[en] Pumping station is the facility of water supply for the Qinshan Phase Two Nuclear Power Station, classified as the seismic category I item. Hereafter is a detailed description of its general analysis, including the establishment of the model, load definition and combination, methods and steps for earthquake resistance analysis, results analysis etc. It's a reference for the design of similar engineering project. (authors)

[en] To the design of nuclear facilities other than nuclear power plants, there is a set of standard design seismic spectrum for different kind of sites recommended in IAEA TECDOC 1347. The characteristics of the spectrum are studied in this paper, and comparing work is conducted between the spectrum and the one recommended in Chinese Standard GB50011-2010. The results are useful in the choosing of reasonable design spectrum in the design of nuclear facilities other that NPPs. (authors)

[en] Through the overview of the damage of Kashiwazaki-Kariwa nuclear power plant caused by Chuetu-Oki Earthquake, analysis and explanation are given to the design of the NPP. Some important issues are mentioned which are related to the seismic design and evaluation of nuclear power plants. (author)

[en] This article introduces a simplified method to analysis a conventional building, which can be kept integrity under a SSE. The method is based on conventional building design code, and can provide guide line for the checking calculation of a conventional building which can be kept integrity during and after a SSE. (author)

[en] Nonlinear finite element analysis of nuclear power plant prestressed concrete containment structure subjected to internal pressure is carried out. SOLID65 element and constitutive model of concrete in ANSYS are introduced in detail, and solution control methods are put forward. In numerical simulation, the radial displacement between 15 m and 30 m model height is larger than that at other level, and the radial displacement at about 25 m height is the maximum. Because of prestressing, the model structure is under compression till internal pressure is up to 0.42 MPa, and it satisfies the design requirement. Analysis of the model structure shows that the containment is safe under the given inner pressure, which can contribute to the integrity test of concrete containment structure. (authors)

[en] Due to the increasing complexity of engineered products, it is of great importance to develop a tool to assess reliability dependencies among components and systems under the uncertainty of system reliability structure. In this paper, a Bayesian network approach is proposed for evaluating the conditional probability of failure within a complex system, using a multilevel system configuration. Coupling with Bayesian inference, the posterior distributions of these conditional probabilities can be estimated by combining failure information and expert opinions at both system and component levels. Three data scenarios are considered in this study, and they demonstrate that, with the quantification of the stochastic relationship of reliability within a system, the dependency structure in system reliability can be gradually revealed by the data collected at different system levels. - Highlights: • A Bayesian network representation of system reliability is presented. • Bayesian inference methods for assessing dependencies in system reliability are developed. • Complete and incomplete data scenarios are discussed. • The proposed approach is able to integrate reliability information from multiple sources at multiple levels of the system.

[en] This paper highlights the importance of structure safety of nuclear power plants, raises 3 major issues in terms of nuclear safety regulation with the reflection of several significant beyond design basis events over the recent years, introduces the current progress of the research on the 3 issues and put forward the recommendations for further nuclear safety regulation. (authors)

[en] Earthquake is one of the external natural disasters threatening the operation of nuclear power plants. Scholar shave conducted extensive research on seismic fortification of systems, structures and components of nuclear power plants, but few studies have been conducted on post-earthquake disposal and recovery strategies for such major projects. This paper lists the events of nuclear power plants attacked by non-destructive earthquakes in recent years, and counts the situation of damage, restart and recovery, compares the settlement of seismic instrumentation system at home and abroad, investigates the post-earthquake disposal and recovery strategies at home and abroad, analyzes and puts forward some suggestions of post-earthquake disposal and recovery strategies for nuclear power plants: it is necessary to make clear the earthquake damage situation of nuclear power plants, formulate post-earthquake disposal guidance documents and operational procedures, refine inspection content and acceptance criteria, and pay attention to the accuracy of seismic records. (authors)

[en] HPR1000 Units are developed by CNPE and GNPE jointly. They are independent designs of 1000 MWe PWR nuclear power units. In the design of nuclear island buildings, technical improvements are involved according to up to date nuclear safety rules comparing to Generation 2 NPPs. In the aspect of seismic design, 3D FE models are established, the input design basis earthquake acceleration level is increased, and mufti-sets of foundation parameters are considered to enhance the safety and feasibility of the seismic design for NI buildings. Sloshing effects of liquids restored in safety related tanks are analyzed through use of nonlinear fluid-structure interaction FE analysis methods. Conforming to newly published HAF 102, large commercial aircraft crash are considered as an exceeding design basis event. Impact assessments are conducted for NI buildings. (authors)

[en] According to a large-span half-steel-concrete (HSC) composited beam in the composited roof in the HTR-PM, a 1:3 scale specimen is investigated by the static load test. By analyzing the loading, deflection, strain and fracture development of the specimen in the process, studying the mechanical characteristics and failure pattern of such components. The ANSYS finite element software is utilized in this paper to analyze the nonlinearity behavior of the HSC beam specimen, and through comparing the experimental results and the numerical simulation, it can be illustrated that the finite element model can simulate the HSC beam accurately. From the test results, it can be concluded that by means of appropriate shear connection and anchorage length, steel plate and concrete can work together very well and the HSC beam has good load carrying capacity and ductility. These conclusions can serve as a preliminary design reference for the large span half-steel-concrete composite beam in NPP. (author)