کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1569817 1514270 2006 13 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
The development of a stress analysis code for nuclear graphite components in gas-cooled reactors
کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
The development of a stress analysis code for nuclear graphite components in gas-cooled reactors
چکیده انگلیسی

Most of the UK nuclear power reactors are gas-cooled and graphite moderated. As well as acting as a moderator the graphite also acts as a structural component providing channels for the coolant gas and control rods. For this reason the structural integrity assessments of nuclear graphite components is an essential element of reactor design. In order to perform graphite component stress analysis, the definition of the constitutive equation relating stress and strain for irradiated graphite is required. Apart from the usual elastic and thermal strains, irradiated graphite components are subject to additional strains due to fast neutron irradiation and radiolytic oxidation. In this paper a material model for nuclear graphite is presented along with an example of a stress analysis of a nuclear graphite moderator brick subject to both fast neutron irradiation and radiolytic oxidation.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 350, Issue 3, 1 May 2006, Pages 208–220
نویسندگان
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