Concept of Standard System Based on China Current Nuclear Power Construction

2014 ◽  
Author(s):  
Yuelan Yan
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Standard System ◽  
Power Development ◽  
Power Construction ◽  
Nuclear Power Development ◽  
System Method ◽  
The Subject ◽  
Power Standard

Since introduce different technical routes, during decades of nuclear power development in our country, the French RCC series standards, American ASME standards and Russian standards are adopted, which led to the current various standards exist in their own way. To promote the building of nuclear power standards system in China, in the year of 2012, important research subject “the research on the standard system of advanced nuclear power in China” has been carried out and subject “nuclear power construction and commissioning” is one of it.. By digestion and absorption of four oversea AP1000 units of Sanmen nuclear power plant in Zhejiang province and Haiyang nuclear power plant in Shandong province, the building of standard system during nuclear power construction suitable to our national condition is studied, including the system frame and composition standards, building standard system method during construction, namely through research and example to present what kind of standard system is suitable for China standard system during construction, and what kind of method or design is used to obtain and maintain such system. The thesis is to promote the subject research methods based on examples to build China’s nuclear power standard system.

Standard Requirements and Localization Development Trend for Nuclear Power Plant Key Components Material

2014 ◽  
Vol 628 ◽  
pp. 406-409
Author(s):  
Shao Jun Zhang ◽  
Yu Qi Kan ◽  
Da Peng Huang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Production Capacity ◽  
Development Trend ◽  
Power Development ◽  
Research Production ◽  
Existing Problems ◽  
Nuclear Power Development ◽  
Countermeasures And Suggestions

The production capacity of Nuclear Island Mechanical Components (NIMC) falls far behind of massive demand of nuclear power increasement. To achieve the goal of nuclear power development in China, the localization progress of key NIMC needs to be speeded up. Taking material of NIMC (not including nuclear fuel and related material) for example, through the analysis and discussion of the standard or norm, status quo of supply and research, production capacity and existing problems of material of NIMC in China, the major obstacles and factors restricting development of nuclear power plant are found out, and the countermeasures and suggestions are also introduced to accelerate the localization progress of key NIMC in this paper.

Advanced Construction Technologies for the Ohma Nuclear Power Plant Reactor Building of Electric Power Development Co., Ltd.

2010 ◽  
Author(s):  
Tatsuya Obata ◽  
Akihito Urashima ◽  
Kiyokatsu Watanabe ◽  
Tsumoru Miyahara
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Electric Power ◽  
Nuclear Power ◽  
Large Scale ◽  
Construction Method ◽  
Strong Wind ◽  
Power Development ◽  
Reactor Building ◽  
Aomori Prefecture

Electric Power Development Co., Ltd has been constructing Ohma Nuclear Power Plant aiming to start commercial operation in Nov. 2014. Ohma Nuclear Power Plant is located in Ohma-town, Aomori Prefecture and is a landmark power plant in which Mixed Oxide fuels can be loaded in the full core of the reactor. Hitachi-GE Nuclear Energy Ltd. and Kajima JV, both have extensive experience of nuclear power plant construction, are the main contractors of this project and supply the entire engineering, manufacturing of all major components, and execute the construction and commissioning for the reactor building. Ohma-town is located at the northernmost part of Aomori Prefecture bordering Tsugaru strait, where is exposed to severe cold and constant strong wind in winter. Such severe weather conditions make the construction very hard, however, Hitachi and KAJIMA tries to complete the project on schedule and on budget applying highly reliable advanced construction technologies, such as open-top and parallel construction method, all whether construction method, and large scale modularization technology. The groundbreaking (acquisition of the first construction permission) was already completed in May 2008. Its civil work steadily progressed, and the rock inspection was completed in Oct. 2009. Base mat will be completed in July 2010, and both building work and mechanical work go into full swing after installation of RCCV lower liner module.

TRANSFORMATION OF RADIOCESIUM SPECIATION IN PONDS AT THE VICINITY OF FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT AND ITS DYNAMICS IN “SEDIMENTS-WATER” SYSTEM

2021 ◽  
pp. 38-45
Author(s):  
A. V. Konoplev ◽  
◽  
Y. Wakiyama ◽  
T. Wada ◽  
M. Ivanov ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Water System ◽  
137Cs Activity ◽  
Exclusion Zone ◽  
Activity Concentrations ◽  
Dam Reservoirs ◽  
Radiocesium Interception Potential ◽  
The Subject

The paper is concerned with the results of 137Cs monitoring in the irrigation ponds of the Okuma town in the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) exclusion zone. The 137Cs activity concentrations in the ponds appeared to be higher than those in the rivers and dam reservoirs in the region. The study has revealed a trend for a decline in 137Cs activity concentrations, both particulate and dissolved. The rate of particulate 137Cs decline was much higher than that of dissolved. The total distri- bution coefficient Kd (137Cs) in the suspended sediment-water system in the studied ponds was decreasing in time with the rate constant of 0.12-0.18 year-1. Assuming that the decrease in Kd is associated with decomposition of hot glassy particles, the time scale of 137Cs leaching from them in these water bodies was estimated to be 5-8 years. These estimates are consistent with the findings of recent laboratory experiments on the subject. With respect to seasonal variations, the highest levels of dissolved 137Cs in the studied ponds were observed from June to October as a function of specific pond and monitoring year. Based on data about 137Cs speciation in the bottom sediment top layer of the ponds and its distri- bution in the sediment-water system, the exchangeable radiocesium interception potential RIPex(K) for the ponds sediments was estimated to be 1650-2250 mg-eq/kg, which is within the range of values measured by laboratory studies.

Review of the Applicability of Nuclear Regulatory Commission Information Notice (IN) 2012-14, “Motor Operated Valve Inoperable Because of Stem-Disc Separation,” to Constellation Energy Nuclear Group’s Ginna Station

2014 ◽  
Author(s):  
David Garofoli ◽  
Gregg Joss
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Operating Experience ◽  
Nuclear Regulatory Commission ◽  
Corrective Action ◽  
Level Of Confidence ◽  
Valve Stem ◽  
The Subject ◽  
Regulatory Commission

U.S. Nuclear Regulatory Commission (NRC) Information Notice (IN) 2012-14, “Motor-Operated Valve Inoperable Because of Stem-Disc Separation”, was issued to inform nuclear power-plant licensees of recent operating experience involving a motor-operated valve (MOV) that failed at the connection between the valve stem and disc. The NRC expectation was that recipients would review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. Additional regulatory suggestions and insights contained in the IN are not NRC requirements. On closer examination of the events involved, it became apparent that the undetected stem-disc separation observed with the subject MOV was not necessarily limited to that type or style of valve. In fact, the vast majority of inservice testing (IST) valves, and the manner in which they are tested, could also be susceptible to loss of functionality going undetected. The intent of the compliance project performed at the R.E. Ginna Station nuclear power plant was to examine the current testing performed on each IST program valve and determine the level of confidence that stem-disc separation would be detected. If the level of confidence was deemed less than acceptable for a subject valve, one or more augmented actions, as deemed both practicable and viable, were recommended for implementation. The purpose of this presentation paper is to describe the systematic methodology that was employed to validate the effectiveness of the current periodic IST valve testing conducted at the R.E. Ginna Station and the corrective-action recommendations that were made as deemed appropriate. The corrective action(s) were designed to preclude the occurrence of future stem-disc separation issues going undetected, which could result in the loss of valve and potentially the loss of the associated accident-mitigation system’s operational readiness condition. Paper published with permission.

scholarly journals Government Strategy To Improve Public Acceptance Toward Nuclear Power Plant

2018 ◽  
Vol 4 (1) ◽  
pp. 24
Author(s):  
Sovian Aritonang ◽  
Nining Parlina ◽  
Yanif Dwi Kuntjoro
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Design Research ◽  
Public Acceptance ◽  
Community Acceptance ◽  
Nuclear Power Development ◽  
The Government ◽  
Is Design

<p>This research to discuss the Government's strategy to increase public acceptance toward nuclear power development plan. The purpose of this research is to obtain recommendation for government’s strategy. It is design as descriptive qualitative one with design research. The results showed there are two strategies, namely; strategies of socialization through counseling and through online media. Based on the research, it is recommended that the government should establish a Coordination Board which is under the command of (under command) specifically in the case of nuclear power plants in Jepara.</p><p><span>Keywords: Nuclear Power Plant; Community acceptance; The government's strategy.</span></p>

Sign in / Sign up

Export Citation Format

Share Document