Nuclear Engineering and Technology
- Volume 18 Issue 3
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- Pages.218-227
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- 1986
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
Deformation Characteristics of Zircaloy-4 Fuel Cladding due to Oxidation in Environment of High Temperature and Steam
고온, 수증기 속에서 산화된 질칼로이-4 핵연료 피복관의 변형 특성에 관한 연구
- Jung, Sung-Hoon (Korea Advanced Energy Research Institute) ;
- Suh, Kyung-Soo (Korea Advanced Energy Research Institute) ;
- Kim, In-Sup (Korea Advanced Institute of Science and Technology)
- Published : 1986.09.01
Abstract
Studies were conducted to determine the extent of oxidation and same of the mechanical property changes of Zircaloy-4 fuel cladding after it was exposed to hot steam environment. The purpose of these tests was to provide some informations on the embrittlement behavior of CANDU type fuel cladding, which could be experienced under the loss-of-coolant accident conditions. The Zircaloy fuel cladding tubes were exposed in a steam environment at the temperature of 90
가상적인 냉각제 상실 사고시의 조건하에 일어날 수 있는 취약화 현상에 대한 자료를 얻기 위하여 고온의 수중기 분위기에서 Zircaloy-4 핵연료피복관의 산화거동과 기계적성질 변화에 대한 연구를 수행하였다. 시편은 캔두형핵연료 피복관으로 사용되는 질칼로이 튜브를 사용하였으며 냉각제 상실 사고시 야기될 수 있는 수중기 분위기속 90
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