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Featured researches published by He Shuyan.


Nuclear Engineering and Design | 2002

The primary loop confinement and pressure boundary system of the HTR-10

He Shuyan; Zhang Zhengming; Qin Zhenya

Abstract The design philosophy and requirements of the HTR-10 reactor building and the primary loop confinement are introduced in this paper. Also introduced are the design, fabrication and the installation of the HTR-10 primary loop pressure boundary system. The primary loop confinement comprises the sealed cavities of the reinforced concrete structure. The main components and the connected gas systems of the primary loop pressure boundary system are contained in the confinement. Under normal operating condition, the inside pressure of the confinement is kept at negative pressure to ensure the sealing function of the confinement. There is a rupture disk of overpressure protection in the confinement wall. After a depressurization accident the pressure of the confinement increases and the rupture disk will break. The air of the confinement is discharged directly to the atmosphere through the accident discharge chimney which is connected to the rupture disk without filter. The main components of the primary loop pressure boundary system consist of the reactor pressure vessel, the steam generator pressure vessel and the hot gas duct vessel. All the above main components are installed in the reactor cavity and the steam generator cavity. They are all nuclear safety class 1 components, whose materials production, design, fabrication, and tests are carried out according to ASME Section III and relevant Chinese nuclear codes.


Nuclear Engineering and Design | 1993

Containment for the low temperature district nuclear-heating reactor

He Shuyan; Dong Duo

Abstract An integral arrangement is adopted for the Low Temperature District Nuclear-Heating Reactor. The primary heat exchangers, control rod drives and spent fuel elements are put in the reactor pressure vessel together with the reactor core. The primary coolant flows in natural circulation through the reactor core and the primary heat exchangers. The primary coolant pipes penetrating the wall of the reactor pressure vessel are all of small diameters. The reactor vessel constitutes the main part of the pressure boundary of the primary coolant. Therefore a small sized metallic containment closed to the wall of the reactor vessel can be used for the reactor. Design principles and functions of the containment are the same as for the containment of a PWR. But the adoption of a small sized containment brings about some benefits such as a short period of manufacturing, relatively low cost, and ease for sealing. A loss of primary coolant accident would not be happened during a rupture accident of the primary coolant pressure boundary inside the containment owing to its intrinsic safety.


Journal of Nuclear Materials | 2006

The influence of roughness on tribological properties of nuclear grade graphite

Luo Xiaowei; Yu Suyuan; Sheng Xuanyu; He Shuyan


Archive | 2013

Small portable self-adaptive hydraulic pipe bender

Zhao Jiaqing; He Shuyan; Luo Xiaowei; Wu Xinshen


Archive | 2005

Sealing structure of aluminium alloy and stainless steel flange

Sheng Xuanyu; He Shuyan; Wu Xinxin


Archive | 2005

Damper-free support system for modular high temperature air-cooled pile pressure casing

He Shuyan; Fu Jiyang; Zhang Zhengming


Archive | 2003

Automatic distant gravitational escapement

He Shuyan; Sheng Xuanyu; Yu Suyuan


Archive | 2014

Compact fan cooler and fan

Luo Xiaowei; Min Qi; Zhang Li; Wu Xinshen; Liu Junjie; He Shuyan


Nuclear Engineering and Design | 2007

Seismic analysis of liquid storage container in nuclear reactors

Zhang Zhengming; He Shuyan; Xu Ming


Archive | 2005

Shaftless rotary gate for nuclear reactor experimental hole shielding

Sheng Xuanyu; Wu Shenxin; He Shuyan

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