Optimization of operation and maintenance of nuclear power plant by probabilistic fracture mechanics

2002 ◽  
Vol 214 (1-2) ◽  
pp. 1-12 ◽  
Author(s):  
Noriyoshi Maeda ◽  
Shinichi Nakagawa ◽  
Genki Yagawa ◽  
Shinobu Yoshimura
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Probabilistic Fracture Mechanics ◽  
Operation And Maintenance

Application of Probabilistic Fracture Mechanics Analysis on BWR Recirculation Piping Systems

2016 ◽  
Author(s):  
Yu-Yu Shen ◽  
Hsoung-Wei Chou ◽  
Chin-Cheng Huang ◽  
Ru-Feng Liu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Fracture Probability ◽  
Probability Of Detection ◽  
Piping System ◽  
Probabilistic Fracture Mechanics ◽  
Piping Systems ◽  
Inspection And Maintenance

In recent years, the probabilistic fracture mechanics (PFM) approach has been widely applied to estimate the fracture risk of nuclear power plant piping systems. In the paper, the probabilistic fracture mechanics code, PRO-LOCA, developed by the Probabilistic Analysis as a Regulatory Tool for Risk Informed Decision Guidance (PARTRIDGE) project, is employed to practically evaluate the fracture probability of the recirculation piping system welds in a Taiwan domestic boiling water reactor (BWR) nuclear power plant. To begin with, the models based on the real situation of the recirculation piping welds are built. Then, the probabilities of through-wall cracking, leak with different rates, and rupture on the welds considering both in-service inspection and leak detection are analyzed. Meanwhile, the effects of probability of detection curves of ISI on the piping are simulated. Further, the efficiencies of performing the induction heating stress improvement and weld overlay are also studied and discussed. The present work could provide a reference of operation, inspection and maintenance for BWR plants in Taiwan.

The Use of the ASME PRA Standard in Pressure Vessel and Piping Work

2002 ◽  
Author(s):  
Richard A. Hill
Keyword(s):  
Risk Assessment ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Risk Information ◽  
Technical Requirements ◽  
Operation And Maintenance ◽  
Construction Operation ◽  
Standard Sets

After several years of intense labor by many industry people, ASME is about to issue its newly approved PRA standard. This standard is for probabilistic risk assessment (PRA) for nuclear power plant applications. It is not a standard on how to build a PRA model; although, that could be inferred from the standard’s technical requirements. This Standard sets forth requirements for PRAs used to support risk-informed decisions related to design, licensing, procurement, construction, operation, and maintenance. It also prescribes a method for applying these requirements depending the degree to which risk information is needed and credited.

Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2

2002 ◽  
Author(s):  
Bjorn Brickstad ◽  
Adam Letzter ◽  
Arturas Klimasauskas ◽  
Robertas Alzbutas ◽  
Linas Nedzinskas ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Pilot Study ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Damage Mechanism ◽  
Core Damage ◽  
Steel Welds ◽  
Nuclear Power Plant Unit

A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.

scholarly journals PERHITUNGAN BIAYA OPERASI DAN PERAWATAN PLTN SKALA BESAR DAN KECIL

2015 ◽  
Vol 17 (2) ◽  
pp. 87
Author(s):  
Mochamad Nasrullah ◽  
Wiku Lulus Widodo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Secondary Data ◽  
Capacity Factor ◽  
Maintenance Cost ◽  
Small Scale ◽  
Operation And Maintenance ◽  
Operation And Maintenance Cost

ABSTRAK PERHITUNGAN BIAYA OPERASI DAN PERAWATAN PLTN SKALA BESAR DAN KECIL. Biaya pembangkit PLTN terdiri dari tiga komponen, yaitu biaya investasi, bahan bakar dan operasi perawatan (O & M). Besarnya biaya O&M pada PLTN besar dan kecil tidaklah sama. Studi ini bertujuan untuk menghitung biaya O&M PLTN skala besar dan kecil dengan mempertimbangkan parameter teknis dan ekonomis yang diambil dari berbagai data sekunder dan sumber lainnya. Studi dilakukan menggunakan data dari PLTN jenis PWR dengan daya 1343 MWe untuk PLTN ukuran besar dan daya 90 MWe untuk PLTN ukuran kecil. Asumsi digunakan tingkat eskalasi sebesar 5%, faktor kapasitas 90%. Metodologi yang digunakan adalah menghitung dengan spreadsheet yang meliputi skala masing-masing komponen O&M. Hasil perhitungan menunjukkan biaya O & M jika dihitung dengan satuan juta US$/tahun, maka biaya O&M PLTN 1343 MWe sebesar 99,21 juta US$/tahun lebih mahal dari PLTN 90 MWe sebesar 45,13 juta US $/tahun. Namun jika biaya O & M PLTN 1343 MWe dihitung dengan satuan mills $/kWh, maka hasilnya  sebesar 9,37 lebih murah dibandingkan dengan PLTN 90 MWe yaitu sebesar 63,70 mills $/kWh. Hal ini berarti semakin kecil ukuran kapasitas dayanya maka biaya operasi dan perawatannya semakin mahal. Penyebab perbedaan biaya operasi dan perawatan antara PLTN skala besar dan kecil, adalah kapasitas daya, faktor kapasitas, jumlah personal yang bekerja pada biaya administrasi umum pegawai dan manajemen, operasi pembangkit tahunan, biaya tenaga kerja offsite. Kata kunci : Biaya operasi dan perawatan, PLTN, LEGECOST ABSTRACT CALCULATION OF OPERATION AND MAINTENANCE COST FOR LARGE AND SMALL SCALE NPP. The generation cost of nuclear power plant consists of three components:  investment costs, fuel cost operation and maintenance (O&M) cost. O&M costs in the large scale of NPP is different from small scale NPP. The objective of this study are to calculate the O&M cost of large NPP and small NPP by considering technical and economic parameters from secondary data and  other references. This study uses 1343 MWe PWR data for large NPP and 90 MWe PWR for small NPP. The assumptions are 5% escalation level and 90% capacity factor. The methodology for calculation using spreadsheet with scaling methods for each O&M components. The results shows that the O &M cost if calculated in units of million US$/year, the O&M cost of NPP 1343 MWe is US$million 99.21/ year which is more expensive than the O&M cost of NPP 90 Mwe which is only US$million 45.13/ year.  But if the cost of O&M 1343 MWe nuclear power plant unit is calculated in units of mills $/kWh, the result shows that the O&M cost is 9.37 mills $/kWh which is less than the 90 MWe NPP which reaches $ 63.70 mills/kWh. The conclusion is  lower NPP capacity  has higher O&M cost. Different O&M cost is caused by power capacity, capacity factor, the amount of worker on site staff, the annual net generation and the offsite technical support. Keywords: Operation and maintenance cost, NPP, LEGECOST 

Thermal Performance Monitoring and Optimization in Dukovany NPP

2014 ◽  
Author(s):  
Jiri Pliska ◽  
Zdenek Machat ◽  
Libor Veznik ◽  
Jiri Smisek
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Performance ◽  
Nuclear Power ◽  
Performance Monitoring ◽  
Accurate Determination ◽  
Process Data ◽  
Important Indicator ◽  
Operation And Maintenance

Competition in the electricity market forces producers to achieve — in compliance with safety — efficiency of production as high as possible. This efficiency and heat rate is an important indicator of both the condition of the power plant equipment and the quality of power plant operation. To cope with these challenges, powerful methods are process data reconciliation, statistical data processing of large data sets and process simulation. These functions and methods can be used to obtain useful information about process quality and equipment and sensor health. The paper discusses practical experience from six years of using a thermal performance monitoring and optimization system in the Dukovany nuclear power plant. The system is integrated into the overall nuclear power plant process information system and data warehouse. The system provides information in near real time. The major benefit of the system lies in a deep view into equipment behaviour and process which ensures timely detection and identification of functionality degradation of process and equipment or sensor faults. The system also helps to find and use margins of equipment operation and the overall thermal cycle. Selected practical examples are used to demonstrate specific benefits of the system for operation and maintenance of the Dukovany nuclear power plant. There are examples of equipment fault detection and sensor degradation detection. The optimization function is explained with an example of cooling circuit optimization aimed to increase the delivery of electrical power into the grid. A detailed description of behaviour of the main components can be used for their performance evaluation and their repair planning. The benefit of more accurate determination of parameter values is reflected in more accurate determination of reactor thermal output. The conclusion of the paper provides an overall evaluation of system benefits for operation and maintenance of a nuclear power plant.

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