基于反应截面的连续能谱中子透射率计算方法研究  

Research on Calculation Method of Neutron Transmittance in Continuous Energy Spectrum Based on Reaction Cross Section

作　　者：占羿箭 ZHAN Yijian(Shanghai Construction Group Co.,Ltd.,Shanghai 200080,China;Shanghai Engineering Research Center of Mega Structure High Performance Concrete,Shanghai 200080,China)

机构地区：[1]上海建工集团股份有限公司,上海200080 [2]上海高大结构高性能混凝土工程技术研究中心,上海200080

出　　处：《建筑施工》2024年第11期1733-1737,共5页Building Construction

基　　金：国家自然科学基金资助项目(51878404);上海市科学技术委员会资助项目(23YF1418500,18DZ2282600);上海建工集团股份有限公司重点科研课题(24JCYJ-04)。

摘　　要：在核电站等核设施建设方面,混凝土一直是工程结构的主要材料之一,而钍基熔盐堆等新一代核能系统对辐射屏蔽结构提出了新的挑战。因此,建立了基于中子反应截面及评价核数据库的连续能谱中子透射率理论计算模型,通过单能量透射、多能量透射、连续能谱透射等试验数据对比,验证了计算模型的准确性,以及对中子能量、屏蔽物组分、厚度等主要影响参数的有效性。通过不同材料中子屏蔽性能的横向对比,可为混凝土等复合屏蔽材料的配方设计及屏蔽性能优化提供理论支撑。In the construction of nuclear facilities such as nuclear power plants,concrete has always been one of the main materials for engineering structures.The new generation of nuclear energy systems,such as thorium-based molten salt reactors,poses new challenges to radiation shielding structures.Therefore,a theoretical calculation model of continuous energy spectrum neutron transmittance based on neutron reaction cross section and evaluated nuclear database is established.The accuracy of the calculation model and the validity of main influence parameters such as neutron energy,shielding composition,and thickness are verified by comparing the experimental data of single energy transmission,multi-energy transmission,and continuous energy spectrum transmission.Through the horizontal comparison of neutron shielding performance of different materials,theoretical support can be provided for the formulation design and shielding performance optimization of composite shielding materials such as concrete.

关 键 词：中子辐射 连续能谱 反应截面 核数据库 屏蔽计算 

分 类 号：TU528.35[建筑科学—建筑技术科学]