MICROSTRUCTURAL DESIGN OF PCA AUSTENITIC STAINLESS-STEEL FOR IMPROVED RESISTANCE TO HELIUM EMBRITTLEMENT UNDER HFIR IRRADIATION

被引：20

作者：

MAZIASZ, PJ

BRASKI, DN

机构：

[1] Oak Ridge Natl Lab, Oak Ridge, TN,, USA, Oak Ridge Natl Lab, Oak Ridge, TN, USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1984年 / 122卷 / 1-3期

关键词：

HELIUM - IRON AND STEEL METALLOGRAPHY - Microstructures - NUCLEAR REACTORS; FUSION - Materials - STEEL - Embrittlement - TITANIUM CARBIDE;

D O I：

10.1016/0022-3115(84)90615-9

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Several variants of Prime Candidate Alloy (PCA) with different preirradiation thermal-mechanical treatments were irradiated in HFIR and were evaluated for embrittlement resistance via disk-bend tensile testing. Comparison tests were made on two heats of 20%-cold-worked type 316 stainless steel. None of the alloys were brittle after irradiation at 300 to 400 degree C to approximately 44 dpa and helium levels of 3000 to approximately 3600 at. ppm. However, all were quite brittle after similar exposure at 600 degree C. Embrittlement varied with alloy and pretreatment for irradiation to 44 dpa at 500 degree C and to 22 dpa at 600 degree C. Better relative embrittlement resistance among PCA variants was found in alloys which contained prior grain boundary MC carbide particles that remained stable under irradiation.

引用

页码：305 / 310

页数：6

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