Shanghai Nuclear Engineering Research & Design Institute

Shanghai Nuclear Engineering Research & Design Institute Co., Ltd.

Mingguang Zheng

Yu Chen

Jinquan Yan

Cheng Ye

Guoxing Gu

Yong Wang

Kemei Cao

Honghui Ge

Yuanwei Ye

Xiankang Dong

Wei Shi

Qiang Liu

Bo Yang

He Sun

Song Chen

Haitao Wang

Jian Qiu

Yun Ling

Zhan Liu

Libing Zhu

Zufeng Xia

Guobao Shi

Shujian Cheng

Boyu Han

Xia Su

Liuhua Shen

Fuzu Miao

A nuclear island base slab of a nuclear power plant and a manufacturing method therefor, and a nuclear island of a nuclear power plant. The nuclear island base slab of a nuclear power plant includes a concrete base slab body and a plurality of air ducts embedded in the concrete base slab body. The air duct has an internal-penetrating bent pipe structure. A first end of the air duct is exposed on an upper surface of the concrete base slab body. A second end of the air duct is exposed on a side surface or the upper surface of the concrete base slab body.

Nuclear island base slab of nuclear power plant, manufacturing method therefor, and nuclear island of nuclear power plant

An integrated passive reactor system including a pressure vessel, a containment vessel arranged outside the pressure vessel, and a reactor core arranged inside the pressure vessel. A primary loop operates in full natural circulation. The reactor system is provided with a secondary side passive residual heat removal system including a primary loop heat exchanger arranged inside the pressure vessel and a passive residual heat removal heat exchanger arranged outside the containment vessel. The primary loop heat exchanger is arranged above the reactor core. The passive residual heat removal heat exchanger is arranged inside a water tank which is fixed outside the containment vessel. The primary loop heat exchanger and the passive residual heat removal heat exchanger are connected by heat exchanger inlet pipelines and heat exchanger outlet pipelines.

Integrated reactor system having passive removal of residual heat

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

Growing community of inventors

Shanghai, China

Mingguang Zheng