[en] Progress report on nuclear science and technology in China (Vol. 2) includes 698 articles which are communicated on the second national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the third one, the content is about nuclear power (Pt.2)

[en] Starting from 1990's, CGN has been actively involved in the introduction, digestion, absorption and re-innovation of reactor design software, and is gradually establishing a software R and D system with CGN's characteristics. This paper briefly introduces the software introduction history and its application status in CGN, and summarizes the independent reactor software R and D system of CGN. (authors)

[en] Base on the analysis of deign documents and process, a database for instrumentation and control system design can be developed with a popular desktop relational database management system (RDBMS). With the RDBMS, an instrumentation and control system CAD system can be built unitizing database link feature of popular CAD software, with the function of management of design data, output of list and forms. and design of drawings. A CAD system of this kind has been used in the design practice of nuclear power plant. With this system, it is shown that, the consistency of information has been controlled and the load on the engineer has been significantly reduced. The methodology used here can also be used in the CAD system for CAP1000 and CAP1400 plant. (authors) series

[en] Fukushima nuclear disaster knocked the alarm bell to the world again. Human being are developing nuclear power prudently, what's more, should prepare for nuclear emergency perfectly. Civil nuclear diathesis should be improved to develop nuclear power, include nuclear security diathesis of all levels of officers and relatively specialists. Mightiness support of consummate nuclear emergency system is necessary to develop nuclear power. Consummate nuclear emergency system is urgent to develop nuclear power. Six proposals are suggested. (authors)

[en] This paper mainly introduces the turbine trip test conditions on 100% FP power platform of Unit 1 of Tianwan Nuclear Power Station. The transient phenomenon and response condition of control system in the course of test are analyzed in this paper; and the problems found in each trip test both on Unit 1 and Unit 2 as well as the optimized design scheme are synthetically analyzed. (author)

[en] March 11, 2011, a huge earthquake and tidal waves in Japan lead to dangerous levels of nuclear leakage at Fukushima nuclear plant, the nuclear accident also cause public panic m many countries. To investigate the reason of the public panic, we employ the theories of sociology and psychology, analyzed that the public panic come from Ignorant Panic. Herd Behavior, Primacy Effect, Stereotype Activation Effect, and the superposition of these effects. In addition, we proposed three measures to the public panic: First, we should emphasize the safety of nuclear power and establish the positive image of nuclear power Second, we should emphasize the popular science of nuclear power so that nu clear power can be accepted in the public; Third, we should enhance the psychological intervention system for nuclear safe emergency and improve the effect of psychological intervention

[en] The underwater Vacuum Cleaner is especially designed for picking up of foreign objects, which may have fallen into reactor pool and spent fuel storage pool. The article describes the working principle, structure and capability as well as one experience of gasket retrieval in the reactor pool. (authors)

[en] The nuclear power plant secondary loop steam and water piping will has local wall thinning under the attack of flow-accelerated corrosion, liquid droplet impingement or cavitation erosion. It will cause leakage or pipe rupture during nuclear power plant operation, more seriously cause unplanned shut down, human damage and heavy economic losses without effective management of wall-thinning. Through investigation. information collection and analysis, the management methodology, tools, practice and research development of wall-thinning management in China and foreign country was introduced in this paper. The advantage and disadvantage, applicability, reliability and economy of two different management methods are discussed in detail. Furthermore, the wall-thinning records of nuclear power plants located at Qinshan and Tianwan of China and some important feedbacks are analyzed. Take into account the actual situation of China nuclear power plants and current management practice, some advice and suggestion on developing effective nuclear power plant secondary loop steam and water piping wall-thinning management are put forward from code development, management procedure development, components and locations selection, measurement method selection and application, result evaluation, residual life predication and decision making, feedbacks usage and inspection plan optimization. (authors)

[en] The pressure vessel is a large open vertical cylindrical thick-walled vessel, which is connected by flange and bolt. It is mainly formed by three parts, container, cover, and the tighten components. Pressure vessel body is a thick- walled cylindrical steel shell, which is welded hemispherical bottom end of head, upper part of a detachable, fitted with a flange and sealing ring on the hemispherical head, the waist has several inlet and outlet nozzle, inside of the pressure vessel is the reactor core, reactor core is composed of fuel assemblies and control rods assemblies. Water as the power transfer get into the pressure vessel through the inlet nozzle, flowing through to the annular space between the core basket and vessel wall, in the bottom of pressure vessel upward flowing through the reactor core, with the reflection of heat generated by nuclear fuel be taken, through outlet nozzle to steam generator to converted into the steam, steam drive the turbine to whirl together with the generator, in this way the electricity has been generated continuously, and been sent to all over the world through the grid. (author)

[en] Farley-Tihange Phenomenon due to thermal fatigue frequently appears on the downstream area filled with cool and heat water of the residual heat removal heat-exchange equipment and the base metal and welding joint of the RIS and RRA pipes connected with the primary coolant pipe directly in global Nuclear power plants in operation. Which brings unacceptable defects, even worse, LOCA. During the pre-service inspection, autonomic ultrasonic test and radiographic test were done to relative pipes and welds of Unit 3 of the Qinshan Nuclear Power Phase Ⅱ. This article summarizes the recurrent position and potential risks of the Farley-Tihange phenomenon, establishes the fault tree of its failure causes, analyses failure mechanism and models of heat fatigue, presents systematically prevention and treatment methods including in-operation supervision, shut-down inspections, emergent maintenance program and so on. (authors)