Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
10293415 | Nuclear Engineering and Design | 2005 | 9 Pages |
Abstract
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.
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Authors
Jun Hwan Kim, Myoung Ho Lee, Byoung Kwon Choi, Yong Hwan Jeong,