[en] GO methodology is a method of system reliability with success-oriented, it has been applied in non-repairable system. The author studies application of GO methodology in repairable system. Considering dependence of components, the quantitative formulas of some GO operations for repairable system have been derived. According to this study, the GO program has been developed. Reliability parameters such as steady availability and failure number can be calculated directly from GO figure and a High Pressure Injection System of Nuclear Power Plant example is given. The study is available for developing and application of GO methodology in repairable system such as nuclear engineering pipeline systems or chemical process systems

[en] The author presents the thermocouple penetration assemblies of 10MW high temperature gas cooled reactor(HTR-10). The thermocouple penetration assemblies, which consist of penetration pipe, assemblies of sheath thermocouple and protective pipe for welding, are used to measure the temperature of components in the reactor. The laser welding technology is used to weld the transition pipe that is designed specially to the sheath thermocouple, and the argon arc weld(TIG) is used for welding the transitional pipe to the penetration pipe. So the difficult problem of sealing under high pressure and high temperature in helium gas environment is solved. By using the long sheath thermocouples, which pass through the containment and are sealed by the swage lock, the traditional commutator for temperature measure signal is avoided. By analysing and calculating with ANSYS program, the structure designs are proved to meet the case for the requirements of stress and earthquake-resistant. For authors' thermocouple penetration assemblies, the leakage of helium gas is less than 1 x 10^-7Pa·m³/s. Passing serial strict test, the thermocouple penetration assemblies have already been fixed in the reactor by now

[en] As the world-wide accepted advanced nuclear reactor, the most prominent characteristic of High-temperature Gas-cooled Modular Reactor is its inherent safety. The core arrangement of the 10 MW High-temperature Gas-cooled Reactor, which is now under construction, is described in detail. The features of its structure design are analyzed, and based on these features, the advantages of inherent safety and manufacture are also discussed

[en] The author has briefly summarized the major achievements of Daya Bau Nuclear Power Plant since its commercial operation, and particularly presented the key management approaches and practices

[en] In the experimental research of reactor thermohydraulic behavior on test facility, an electric heater is always used instead of a nuclear reactor. There are many inherent reactivity feedback in a real reactor, such as temperature coefficient feedback and void coefficient feedback, so when an electric heater is used as a nuclear fuel in a test facility, it is required to simulate the reactivity feedback. An analysis of effect of reactivity feedback is made and a method of simulating reactivity feedback is proposed

[en] The set up of abnormal events database for the High Flux Engineering Test Reactor (HFETR) is described, and its abnormal event are counted analyzed. The results show that the main abnormal events include reactor control and protection system breakdown, reactor coolant system breakdown and others breakdown. These three breakdowns make up about 86.09% of the total events. But the influence of they on the reactor safety is not clear

[en] RELAP5/MOD3 code is used to analyze 4 x 4 fuel-assemble test's small break loss of coolant accident. The results show emergency core cooling system for the tests can ensure the test core safety, not influence High Flux Engineering Reactor

[en] Heat-treatment and machining are two key process when manufacturing pressurizer forging, which need to be performed heat-treatment many times to assure its mechanical strength because of being used as the pressure-resistant vessel. The mechanical property of forging must be satisfied the technology requirements after preliminary heat-treatment and property heat-treatment. Because the enclosure heat of Qinshan phase-II nuclear power project is a special big type spherical surface, it is very difficult to perform its mechanical machining. The author introduces a mechanical machining method to overcome the difficulty for hoisting and determining datum

[en] Using the functions of the software 'I-DEAS Master Series 5', such as the mode of design, drafting, simulation, test, geometry and so on, the task of stereo graphics simulating the PWR is done. Reliability of designed data is checked

[en] The coordination control system and its design method for nuclear power device are given. At present, it is a advanced control system which have been accepted in other many industrial processes. DCS (Distributed Control System) with high, new technologies provides the coordination control system with prime hardware and software