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Thermal-hydraulics Analysis on Design of Supercritical
1. 제 목 : Thermal-hydraulics Analysis on Design of Supercritical
Water-Cooled Reactor
2. 연 사 : Professor S. Koshizuka
Nuclear Engineering Research Laboratory
Graduate School of Engineering
The University of Tokyo
3. 일 시 : 2002년 10월 30일 (수) 오후 4시
4. 장 소 : 301동 1512호
5. 요 약 :
Supercritical water-cooled reactor is an advanced design concept which aims economical improvement of nuclear power. The core is cooled by supercritical water which does not exhibit boiling. Once-through direct cycle is employed to simplify the plant system. This design concept has been developed in the University of Tokyo for these 10 years. The thermal-hydraulic analysis and design are reviewed here. Ongoing research projects in the world are also introduced.
6. 문 의 : 기계항공공학부 이준식 교수 (880-7117)
Water-Cooled Reactor
2. 연 사 : Professor S. Koshizuka
Nuclear Engineering Research Laboratory
Graduate School of Engineering
The University of Tokyo
3. 일 시 : 2002년 10월 30일 (수) 오후 4시
4. 장 소 : 301동 1512호
5. 요 약 :
Supercritical water-cooled reactor is an advanced design concept which aims economical improvement of nuclear power. The core is cooled by supercritical water which does not exhibit boiling. Once-through direct cycle is employed to simplify the plant system. This design concept has been developed in the University of Tokyo for these 10 years. The thermal-hydraulic analysis and design are reviewed here. Ongoing research projects in the world are also introduced.
6. 문 의 : 기계항공공학부 이준식 교수 (880-7117)