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The influence of low-temperature neutron irradiation on physicomechanical properties of new reactor alloys saturated with tritium

Victor V. Sagaradze, Vadim L. Arbuzov, Boris N. Goshchitskii, Vitaly D. Parkhomenko, Vitaly V. Andryushin1998年Fusion Engineering and DesignIF 1.7出版社

AbstractThe influence of tritium (∼0.03 at.%) and low-temperature (77 K) neutron irradiation (fluence 1.5×1018–15×1018 n cm−2) on changes in physical and mechanical properties of stainless steels at 77 K was studied. Strength of the steels was found to be considerably enhanced by increasing the fluence of fast neutrons (power dependence). This increase in strength is explained by the appearance of a large number of clusters formed at low temperatures (hence termed ‘low-temperature clusters’) under cascade-forming irradiation. The deterioration of plasticity of BCC steels and alloys was shown to be an order of magnitude faster than that for reactor materials having an FCC lattice.

日本語訳

トリチウム(約0.03 at.%)および低温(77 K)中性子照射(フルエンス1.5×10¹⁸–15×10¹⁸ n cm⁻²)がステンレス鋼の物理的・機械的性質の変化に及ぼす影響を77 Kで研究した。高速中性子のフルエンスの増加に伴い、鋼の強度が著しく向上することが見出された(出力依存性)。この強度の増加は、カスケード形成照射下で低温において形成される多数のクラスター(以下「低温クラスター」と称する)の出現によって説明される。BCC格子を有する鋼および合金の塑性の劣化は、FCC格子を有する原子炉材料よりも一桁速い速度で進行することが示された。

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TritiumNeutron irradiation
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