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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2014.12
- 수록면
- 109 - 114 (6page)
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초록· 키워드
오류제보하기
After the Fukushima accident in 2011, it was revealed that nuclear power plant has the vulnerability to SBO accident and its extension situation without sufficient cooling of reactor core resulting core meltdown and radioactive material release even after reactor shutdown. Many safety systems had been developed like PAFS, hybrid SIT, and relocation of RPV and IRWST as a part of steps for the Fukushima accident, however, their applications have limitation in the situation that supply of feedwater into reactor is impossible due to high pressure inside reactor pressure vessel. The concept of hybrid heat pipe with control rod is introduced for breaking through the limitation. Hybrid heat pipe with control rod is the passive decay heat removal system in core, which has the abilities of reactor shutdown as control rod as well as decay heat removal as heat pipe. For evaluating the cooling performance hybrid heat pipe, a commercial CFD code, ANSYS-CFX was used. First, for validating CFD results, numerical results and experimental results with same geometry and fluid conditions were compared to a tube type heat pipe resulting in a resonable agreement between them. After that, wall temperature and thermal resistances of 2 design concepts of hybrid heat pipe were analyzed about various heat inputs. For unit length, hybrid heat pipe with a tube type of B4C pellet has a decreasing tendency of thermal resistance, on the other hand, hybrid heat pipe with an annular type B4C pellet has an increasing tendency as heat input increases.
목차
ABSTRACT
1. 서론
2. 하이브리드 히트파이프 소개
3. 형상 및 수치해석 방법
4. 결과 및 고찰
5. 결론
References
참고문헌 (9)
참고문헌 신청
1. [학술지(정기간행물)] - Mochizuki, M / 2011 / Nuclear Reactor Must Need Heat Pipe for Cooling / Frontiers in Heat Pipes 2 : 033001 ~
2. [단행본] - Reav, D. A / 2006 / Heat Pipes / Elsevier : 29 ~ 30
3. [학술대회논문] - Singh, R / 2011 / Heat Pipe Based Emergency Cooling System for Removing Decay Heat from Nuclear Power Reactor and Spent Fuel Pool / Japan Association of Heat Pipe Meeting
4. [학술지(정기간행물)] - Mochizuki, M. / 2014 / Heat Pipe Based Passive Emergency Core Cooling System For Safe Shtudown of Nuclear Power Reactor / Applied Thermal Engineering
5. [학술지(정기간행물)] - Sviridenko, I. I. / 2008 / Heat Exchangers Based on Low Temperature Heat Pipes for Autonomous Emergency WWER Cooldown Systems / Applied Thermal Engineering 28 : 327 ~ 334
2. [단행본] - Reav, D. A / 2006 / Heat Pipes / Elsevier : 29 ~ 30
3. [학술대회논문] - Singh, R / 2011 / Heat Pipe Based Emergency Cooling System for Removing Decay Heat from Nuclear Power Reactor and Spent Fuel Pool / Japan Association of Heat Pipe Meeting
4. [학술지(정기간행물)] - Mochizuki, M. / 2014 / Heat Pipe Based Passive Emergency Core Cooling System For Safe Shtudown of Nuclear Power Reactor / Applied Thermal Engineering
5. [학술지(정기간행물)] - Sviridenko, I. I. / 2008 / Heat Exchangers Based on Low Temperature Heat Pipes for Autonomous Emergency WWER Cooldown Systems / Applied Thermal Engineering 28 : 327 ~ 334
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