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

Restoration of the graphite memory of a reactor in the third power-generating unit of the Leningrad nuclear power plant

Atomic Energy ◽  
1999 ◽  
Vol 87 (5) ◽  
pp. 823-827
Author(s):  
V. I. Lebedev ◽  
Yu. V. Garusov ◽  
M. A. Pavlov ◽  
A. N. Peunov ◽  
E. P. Kozlov
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Generating Unit ◽  
The Third ◽  
Leningrad Nuclear Power Plant

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.

scholarly journals STUDIES ON THERMAL DIFFUSION AND VERIFICATION OF THE THIRD NUCLEAR POWER PLANT IN TAIWAN

1986 ◽  
Vol 1 (20) ◽  
pp. 198
Author(s):  
K.C. Tang ◽  
M.T. Tsai ◽  
Y.R. Hwang ◽  
H.H. Hwung
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Numerical Simulations ◽  
Thermal Diffusion ◽  
Nuclear Power ◽  
Field Measurements ◽  
Hydraulic Model ◽  
Model Tests ◽  
The Third ◽  
Made In

In general, hydraulic model tests and numerical simulations can be used for securing enough informations in order to assess the environmental impact by thermal discharge after the power plant operation. However, the numerical simulations should be verified by the consequence of hydraulic model tests or the field data. Then, the numerical model can be used as a prediction model to foresee the nature of thermal diffusion when the additional generators will be operated. The third nuclear power plant in Taiwan has been constructed in 1984. In order to protect the abundant corals which distributed on the rocky bottom around this power plant, a complete studies on thermal diffusion have been performed, accordingly, a verification with field measurements were also made in this paper.

Engineering Assessment Approach for the Leningrad Nuclear Power Plant In-Depth Safety Assessment

2000 ◽  
Author(s):  
Garill Coles ◽  
Sam McKay ◽  
Jon Young ◽  
Yuri Skok
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Safety Analysis ◽  
Regulatory Compliance ◽  
Regulatory Requirements ◽  
Related Function ◽  
Assessment Approach ◽  
Leningrad Nuclear Power Plant

Abstract Engineering assessment that supports the safety basis for a reactor plant operating license is defined as: “An assessment of a system to determine its adequacy to successfully perform its safety-related function(s) when required.” The approach to engineering assessment of systems at the Leningrad Nuclear Power Plant (LNPP), as part of its in-depth safety assessment (ISA), is unique. The content and format of engineering assessments for western Safety Analysis Reports (SARs) have evolved over time and current requirements are somewhat scattered in the governing documents (USNRC, 1978). Many regulatory guides and requirements (western or eastern) have not kept up with changes in safety analysis technology. Performance of the ISA for LNPP affords the opportunity to rethink the approach to engineering assessments, and to incorporate current methods and latest technology in safety analysis. As an example, for many systems, information about system reliability obtained from a modem Probabilistic Safety Assessment is more comprehensive than that from a Single Failure Analysis as prescribed in SAR content and format guides. Overall, the engineering assessment of LNPP systems looks at five major assessment elements: 1) assessment of regulatory compliance, 2) assessment of operability, 3) assessment of vulnerability, 4) assessment of environmental qualifications, and 5) assessment of reliability. By reorganizing the approach to meeting regulatory requirements, and by looking at engineering assessment in various ways, information can be obtained that goes beyond simply demonstrating regulatory compliance to more fully supporting the safety basis for a plant operating license.

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