用于短脉冲毫瓦级中子源的硼基热中子吸收剂的研制——如何增强预解耦功能？

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-16 DOI:10.1016/j.jnucmat.2025.155779

Toshifumi Okutomi , Makoto Teshigawara , Sota Sato , Stephen Gallimore , Robert Bewley , Motoki Ooi , Masahide Harada , Shigeru Kuramoto

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引用次数: 0

摘要

去耦器（热中子吸收器）用于脉冲中子源中中子束的脉冲整形，有助于提高中子仪器的分辨率。我们正在为 MW 脉冲中子源开发一种基于硼（B）的去耦合器材料，重点是通过添加其他更高的热中子吸收材料（钆（Gd））来实现预去耦合功能，以抑制因 B 的（n，α）反应而导致的材料脆化。目前的挑战是开发一种 B 和 Gd 均匀分散的材料。在以热等静压（HIP）方法为重点的烧结材料开发过程中，在 HIP 温度从 893 K 以上到熔点以下的条件下，获得了进一步增强预解耦功能的可能性。

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Development of boron-based thermal neutron absorbers for short-pulsed MW-class neutron sources – how can the pre-decoupling function be enhanced?

Decouplers (thermal neutron absorbers) are used for pulse shaping of neutron beams in pulsed neutron sources, contributing to higher resolution of neutron instruments. We are developing a boron (B)-based decoupler material for MW pulsed neutron sources, focusing on the pre-decoupling function to suppress material embrittlement due to the (n, α) reaction of B by adding other higher thermal-neutron absorption material (gadolinium (Gd)). The challenge is to develop a material in which B and Gd are uniformly dispersed. In the development of sintered materials focusing on the hot isostatic pressing (HIP) method, the possibility of further enhancing the pre-decoupling function was obtained under HIP temperature conditions from above 893 K to below the melting point.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.