Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

2017 ◽  
Author(s):  
Yang Cheng ◽  
Zhang Xueliang ◽  
Xia Peng ◽  
Zeng Qingyue ◽  
Li Tian
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technology Development ◽  
Nuclear Industry ◽  
Third Generation ◽  
Difference Analysis ◽  
The Third ◽  
Pressure Test ◽  
Service Inspection

RSE-M 2010 and ASME Section XI are the widely used and most detailed PWR in-service inspection regulations applied in China PWRs which are separately belong to French AFCEN and American ASME regulations, and come from the different nuclear industry practices of their countries. In 1987, the French M310 type reactor was imported to China and therewith the RSE-M in-service inspection regulation was introduced, beginning to be widely used in China PWRs since that time. Meanwhile, Chinese nuclear power institutes began to independently develop its own PWR reactor named Qinshan Phase I Nuclear Power Plant, and then ASME Section XI in-service inspection regulation was used which was also beginning to be widely used in some Chinese PWRs. With the nuclear power technology development and innovation, such regulations are continually updated and perfected. Thus, there are many differences during application in Chinese specific PWRs. This paper has performed quite deeply application difference analysis between the two regulations based on several aspects, such as upstream laws cited, component classification, inspection requirement, NDE, qualification, pressure test and the Safety Authority review requirements for licensing. Some preliminary thinking has been presented during applying these two regulations and some technical suggestions have been also provided to perfect the regulations in the hope to provide better reference during application on the third generation PWRs (including HPR1000) in China.

The Durability Design of the Technical Specifications for Nuclear Building Concrete of ACP1000

2017 ◽  
Author(s):  
Chen Dan ◽  
Liu Yulin ◽  
Zhang Weiguo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Raw Materials ◽  
Site Conditions ◽  
Third Generation ◽  
The Third ◽  
Technical Requirements ◽  
Durability Design ◽  
Materials Used

For the continuous improvement of nuclear power plants safety standards, the actual requirements of the plant’s long service life, and the diversification of the plant site conditions, the durability design of nuclear building concrete structure has attracted widespread attention gradually. ACP1000, the third generation class nuclear power plant, is developed by China independently, and it may locate in different site conditions. Taking an ACP1000 nuclear power plant under construction as an example, this paper provides the technical requirements of concrete and concrete raw materials used in nuclear building. And by comparing with AP1000, the third generation class nuclear power plant imported from the United States, the advance and reasonableness of technical requirements of concrete and concrete raw materials used in nuclear building are provided further evidence.

What’s New in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components

2004 ◽  
Author(s):  
Gary Park
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Mechanical Engineering ◽  
Nuclear Industry ◽  
Nondestructive Examination ◽  
American Society ◽  
Plant Components

The nuclear industry is a pretty dynamic industry, in that it is always on the move, changing every time we turn around. For that very reason, there is a need to keep up with the industry by providing changes to American Society of Mechanical Engineering Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components.” There have been many changes over the last three years. This paper addresses a few of those, but gives a feel for the number of changes from the 2000 Addenda to the 2003 Addenda, there have been a total of approximately 56 changes. Of those changes, 11 were in the repair/replacement requirements, 19 in the inspection requirements, 4 in the evaluation requirements, 18 in the nondestructive examination requirements, and 4 in the administrative requirements. The paper classifies the changes as “Technically Significant,” “Significant,” “Non-Significant,” or “Editorial.” The paper addresses only a few of those changes that were “Technically Significant.” The paper also includes some of the activities that the ASME Section XI Subcommittee is currently working on.

The Analysis and Realization of Interpreter Language in Nuclear Industry

2014 ◽  
Vol 989-994 ◽  
pp. 2097-2100
Author(s):  
Zheng Zhang ◽  
Hai Bo He ◽  
Hao Liang Lu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Semantic Analysis ◽  
Reactor Core ◽  
Nuclear Industry ◽  
Logical Language ◽  
Grammatical Analysis ◽  
Actual Operating ◽  
Comparison Results

In order to satisfy the calculation requirements of nuclear power plant operating in different conditions, the integration and combination of reactor core computation modules have been proposed. By writing logical language instructions, and then read by interpreter, the engineering designers can make grammatical analysis, lexical analysis, semantic analysis and information extraction. In Linux system environment, the interpreter can fulfill computational tasks based on the actual operating parameters of nuclear power plant. The comparison results indicate that the calculated results obtained by the interpreter language are correct. Therefore, it also demonstrates that the interpreter language is valid.

Application of RSE-M2010 on In-Service Inspection of Taishan EPR Project

2013 ◽  
Author(s):  
Xueliang Zhang ◽  
Chunbing Shao ◽  
Ximing Tang ◽  
Cheng Yang ◽  
Huixing Feng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Previous Edition ◽  
Future Improvement ◽  
Service Inspection ◽  
Industrial Risk

The latest edition of French In-service Inspection Rules RSE-M2010, incorporating the up-to-date upstream French regulations, orders and requirements for pressure equipments, and taking into account both of the radioactive risk and industrial risk in nuclear power plant (NPP), has been adopted as the applicable rule for in-service inspection (ISI) of EPR units. In RSE-M2010, the previously used benchmark for classification Safety Class has been replaced by the Nuclear Pressure Equipments Class (ESPN Class), and the category of pressure equipments has been introduced to monitor the industry risks of NPP pressure equipments, making it much more precise and convenient to define the scope of equipments which subjected to ISI and corresponding ISI requirements on frequency and methods. This paper described the main differences of the ISI requirements in RSE-M2010 and previous edition of RSE-M, also introduced practices of applying RSE-M2010 when preparing the ISI program of Taishan EPR units. Based on the application practice of RSE-M2010 on Taishan EPR project, some proposals for future improvement of this code are presented. Preliminary thinking for future implementation of EPR ISI activities has also been described.

EDF Decommissioning Programme: A Global Commitment to a Sustainable Development

2003 ◽  
Author(s):  
Jean-Jacques Grenouillet
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Cost Effective ◽  
Eu Enlargement ◽  
Nuclear Industry ◽  
Successful Implementation ◽  
Early Closure

Nowadays, decommissioning of nuclear power plants has become a key issue for nuclear industry in Europe. The phasing out of nuclear energy in Germany, Belgium and Sweden, as well as the early closure of nuclear units in applicant countries in the frame of EU enlargement, has largely contributed to consider decommissioning as the next challenge to face. The situation is slightly different in France where nuclear energy is still considered as a safe, cost-effective and environment friendly energy source. Electricite´ de France (EDF) is working on the development of a new generation of reactor to replace the existing one and erection of a new nuclear power plant could start in the next few years. Nevertheless, to achieve this objective, it will be necessary to get the support of political decision-makers and the acceptance of public opinion. Due to the growing concern of these stakeholders for environmental issues, their support can only be obtained if it is possible to demonstrate that nuclear energy industry will not leave behind unsolved issues that will be a burden to the next generations. In this context decommissioning of the first generation of EDF NPPs constitutes a prerequisite for the erection of a new type of nuclear power plant. This paper will present the programme defined by EDF for the decommissioning of its nine already shutdown reactors (Fig. 1). The reasons of the recent evolution of EDF decommissioning strategy will be explained and the key issues that will contribute to the successful implementation of this programme will be addressed. Finally, what has been achieved on sites so far and major planned activities will be described.

Improving Public Acceptance to Nuclear Power: Policy, Practice and Experience With Public Communication

2017 ◽  
Author(s):  
Zhang Xiaofeng ◽  
Zhao Feng ◽  
Zhu Rongxu ◽  
Yang Zongzhen ◽  
Shangguan Zhihong
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Public Awareness ◽  
Rapid Development ◽  
Clean Energy ◽  
Nuclear Industry ◽  
Public Acceptance ◽  
Public Communication ◽  
Administrative Authority

With the development of public awareness on environmental protection, especially after the Fukushima nuclear accident, the opposition to nuclear power due to NIMBY (not in my back yard) effect begins to hinder the rapid development of Chinese nuclear industry. For example, in recent years several large-scale mass incidents with appealing to stop the siting and construction of nuclear facilities in China have put related projects (including nuclear power plant and nuclear fuel cycle facility) into termination, resulting in certain financial loss and unnecessary social unstabilization, thus causing more and more concern from administrative authority, research institution and nuclear industry. To strengthen public acceptance on nuclear power, related enterprises such as CGN and CNNC have made great efforts in information disclosure to eliminate mysterious feelings towards nuclear power and expect to build new impression as clean energy. Domestic institutions and universities carry out plenty of work on methods to help public correctly perceive nuclear risk and present strategies for effective public communication. Administrative authority also issued detailed guidance on public communication required to be fulfilled during plant’s siting phase, which provided explicit provisions on the responsibility and job content of different entities. Here we will take one public communication practice of one nuclear power project located in south Zhejiang region as an example. In this scenario, we face more difficulty than other projects, such as doubt from local government, complexity of public types, and large amount of stakeholders. In this paper, we will make summary on endeavors to improve public acceptance, such as large amount of NPP visits, comprehensive scientific popularization, direct communication with stakeholders and integration development between local society and nuclear industry. And we will discuss the feasibility of innovative practice, combining several similar tasks needed in different subjects, such as environmental impact assessment and social stabilization assessment, to fulfill at once. To achieve this goal, we design specific questionnaire and use it to survey the opinion of more than 800 people in the fairly large region across different provinces, covering 30km radius area of site, which gains satisfactory results. By comparing outcomes of opinion surveys carried out before and after the practice, we will put forward to the considerable effect of public communication in improving public acceptance to nuclear power, and analysis the pros and cons of this example. Moreover, we also expect the good experience in practice can be promoted to overall processes of nuclear power plant, including siting, construction, commission and life extension, helping nuclear power gain more public acceptance.

Chemicotechnological regime during preparation of the third block of the Leningrad Nuclear Power Plant for physical start-up

1982 ◽  
Vol 52 (2) ◽  
pp. 141-144
Author(s):  
V. M. Sedov ◽  
P. G. Krutikov ◽  
N. V. Nemirov ◽  
S. T. Zolotukhin ◽  
A. V. Devochkin ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
The Third ◽  
Start Up ◽  
Leningrad Nuclear Power Plant
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