Shanghai Nuclear Engineering Research & Design Institute

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

Jinquan Yan

Yu Chen

Mingguang Zheng

Cheng Ye

Guoxing Gu

Yong Wang

Kemei Cao

Yuanwei Ye

Xiankang Dong

Wei Shi

Ying Liu

Bo Yang

He Sun

Hao Jiang

Song Chen

Haitao Wang

Honghui Ge

Zhan Liu

Yun Ling

Jian Qiu

Libing Zhu

Zufeng Xia

Guobao Shi

Chunli Liu

Xia Su

Tingting Niu

Shuan Xia

Liuhua Shen

Youqiang Cai

Minming Zhan

Fuzu Miao

Mingxu Zhang

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

An acousto-optic leakage monitoring system for main steam pipeline in nuclear power plant. The system includes an acoustic emission leakage monitoring loop and a spectrum leakage monitoring loop, wherein the signal input ends of the acoustic emission leakage monitoring loop and the signal input ends of the spectrum leakage monitoring loop are respectively arranged at detection points of the main steam pipeline. The signal output ends of the acoustic emission leakage monitoring loop and the signal output ends of the spectrum leakage monitoring loop are communicatively connected to each other through a network switch, and the network switch is sequentially connected with a control unit and a display unit. Compared with the prior art, the acousto-optic leakage monitoring system for the main steam pipeline in nuclear power plant according to the present invention provides early warning before the main steam pipeline leaks and realizes the diversity and redundancy of the main steam pipeline leakage monitoring methods by combining acoustic emission and spectroscopy, so that the detection results are more credible, and the maintenance cost after installation is extremely low. The detection sensitivity is higher and the response time is shortened, which significantly improves the response speed after leakage is found and provides a larger safety margin.

Acousto-optic leakage monitoring system for nuclear power plant main steam pipeline

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

Jinquan Yan