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郭圣淼, 张璐, 李金阳, 姜韦, 戴勇, 顾龙. 加速器驱动嬗变研究装置顶盖漏束的热中子等效注量率评估[J]. 原子核物理评论, 2023, 40(3): 478-484. DOI: 10.11804/NuclPhysRev.40.2022093
引用本文: 郭圣淼, 张璐, 李金阳, 姜韦, 戴勇, 顾龙. 加速器驱动嬗变研究装置顶盖漏束的热中子等效注量率评估[J]. 原子核物理评论, 2023, 40(3): 478-484. DOI: 10.11804/NuclPhysRev.40.2022093
Shengmiao GUO, Lu ZHANG, Jinyang LI, Wei JIANG, Yong DAI, Long GU. Estimation of Equivalent Thermal Neutron Fluence Rate in the Leakage Beam of China Initiative Accelerator Driven System[J]. Nuclear Physics Review, 2023, 40(3): 478-484. DOI: 10.11804/NuclPhysRev.40.2022093
Citation: Shengmiao GUO, Lu ZHANG, Jinyang LI, Wei JIANG, Yong DAI, Long GU. Estimation of Equivalent Thermal Neutron Fluence Rate in the Leakage Beam of China Initiative Accelerator Driven System[J]. Nuclear Physics Review, 2023, 40(3): 478-484. DOI: 10.11804/NuclPhysRev.40.2022093

加速器驱动嬗变研究装置顶盖漏束的热中子等效注量率评估

Estimation of Equivalent Thermal Neutron Fluence Rate in the Leakage Beam of China Initiative Accelerator Driven System

  • 摘要: 加速器驱动次临界系统(ADS)利用质子轰击散裂靶产生的中子驱动次临界堆稳定、持续运行,有望实现长寿命次锕系核素嬗变,并进行洁净能源生产。在加速器与反应堆耦合过程中,束流管道贯穿反应堆的顶盖,堆芯中的散裂中子和裂变中子会通过束流管道大量泄漏,需开展相关屏蔽设计,以减小顶盖外的设备活化,进而减小停堆后堆顶设备维修人员所受辐射剂量。传统热堆的堆外辐射屏蔽设计中,常将热中子注量率限制在105 n/(cm2 · s),以减小设备活化,提高可维护性。对于加速器驱动次临界系统而言,顶盖漏束具有快中子谱、注量率高等特点,需以热中子等效注量率为限值,开展相关屏蔽设计分析。本工作以加速器驱动嬗变研究装置(CiADS)为例,分析了顶盖漏束后产生的活化核素的预期辐射释能,并通过与热中子的预期辐射释能进行等效,得到了束管漏束屏蔽设计所需的漏束中子注量率,并对其适用性进行了评估。研究表明,平均注量率为9.292×105 n/(cm2 · s)的漏束中子在预期辐射释能上等效于注量率为105 n/(cm2 · s)的热中子,在相关辐射屏蔽设计中,可保守取顶盖外部中子注量率限值为8×105 n/(cm2 · s)。本工作提出了一种ADS堆外活化屏蔽设计时的热中子等效注量率的选取方法,可为快谱下的屏蔽分析提供参考。本文获得的热中子等效注量率可用于CiADS顶盖屏蔽的工程设计与分析。

     

    Abstract: The Accelerator Driven subcritical System(ADS) is driven by spallation neutrons, which is generated during the proton bombarding the spallation target, to make the subcritical reactor operate stably and continuously. It has high potential to transmute the long-lived minor-actinides and produce cleaner nuclear energy. During the coupling process of the accelerator and reactor, the beam pipeline penetrates through the top cover of the reactor, and spallation neutrons and fission neutrons in the core tend to leak through the pipeline in large quantities. In order to reduce the equipment activation and reduce the personnel radiation dose received during the maintenance, it’s necessary to carry out relevant shielding design work. In the radiation shielding design of thermal spectrum reactor, the thermal neutron fluence rate is usually limited to 105 n/(cm2 · s) to reduce equipment activation and ensure maintainability. For the Accelerator Driven subcritical System, the leakage neutrons from the top cover are fast neutrons with high fluence rate. It is necessary to carry out the shielding design analysis according to an appropriate equivalent thermal neutron fluence rate. This work takes the China initiative Accelerator Driven System(CiADS) as a reference to analyze the expected radiant energy release of activated nuclides generated by the leakage neutrons, and a leakage neutron equivalent fluence rate is obtained. The applicability for this thermal neutron equivalent fluence rate is evaluated. Studies have shown that leakage neutrons with an average fluence rate of 9.292×105 n/(cm2 · s) are equivalent to thermal neutrons with a fluence rate of 105 n/(cm2 · s) in the expected radiant energy release. In the radiation shielding design, the neutron fluence rate limit outside the top cover can be conservatively taken as 8×105 n/(cm2 · s). This research work proposes a method for selecting the equivalent neutron fluence rate in the design of the ADS external activation shield, which can be used in the fast spectrum neutron shielding analysis. The thermal neutron equivalent fluence rate obtained in this paper can provide reference for the shielding design and analysis of CiADS.

     

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