核电厂的安全文化

以DNMC(大亚湾核电站)管理干部安全文化培训教材为基础,简要地说明核电厂的安全、设计、管理、组织文化、安全文化这一系列概念的基本内容和相互之间的关系。重点解释了安全文化体系的构成要素;政策层、管理层和员工个人三层承诺的基本要求;并对典型的安全文化事项,如透明的文化、习惯性违规等进行了分析和论断。人三层承诺的基本要求;并对典型的安全文化事项,如透明的文化、习惯性违规等进行了分析和论断。     

Safety goals for nuclear power plant regulation

A survey and comparison has been made of 10 widely disseminated safety goal proposals originating in Canada, the U.K. and the U.S. When the proposals are placed in a directly comparable numerical context, they are remarkably similar in the inferred levels of safety. The development of quantitative safety goals by the U.S. Nuclear Regulatory Commission is also reviewed. While progress has been made in structuring technically and politically defensible goals, because of the way the regulatory philosophy has evolved in the U.S. the implementation of such goals could well turn out to be more difficult than defining the goals themselves.The safety goals are useful in providing guidance to the designers, operators and regulators of nuclear power plants with regard to public safety concerns as well as plant reliability and engineering considerations.     

The economic effect of increased seismic load on nuclear power plant design and construction costs

A research program aimed at providing the desired level of seismic resistance of nuclear power plants in a cost-effective manner is proposed. The results of such a research program would provide direct measurement of seismic design parameters associated with loadings which closely simulate real strong motion characteristics on major structural and mechanical systems.     

Safety design consideration for HTGR coupling with hydrogen production plant

Safety requirements and design considerations are examined for a nuclear hydrogen production system that consists of High Temperature Gas-cooled Reactor (HTGR) and a hydrogen production plant by thermochemical water splitting iodine–sulfur process (IS process). Requirements in order to construct hydrogen production plants under conventional chemical plant regulation are identified in order to take into account a fundamental difference in safety philosophy between the nuclear facility and chemical plant and meet requests from the potential users of nuclear heat. In addition, safety requirements for the collocation of the nuclear facility and hydrogen production plant utilizing IS process (IS plant) are investigated. Furthermore, design considerations to comply with the requirements are suggested and the technical feasibility of the design considerations is evaluated. The evaluation results for a reference plant showed that safe distance determined by the chemical plant regulation against combustible gas and hazardous chemical leakages comply with the plant layout design. Furthermore, the results demonstrated the feasibility of IS plant construction under non-nuclear regulation by showing that the tritium concentration in IS plant can be maintained below the regulation limit and reactor normal operation can be achieved during abnormal conditions in the IS plant. These results clarified that design considerations suggested for coupling the IS plant to HTGR are reasonably practicable. The proposed criteria can be used not only for coupling hydrogen production plants but also for other chemical plants such as steam reforming plants, etc.     

核电机组电气设计分析

近年来,我国核电事业得到快速发展,一大批核电项目陆续开工建设,其中大部分为引进技术的二代改进型和三代核电机组。由于技术输出国的标准规范与我国现有的核电设计标准不一致,以及考虑厂址适应性等问题,我国对引进的核电机组存在逐步消化、吸收并改进的过程。本文对核电机组的电气设计进行探讨,希望对今后同类工程具有参考作用。     

核电厂核事故应急演习新模式的实践

研究核事故应急演习监督评估的现状及存在问题,探索并首次实践了一种"无预先通知、无演习脚本、无专门准备、多重突发事件叠加"的核事故综合应急演习监督评估模式,分析了这种模式的良好实践,并讨论了后续深入开展相关工作的方法。     

Research needs and improvement of standards for nuclear power plant design

The need for research and improvement of code requirements, for both economy and safety reasons, is discussed for the following topics relevant to nuclear power plant structural analysis: Earthquake definition; dynamic behavior of reinforced concrete structures under impact loads; design for postulated pipe rupture; code requirements for loading combinations for concrete structures, reinforcing steel splicing, reinforced concrete structural design for thermal effects.     

Structural analysis and design of a nuclear power plant building for aircraft crash effects

The object of this investigation is to assess the effect of a large commercial airplane crashing perpendicularly on to the surface of a spherical reactor building dome. This investigation is related to a project currently in execution. Practical solutions of the postulated case, which vary in the degree of engineering effort used, are shown. Based on safety consideration the various solutions are discussed from the viewpoint of penetration, cracking and collapse modes of failure, where, primarily, the carrying capacity of the structure under an equivalent statical load is considered. The performed investigations include:

1. (a) Calculation of the failure load following the yield line theory;

2. (b) Calculation of the sectional forces using the linear-elastic shell theory and subsequent design by the ultimate strength method;

3. (c) Calculation of the failure load, establishing of the failure mechanism and distribution of sectional forces using the plastic shell theory;

4. (d) Calculation using a three-dimensional FEM program with plastic capabilities; this includes the collapse load, the failure mechanism and the distribution of sectional forces.

A discussion of the resultant forces and the configutation of the critical section is given for the various methods used. The evaluation of the carrying capacity of the structure with respect to load is based on energy considerations. It is attempted to compare such results, to evaluate possible simplifications in the used solutions, and to give some recommendations for the practical design and for the development of structural details.     

An integrated translation of design data of a nuclear power plant from a specification-driven plant design system to neutral model data

How to efficiently integrate and manage lifecycle data of a nuclear power plant has gradually become an important object of study. Because plants usually have a very long period of operation and maintenance, the plant design data need to be presented in a computer-interpretable form and to be independent of any commercial systems. The conversion of plant design data from various design systems into neutral model data is therefore an important technology for the effective operation and maintenance of plants. In this study, a neutral model for the efficient integration of plant design data is chosen from among the currently available options and extended in order to cover the information model requirements of nuclear power plants in Korea. After the mapping of the neutral model and the data model of a specification-driven plant design system, a plant data translator is also implemented in accordance with the schema mapping results.     

Transition to a new size of the sanitary-protective zone of a nuclear power plant

In our country, in accordance with world-wide practice, nuclear power plant safety is ensured by the systematic implementation of the concept of deeply esheloned protection based on the use of a system of physical barriers, including a fuel matrix, fuel-element cladding, boundary of the reactor coolant loop, airtight sealing of the reactor system, and radiation protection. In the Soviet Union, in contrast to other countries, an additional barrier was introduced in the construction and operation of nuclear power plants-a sanitary-protective zone separating the atomic power plant from housing developments. The results achieved in nuclear power give every basis for concluding that it is in principle possible to reject the use of part of the environment for protecting the public from the radiation effects of a nuclear power plant operating under normal conditions, i.e., the size of the sanitary-protective zone of the territory of the industrial site of a nuclear power plant can be limited in accordance with the operative law and normative base. The results of calculations and validations are presented. __________ Translated from Atomnaya énergiya,Vol. 100, No. 6, pp. 458–465, June, 2006.     

Significance of seismic response spectrum normalization in nuclear power plant design

Peak ground acceleration has been used most commonly to normalize seismic response spectra. Apparently, there is a general consensus that this is not the best parameter for spectrum normalization. Several other parameters have been proposed, such as, peak acceleration-velocity-displacement triad, peak velocity and spectrum intensity. This paper presents statistical studies of response spectra from a number of recorded earthquake motions normalized by several different parameters. The parameters used are peak acceleration, peak velocity, spectrum intensity, spectrum ordinate, etc. Spectrum shapes are generated corresponding to 84 percentile probability level for different normalization parameters. These shapes are compared with the other standrad spectrum shapes used in the nuclear power plant design to investigate significance of different normalization techniques.     

Numerical method for the containment of fission products at a hypothetical accident in an underground nuclear power plant

As one means to expand the siting of nuclear power plants, construction of underground plants is now under study. An underground nuclear power plant has the feature that ground surrounding the underground cavity can contain the fission products of a hypothetical accident.If it is assumed that in a hypothetical reactor accident the cooling system loses its capacity wholly or partially, and gas containing fission products is emitted into the underground cavity. As a result, temperature, gas concentration and gas pressure in the cavity increase and it can be supposed that the gas leaks up to the surface through the ground, and that ground-water contains and carries fission products. The present paper numerically simulates a course of movement as mentioned above by the finite element method and gives the underground containment effect for fission products from a hypothetical accident.     

Safety prediction in nuclear power

The practical operational safety of nuclear objects is of fundamental importance for assessing the future prospects under discussion and selecting a strategy for the development of nuclear power. It is shown that the methods currently being used for making safety predictions do not contain an analysis of the unavoidable errors and uncertainties of the models used or the initial and boundary conditions under which the physical processes that develop into serious accidents arise and develop. It is proposed that the method of quantile estimates of the uncertainties, which is free of the drawbacks of the Monte Carlo method and which increases the reliability of safety predictions in nuclear power, be used. __________ Translated from Atomnaya énergiya, Vol. 102, No. 2, pp. 80–86, February, 2007.     

核电厂HRA定性分析

人因可靠性分析(HRA)是核电厂概率安全评价(PSA)的重要组成部分,定性分析是HRA的基础和出发点。本文介绍了核电厂HRA定性分析的目的、原则、方法和程序,并以压水堆核电厂SGTR为具体实例进行说明。