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The operation method of nuclear power plants is currently changing to high burn-up and long period that can enhance economics and efficiency of the plant. Since nuclear plant operation environment has been becoming severe, the amount of absorbed hydrogen also has increased. Absorbed hydrogen can be fatal securing safety of nuclear fuel cladding in case of Loss of Coolant Accidents(LOCA). In order to examine the impact of hydride on high-temperature oxidation, high-temperature oxidation experiment was performed on normal Zry-4 cladding and on Zry-4 cladding where hydrogen is charged in air pressure·steam atmosphere under the 950℃ and 1000℃. According to the results, while oxidation acceleration due to charged hydrogen was not observed prior to breakaway oxidation creation, oxidation began to accelerate in cladding where hydrogens charged as soon as the breakaway oxidation started. If so much hydrogen are charged in the cladding, equiaxial monoclinic phase to unstable of stress is formed and it is presumed that oxidation is accelerated because nearby stress caused a crack in equiaxial phase, and that makes corrosion resistance decline sharply.
목차
Abstract
1. 서론
2. 실험방법
3. 결과 및 고찰
4. 결론
References
참고문헌 (12)
참고문헌 신청
[학술지(정기간행물)] - D. D. Lanning / 2005 / FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties / NUREG/CR-6534 4 : 53 ~ 57
[학술지(정기간행물)] - R. E. Pawel / 1979 / The Oxidation of Zry-4 at 900 and 1100℃ in High Pressure Steam / J. Nucl. Mater 82 : 129 ~ 139
[기타자료] - Nuclear Regulatory Commission / 2014 / Performance-Based Emergency Core Cooling Systems Cladding Acceptance Criteria :Proposed Rule, 10 CFR Parts 50 and 52 / Federal Register. Vol.79 : 34 ~ 46
[기타자료] - ASTM / 1991 / Standard Test Method for Corrosion Testing of Products of Zirconium, Hafnium, and Their Alloys in 633 K or in Steam at 673 K [Metric] / Annual Books of ASTM Standard section, ASTM, 3, 49
[보고서] - Y. S. Kim / 1999 / A Manual for Characterization Tests for Zr-2.5Nb Pressure Tubes
[학술지(정기간행물)] - R. E. Pawel / 1979 / The Oxidation of Zry-4 at 900 and 1100℃ in High Pressure Steam / J. Nucl. Mater 82 : 129 ~ 139
[기타자료] - Nuclear Regulatory Commission / 2014 / Performance-Based Emergency Core Cooling Systems Cladding Acceptance Criteria :Proposed Rule, 10 CFR Parts 50 and 52 / Federal Register. Vol.79 : 34 ~ 46
[기타자료] - ASTM / 1991 / Standard Test Method for Corrosion Testing of Products of Zirconium, Hafnium, and Their Alloys in 633 K or in Steam at 673 K [Metric] / Annual Books of ASTM Standard section, ASTM, 3, 49
[보고서] - Y. S. Kim / 1999 / A Manual for Characterization Tests for Zr-2.5Nb Pressure Tubes
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