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聚变-裂变实验混合堆材料研究现状 被引量:1

State of Studies on First-wall Materials for Fusion-Fission Hybrid Reactor
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摘要 本文介绍聚变-裂变实验混合堆第一壁初步概念设计的特点和要求,结构材料和衬瓦材料研究计划;低通量聚变中子、高通量裂变中子,a^-,P^-、C^+等带电粒子和高能电子照射前几种奥氏体不锈钢的微观结构和性能;带电粒子照射后的组织变化及肿胀行为初探;低各向异性度石墨和不同工艺条件下涂层的C^+SiC抗H^+溅射和抗电子束热震行为。500℃,1.8-4.7MeV的a^-粒子束和1.5MeV质子束分别照射至10^(18)a/cm^2和3.7×10^(19)P/cm^2,固溶退火的316SS的肿胀率为8%,20%冷加工316SS和316(Ti)SS的性能优于316LSS。 The paper describes the feature and requirment of the first wall in accordance with the prelimenary conceptual design for experimental hybrid reactor; the structrual and armour materials research program; the prelimenary results of the relationship between microstructure and properties of pre-irradiation; swelling performance induced by irradiation of a^-, P^-, C^+ particle and high energetic electron beams; the technology of low anisotropic graphite and C+SiC coating and their performances of Sputtering by H^+ and thermal shocking by electron beam.8% swelling was produced in 316 LSS irradiated by 1.8—4.7 MeV a^- particle beam and 1.5 MeV proton beam up to fluence of 10^(18) a/cm^2, 3.7×10^(19)p/cm^2 respectively at 500℃ in contrast with 316LSS, the performances of 20% cw316SS and 316(Ti)SS are much better than those of 316LSS.
作者 戴受惠
出处 《核动力工程》 EI CAS CSCD 北大核心 1991年第6期28-35,共8页 Nuclear Power Engineering
关键词 聚变 裂变 实验堆 混合堆 材料 Fusion-fission hybrid reactor, 316LSS Structural C+S1C CVD coating materials, Armour materials, Irradiation.
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