Shanghai Nuclear Engineering Research & Design Institute

Guoxing Gu

Yu Chen

Cheng Ye

Jinquan Yan

Mingguang Zheng

Yong Wang

Xiankang Dong

Yuanwei Ye

Wei Shi

He Sun

Song Chen

Kemei Cao

Honghui Ge

Yun Ling

Jian Qiu

Libing Zhu

Guobao Shi

Xia Su

Liuhua Shen

Fuzu Miao

Zufeng Xia

A passive cooling system for a reactor core of a large-scale pressurized water reactor nuclear power plant includes a shield building having an outer wall and a through air inlet arranged on an upper part of the outer wall, a water tank arranged at an upper part of the shield building, a cooling water distribution plate arranged above a top of a containment within the shield building, a spray pipe arranged at an inside of the top of the shield building and having a water inlet end and a water outlet end, wherein the water inlet end is connected to a bottom of the water tank and the water outlet end is extended to be above the cooling water distribution plate, and an air deflector arranged between the shield building and the containment and having an upper end connected to an inside of the top of the shield building.

Completely passive cooling system for reactor core after accident of large-scale pressurized water reactor nuclear power plant

A heat pipe based passive residual heat removal system for a spent fuel pool (). Partitions () are arranged around an inside of the spent fuel pool. Evaporation-end heat pipes () are arranged between the outside of the partitions and an inner wail of the pool. The evaporation-end heat pipes have outlets that extend beyond the pool and are connected to an Inlet of an ascending pipe (), and have inlets connected to an outlet of a descending pipe (). Condensation-end heat pipes () have inlets connected to an outlet of the ascending pipe, and have outlets connected to an inlet of the descending pipe. The heat pipes cool the spent fuel pool. A heat exchange by phase change of working medium in the heat pipe leads to heat exchange of low temperature difference and high efficiency, relying on density difference for natural circulation drive.

Heat pipe based passive residual heat removal system for spent fuel pool

An apparatus for retention of molten material for a Generation IV reactor after a nuclear power plant accident comprises an inner wall which is peripherally closed, a vapor channel wall with an opening at the bottom fixed in the inner side of the inner wall, a pressure vessel disposed in the vapor channel wall, a vapor rising channel formed between the pressure vessel and the vapor channel wall, and it further comprises an outer wall surrounding the inner wall, a core molten material retention apparatus fixed at the bottom of the inner wall, and a deflector keeping away from the inner wall and the core molten material retention apparatus to form a gap; wherein a coolant falling channel is formed between the outer wall and the deflector, a coolant inlet is disposed at the bottom of the deflector, and a coolant channel is disposed between the inner wall and the core molten material retention apparatus; a core molten material retention recess is disposed at the upper surface of the core molten material retention apparatus, and the lower surface of the core molten material retention apparatus is arch-shaped; the core molten material retention apparatus is made of non-metal inorganic fireproof material. The invention adopts the design of molten material retention outside the reactor, using different material containing molten material and cooling the molten material by coolant cycle and the deflector structure, thus to improve the safety of the nuclear power plant.

Apparatus for retention of molten material outside generation IV reactor after nuclear power plant accident

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Shanghai, China

Guoxing Gu