“Making It Work”: The Vital Role of Commissioning in Nuclear Power Programs

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
John H. Moore
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Vital Role ◽  
Special Relationship ◽  
Plant Component ◽  
Term Operation

This paper presents an overview of the duties of a nuclear power plant (NPP) commissioning organization and its special relationship with both the early stages of an NPP project and the long-term operation of such power plants. Decisions made early in the design and procurement process need to be understood by commissioning staff, and their implications need to be incorporated into commissioning programs. Commissioning programs also need to take the steps needed to baseline plant-component ageing programs to facilitate the long-term NPP operation.

Steam Line Integrity Analyses for LTO: Enhancing Credibility With Comprehensive Measurement

2012 ◽  
Author(s):  
Horst Rothenhöfer ◽  
Andreas Manke
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Simulation Models ◽  
Proper Function ◽  
Blow Down ◽  
Term Operation ◽  
High Level ◽  
Comprehensive Measurement

The safety relevant components of nuclear power plant Neckarwestheim 1 — in service since 1976 — have been reviewed and updated for long-term operation (LTO). The actions included hardware retrofits as well as updates of analysis according to the latest state of the scientific and technical knowledge. For large piping such as the steam lines, the established pipes have been retained while the supports have been optimized. All shock absorbers (snubbers) including corresponding inertia have been eliminated resulting in a defined guidance and statically defined displacements. The integrity analyses for the optimized steam lines, including break preclusion, have been validated successfully with comprehensive measurements. The verification has delivered an extra high level of credibility, exceeding the “standard” requirements to achieve fitness for service in long-term operation. Measurement and validation, which are the main focus of this paper, range from monitoring of service loads to the static and dynamic measurements of pressure, local temperatures and displacements during initial start-up after implementation of the design modifications. The proper function of supports has been proved and the quality of the simulation models has been confirmed. Some expected and some unexpected dynamic events have been detected during blow-down tests. It was demonstrated that the amplitudes of all dynamic loads stay within limits. The validation of analyses with comprehensive measurement has been an important proof of quality and delivered the redundancy required for the integrity of a nuclear power plant in service, enhancing the high level of safety even more.

Fatigue Monitoring in the Context of Long-Term Operation of the Goesgen Nuclear Power Plant Using AREVA’s FAMOSi

2015 ◽  
Author(s):  
Thomas Wermelinger ◽  
Florian Bruckmüller ◽  
Benedikt Heinz
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Primary Circuit ◽  
Feed Water ◽  
Term Operation ◽  
Operation Modes ◽  
Fatigue Monitoring ◽  
Load Evaluation

In the context of long-term operation or lifetime extension most regulatory bodies demand from utilities and operators of nuclear power plants to monitor and evaluate the fatigue of system, structures and components systematically. As does the Swiss Federal Nuclear Safety Inspectorate ENSI. The nuclear power plant Goesgen started its commercial operation in 1979 and will go into long-term operation in 2019. The increased demand for monitoring and evaluating fatigue due to the pending long-term operation led the Goesgen nuclear power plant to expand the scope of their surveillance and therefore to install AREVA’s fatigue monitoring system FAMOSi in the 2014 outage. The system consists of 39 measurement sections positioned at the primary circuit and the feed-water nozzles of the steam generators. The locations were chosen due to their sensitivity for fatigue. The installed FAMOSi system consists of a total of 173 thermocouples which were mounted in order to get the necessary input data for load evaluation. The advantage of FAMOSi is the possibility to obtain real data of transients near places with highest fatigue usage factors. Examples of steam generator feed-in during heating-up and cooling-down will be given. In addition, spray events before and after the installation of closed loop controlled spray valves will be compared. The measurements and the results of the load evaluation are not only of interest for internal use e.g. in regard to optimization of operation modes (e.g. load-following), but must also be reported to ENSI annually. In addition, by evaluation of stresses and determination of usage factors combined with an optimization of operation modes an early exchange of components can be avoided.

scholarly journals Prospects of diversification and ensuring energy safety of Uzbekistan

2019 ◽  
Vol 139 ◽  
pp. 01002 ◽  
Author(s):  
Kahraman Allaev ◽  
Tokhir Makhmudov
Keyword(s):  
Renewable Energy ◽  
Energy Balance ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Current State ◽  
The Republic

The data on the current state of energy in Uzbekistan are given. The need to diversify the structure of the energy balance of the republic is shown, which ensures the energy security of the state in the medium and long term. It is argued that the construction of a nuclear power plant in Uzbekistan is not only expedient, but also necessary. In the future, renewable energy and nuclear power plants will become the basis of energy in Uzbekistan.

The role of pressure vessel embrittlement in the long term operation of nuclear power plants

2012 ◽  
Vol 243 ◽  
pp. 63-68 ◽  
Author(s):  
A. Ballesteros ◽  
R. Ahlstrand ◽  
C. Bruynooghe ◽  
U. von Estorff ◽  
L. Debarberis
Keyword(s):  
Pressure Vessel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Term Operation

scholarly journals Study of the Characteristics of Wind over Nuclear Power Plants in Korea

2021 ◽  
Vol 21 (1) ◽  
pp. 57-70
Author(s):  
Su-Bin Oh ◽  
Chun-Ji Kim ◽  
Sang-Hyun Lee ◽  
Hyun-Ha Lee ◽  
Chun-Sil Jin ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Protective Action ◽  
Radioactive Materials ◽  
Sea Breezes ◽  
Wind Characteristics ◽  
And Diffusion

To establish a strategy for public protective action from radioactive leakage in the event of Nuclear Power Plant (NPP) accidents, long-term records of wind data collected at the Korean NPPs were analyzed. Wind characteristics related to the advection and diffusion of radioactive pollutants were examined by analyzing the wind direction, speed, and land-sea breezes for NPPs (Hanbit, Hanul, Wolsong, Kori, and Shin-Kori) in Korea. The study also analyzed the characteristics of calm winds causing the accumulation of radioactive materials. The wind characteristics of each NPP differ depending on the seasonal and daily variabilities; thus, a detailed time-scaled airflow database is required. In addition, the findings, through continuous updates of the airflow database, will contribute to improving preparedness.

Development of an ASME QME-1-2007 Program for Safety Related Active Valve Assemblies for Advanced Plants

2011 ◽  
Author(s):  
L. Ike Ezekoye ◽  
Edward W. Drake
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Mechanical Equipment ◽  
Plant Component ◽  
Valve Assembly ◽  
Active Valve ◽  
The Right

ASME QME-1 “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants” sets forth the requirements and guidelines which could be used to assure that active mechanical equipment is qualified for specified service conditions [1]. As determined by federal regulators and/or nuclear power plant licensees, this Standard could be applied to future nuclear power plants, or existing operating nuclear power plant component replacements, modifications, or additions. Over the years, the standard has gone through various revisions to both clarify and extend the requirements. However, the ASME QME-1-2007 standard significantly altered the qualification process for Active Valve Assemblies. For new nuclear plants, such as the Westinghouse AP1000, the change required a redevelopment of the valve assembly qualification program. This paper examines how the ASME QME-1-2007 valve assembly qualification requirements changed, how this has affected new plant valve assemblies and overall equipment qualification program, and the lessons that have been learned during the redevelopment and implementation of the standard. Specific issues covered in this paper include selecting the qualified valves and adjusting valve actuator qualifications to provide the right inputs to the ASME QME-1-2007 program.

scholarly journals Long-term operation of a boiling pressure vessel and its internals

2019 ◽  
Vol 52 (4) ◽  
pp. 200-221
Author(s):  
Otso Cronvall
Keyword(s):  
Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Power Plants ◽  
Pilot Project ◽  
Computational Time ◽  
Degradation Mechanisms ◽  
Term Operation ◽  
Reactor Pressure

This study concerns the long-term operation (LTO) of a boiling water reactor (BWR) reactor pressure vessel (RPV) and its internals. The main parts of this study are: survey on the susceptibility to degradation mechanisms, and computational time limited ageing analyses (TLAAs). The ageing of nuclear power plants (NPPs) emphasizes the need to anticipate the possible degradation mechanisms. The BWR survey on the susceptibility to these mechanisms uses the RPVs and significant internals of the Olkiluoto power plant units OL1 and OL2 as a pilot project. For the components that screened in, the potential to brittle, ductile or other degradation is determined. This was carried out by applying structural mechanics and fracture mechanics procedures. Only some most significant cases and results are presented here.

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