کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
10293415 511841 2005 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench
چکیده انگلیسی
Simulated loss of coolant accident (LOCA) tests on Zircaloy-4 cladding were carried out to evaluate the thermal shock property during the injection of emergency core coolant. A Zircaloy-4 specimen was oxidized in a steam environment between 1000 and 1250 °C followed by a flooding of the cooling water. After the test, the ductility of the thermally embrittled specimen was measured by a ring-compression test and a microstructural analysis was carried out. The results showed that the threshold equivalent cladding reacted (ECR) value to cause a failure was higher than the conventional 17% criterion calculated by the Baker-Just equation. A residual metal thickness under 0.3 mm as well as a ring-compression ductility below 0.2 mm for a fracture is effective to assess the thermal shock embrittlement of Zircaloy-4 in an axially unrestrained, or even in a restrained condition.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 235, Issue 1, January 2005, Pages 67-75
نویسندگان
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