REACTOR CONTAINMENT STRUCTURE COOLING SYSTEM

• Main Authors: KIM HWAN YEOL, SONG YONG MANN, SONG JIN HO, HA KWANG SOON
• Format: Patent
• Language: English; Japanese
• Published: 08.01.2015
• Subjects: DECONTAMINATION ARRANGEMENTS THEREFOR; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; NUCLEAR ENGINEERING; NUCLEAR PHYSICS; NUCLEAR REACTORS; PHYSICS; PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT; REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGYGENERATION, TRANSMISSION OR DISTRIBUTION; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS; TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE; TREATING RADIOACTIVELY CONTAMINATED MATERIAL

PROBLEM TO BE SOLVED: To provide a reactor containment structure cooling system allowing long-term operation by natural convection without power supply.SOLUTION: A reactor containment structure 10 cooling system includes: a containment structure 10 containing a reactor; a pressure vessel 20 housing condensed water W inside and having a housing space at least part of which is positioned lower than the bottom of the containment structure 10; a discharge pipe 30 connecting inside of the containment structure 10 and inside of the pressure vessel 10 so as to make water vapor and fission products generated in the containment structure 10 flowable to the pressure vessel 10 at the occurrence of an accident; and a recovery pipe 40 connecting inside of the pressure vessel 20 and inside of the containment structure 10 so as to make the condensed water W housed in the pressure vessel 20 flowable to the containment structure 10. When the level of the condensed water W housed in the pressure vessel 20 is higher than the level of the containment structure 10, the condensed water W flows from the pressure vessel 20 toward the containment structure 10 by a water head difference. 【課題】自然対流によって電源供給なしに長期間運転が可能な原子炉格納構造物の冷却システムを提供する。【解決手段】原子炉格納構造物１０の冷却システムは、原子炉が格納された格納構造物１０と、内部に凝縮水Ｗが収容され、少なくとも一部が前記格納構造物１０の底部より低く位置する収容空間が形成された圧力容器２０と、事故発生時に前記格納構造物１０で発生した水蒸気及び核分裂生成物が圧力容器１０に流動可能になるように、格納構造物１０の内部と圧力容器１０の内部を連結する放出配管３０と、圧力容器２０に収容された凝縮水Ｗが格納構造物１０に流動可能になるように、圧力容器２０の内部と格納構造物１０の内部を連結する回収配管４０とを含み、圧力容器２０に収容された凝縮水Ｗの水位が格納構造物１０の水位よりも上昇する場合、凝縮水Ｗは、水頭差によって圧力容器２０から格納構造物１０側に流動する。【選択図】図１