Development of the ageing management database of PUSPATI TRIGA reactor

Steam Generator Ageing Management Database

18th International Conference on Nuclear Engineering: Volume 5 ◽

10.1115/icone18-30279 ◽

2010 ◽

Author(s):

Junqi Chen ◽

Fei Xue ◽

Peng Liu ◽

Lin Zhou ◽

Lei Lin ◽

...

Keyword(s):

Real Time ◽

Steam Generator ◽

Information Technologies ◽

Online Monitoring ◽

Information Management System ◽

Management Program ◽

Time Data ◽

Operation Condition ◽

Ageing Management ◽

Management Database

Steam generator (SG) is one of the key important equipments to safety of nuclear power plant (NPP), which is covered by NPP ageing management program (AMP). SG tube rapture often takes place due to stress corrosion crack for a long time according to international application. And its reliability is the only one vital weakness of nuclear steam supply system (NSSS), so it is necessary to increase its reliability for safety operation in ageing management (AM) area. Utility engineers and managers frequently use information of their individual SG to optimize SG AM in their plants. However the SG AM data has not always been readily available, thus the Steam Generator Ageing Management Database (SGAMDB) was developed to integrate decentralized information and provide a valuable data center that the data needed could be easily and quickly retrieved, and can serve as the basis platform for optimizing SG ageing evaluation and management. SGAMDB is an online interactive integrated information management system. Some modern information technologies are applied, especially real-time data acquisition and virtual reality technology. The in-situ application of SGAMDB can improve efficiency in SG AM. As the main platform for SG AM, it not only contains all equipment condition information and important operation data that are needed based on data warehouse technology, but also provides fundamental online monitoring, trend analysis, ageing assessment functions and basis data management functions. The assessment models and technology of real-time online monitoring can ensure SG a controllable state during in-service time, find the change of operation environment and adjust the operation condition early, so as to reduce influence for equipment ageing.

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Maximum Temperature Calculation and Operational Characteristics of Fuel Follower Control Rods for the AFRRI TRIGA Reactor Facility

10.21236/ada237744 ◽

1991 ◽

Author(s):

M. Forsbacka ◽

M. Moore

Keyword(s):

Maximum Temperature ◽

Reactor Facility ◽

Triga Reactor ◽

Temperature Calculation ◽

Operational Characteristics ◽

Control Rods

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Demonstration of Fatigue for LTO License of NPP Borssele

Volume 3: Design and Analysis ◽

10.1115/pvp2015-45791 ◽

2015 ◽

Author(s):

M. H. C. Hannink ◽

F. J. Blom ◽

P. W. B. Quist ◽

A. E. de Jong ◽

W. Besuijen

Keyword(s):

Environmental Effects ◽

Nuclear Power ◽

Power Plants ◽

Integrated Approach ◽

Temperature Measurements ◽

Fatigue Assessment ◽

Term Operation ◽

Load Monitoring ◽

Number Of Cycles ◽

Ageing Management

Long Term Operation (LTO) of nuclear power plants (NPPs) requires an ageing management review and a revalidation of Time Limited Ageing Analyses (TLAAs) of structures and components important for nuclear safety. An important ageing effect to manage is fatigue. Generally, the basis for this is formed by the fatigue analyses of the safety relevant components. In this paper, the methodology for the revalidation of fatigue TLAAs is demonstrated for LTO of NPP Borssele in the Netherlands. The LTO demonstration starts with a scoping survey to determine the components and locations having relevant fatigue loadings. The scope was defined by assessment against international practice and guidelines and engineering judgment. Next, a methodical review was performed of all existing fatigue TLAAs. This also includes the latest international developments regarding environmental effects. In order to reduce conservatism, a comparison was made between the number of cycles in the analyses and the number of cycles projected to the end of the intended LTO period. The projected number of cycles is based on transient counting. The loading conditions used in the analyses were assessed by means of temperature measurements by the fatigue monitoring system (FAMOS). As a result of the review, further fatigue assessment or assessment of environmental effects was necessary for certain locations. New analyses were performed using state-of-the-art calculation and assessment methods. The methodology is demonstrated by means of an example of the surge line. The model includes the piping, as well as the nozzles on the pressurizer and the main coolant line. The thermal loadings for the fatigue analysis are based on temperature measurements. Fatigue management of the NPP is ensured by means of the fatigue concept where load monitoring, transient counting and fatigue assessment are coupled through an integrated approach during the entire period of LTO.

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