠州516000

出　　处：《核技术》2022年第10期77-84,共8页Nuclear Techniques

基　　金：国家自然科学基金(No.12505160);中国科学院西部青年学者项目、甘肃省自然科学基金(No.20JR10RA065)资助。

摘　　要：目前,国家重大科技基础设施“加速器驱动嬗变研究装置”(China Initiative Accelerator Driven System,CiADS)正在建设的关键阶段,对其方案展开详细计算分析可以为核能的可持续发展和国家能源安全战略提供强有力的技术支持。利用先进反应堆物理计算系统(Nuclear Engineering Computational Physics Laboratory,System for Advanced Reactor Analysis at Xi'an Jiaotong University,NECP-SARAX),通过比较不同燃料/冷却剂选型、结构尺寸下的堆芯寿期、能谱特性以及反应性反馈系数等参数,对加速器驱动先进核能系统(Accelerators Drive Advanced Nuclear Energy Systems,ADANES)展开了堆芯中子学特性分析,并对堆芯的瞬态特性进行了初步分析,瞬态事故包括无保护反应性引入事故以及无保护失流事故。数值计算结果表明:ADANES堆芯在满功率运行条件下可以实现大于10 a的运行寿期,同时具备负的反馈反应性系数,通过瞬态分析表明该堆芯具备了在典型事故下的固有安全特性。[Background]At present,in the key stage of the construction of China Initiative Accelerator Driven System,various research institutes have also put forward corresponding core schemes for different purposes,including the accelerators drive advanced nuclear energy system(ADANES)proposed by Institute of Modern Physics,Chinese Academy of Sciences.Detailed calculation and analysis of its scheme can provide strong technical support for the sustainable development of nuclear energy and the national energy security strategy.[Purpose]This study aims to analyze the steady-state neutronics characteristics of ADANES reactor with emphasis on the preliminary typical transient analysis under the typical accident conditions of fast reactor.[Methods]The NECPSARAX(Nuclear Engineering Computational Physics Laboratory,System for Advanced Reactor Analysis at Xi'an Jiaotong University)code system,which was based on deterministic neutron transport theory,was applied to perform the detailed analysis.The main design parameters,including core length,neutron spectrum and reactivity feedback coefficients,were calculated under various fuel types,coolant types,and reactor geometry parameters.In addition,the primary transient characteristics were simulated,including unprotected transient over power and unprotected loss of flow transient.The changes of reactor power and the maximum fuel/coolant temperature were obtained and analyzed.[Results&Conclusions]The steady-state calculation results show that ADANES could achieve 10 effective full power year for each selected case.The reactivity feedback coefficients reach−5.4×10^(−5) K^(−1) in total so that the core has inherent safety under typical accident condition conditions during the simulated transient.

关 键 词：ADANES堆芯 NECP-SARAX 中子学分析 确定论 

分 类 号：TL942[核科学技术—辐射防护及环境保护]