How a Knowledge Data Base Assists the Process of Aging Management

2011 ◽  
Author(s):  
Horst Rothenho¨fer ◽  
Friedrich Scho¨ckle ◽  
Gu¨nter Ko¨nig
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Base ◽  
Nuclear Power ◽  
Collaborative Work ◽  
Operational Experience ◽  
Operational Parameters ◽  
Pdca Cycle ◽  
Definition Of ◽  
Status Analysis

The process of aging management in a nuclear power plant requires collaborative work of different departments. In this process information has to be gathered and evaluated systematically. At the beginning of the process it is important to classify all systems, structures and components (SSCs) into 3 categories of descending importance concerning safety where only the first two categories have to be considered for aging management. Basic information on the material and dimensions, operational parameters, quality status, analysis reports and relevant degradation mechanisms is stored in the data base for all SSCs of category 1 and 2. While a nuclear power plant is in service numerous events may occur which are related to aging and may have an influence on the quality of SSCs. Relevant events may be malfunction messages, maintenance results, operational experience, results of surveillance or events in external installations. It is important to evaluate these events concerning the aspect of aging and to decide which measures are required to prevent unexpected events of the same kind in the future. In some cases the new experience has to be assigned to comparable SSCs. These evaluations, the definition of measures and the tracking of their effectiveness have to be done by an aging management team that meets regularly every 3 months. The knowledge data base supports the application of the PDCA cycle and provides an overview and fast access to all quality documents related to each SSC including surveillance measures and results. It simplifies the generation of annual status reports which are valuable quality documents that reveal the effectiveness of aging management. Finally the procedure can be extended to SSCs which are important for the availability of the plant and thus take a step forward from aging management to plant life management.

Concept for the Guarantee of the Integrity of Bolted Flanged Connections in a German Nuclear Power Plant

2008 ◽  
Author(s):  
Manfred Schaaf ◽  
Friedrich Schoeckle ◽  
Jaroslav Bartonicek
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Base ◽  
Nuclear Power ◽  
Test Laboratory ◽  
Third Party ◽  
Nuclear Facilities ◽  
Systematic Treatment ◽  
Bolted Flange ◽  
Test Loading

In nuclear facilities in Germany a systematic treatment of all sealing connections which are opened during the annual shutdowns is performed since several years. Special attention is paid to a design which meets specifications of the bolted flange connections (BFC’s). Apart from the use of suitable and certified materials this includes also the calculation of the required torques in accordance to the present rules. For the calculation procedure the nuclear code KTA 3211.2 (draft 2003) is applied which allows a tightness proof of the BFC, besides a stress analysis. For this calculation, experimentally achieved gasket characteristics according to DIN 28090-1 are required, which are either supplied by the gasket manufacturers or determined in the amtec test laboratory. The geometry and material data of each BFC are stored in a special data base. In addition, the data of the operating state as well as the design and test loading cases are included in the data base, so that all inputs for a later calculation are available. The results of the calculation which must be checked and approved by an expert third-party are stored in the flange data base, too (assembly state settings of each flange connection). On this base individual flange data sheets can be provided to the flange fitter teams that include all necessary information for assembly of each BFC (bolts, nuts, gasket, geometry and material specifications, lubricant, etc.).

scholarly journals The Armenian nuclear power plant: problems of electricity export

2018 ◽  
Vol 212 ◽  
pp. 02010
Author(s):  
Vahe Davtyan
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Power Market ◽  
Electric Power Market ◽  
South Caucasus ◽  
Definition Of ◽  
Armenian Nuclear Power Plant

The prerequisites for the development of Armenia’s nuclear power industry are indicated. The main geopolitical problems of operation of the Armenian NPP are revealed through studying the electric power market of the South Caucasus with the definition of the export opportunities of Armenia. The main problems of nuclear fuel supplies to the Armenian NPP are studied. Recommendations are given on the long-term development of nuclear energy in Armenia.

Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant

2018 ◽  
Vol 4 (2) ◽  
Author(s):  
Tamás János Katona ◽  
András Vilimi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Severe Accident ◽  
Exceedance Probability ◽  
Basic Question ◽  
Existing Structures ◽  
Design Basis ◽  
Accident Management ◽  
Definition Of

Paks Nuclear Power Plant (NPP) identified the post-Fukushima actions for mitigation and management of severe accidents caused by external events that include updating of some hazard assessments, evaluation of margins of existing severe accident management (SAM) facilities, and construction of some new systems and facilities. While developing the SAM strategy, the basic question was what is the sufficient margin above the design basis level of existing structures, systems, and components for avoiding the cliff-edge effects, and what level of or hazard should be taken for the design of new structures and systems dedicated for SAM. Paks NPP developed an applicable in the practice concept for the qualification of already implemented SAM measures and design the new post-Fukushima measures that are outlined in the paper. The concept is based on the generalization of the procedure and assumptions used in the definition of acceptable margins for seismic loads, analysis of the steepness of the hazard curves and features of the hazards. Justification of the definition of exceedance probability of the design basis effects for the design of SAM systems is given based on the first order reliability theory. The application of the concept is presented on several practical examples.

scholarly journals Room Classification Based on EMC Conditions in Nuclear Power Plants

Energies ◽  
2020 ◽  
Vol 13 (2) ◽  
pp. 359 ◽  
Author(s):  
Hrvoje Grganić ◽  
Davor Grgić ◽  
Siniša Šadek
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Electromagnetic Compatibility ◽  
Numerical Calculations ◽  
Operational Experience ◽  
Systematic Classification

Electromagnetic compatibility (EMC) in nuclear power plants today mostly relies on the qualification tests of the new equipment and adhering to some good installation practices. Diversity of the electromagnetic environment and different susceptibility of the plant equipment calls for a systematic classification of the EMC zones in a nuclear power plant. The paper proposes a methodology that uses a combination of the qualification tests, in situ and bench immunity tests, site survey measurements, operational experience, and numerical calculations to divide a nuclear power plant into a reasonable number of EMC zones. This would primarily help to have a better overview of the current EMC level in the plant and to unify emission and susceptibility requirements for the new equipment. In this paper, special attention is given to the preparation and performance of the in situ tests, which present the most challenging step of the methodology. In addition, the paper proposes some of the possible applications of the numerical calculations and addresses their challenges and limitations. The novel classification methodology, inspired by the equipment qualification program, is illustrated with examples from Krško Nuclear Power Plant, which recently performed a comprehensive EMC assessment.

A Multi-Objective Optimization of the Reactor Power Plant

2018 ◽  
Author(s):  
Chen Lei ◽  
Jia Zhen ◽  
Wang Cong ◽  
Gong Zili ◽  
Liao Yi ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Mathematical Models ◽  
Steam Generator ◽  
Nuclear Power ◽  
Sensitivity Analyses ◽  
Immune Memory ◽  
Multi Objective Optimization ◽  
Operational Parameters ◽  
Multi Objective

From the view of practical engineering application, a compacter nuclear power plant is expected. The weight and the volume of a nuclear power plant can be reduced by optimal selection of the operational parameters. In this work, a thermal-hydraulic model of the reactor, mathematical models of the reactor vessel, the main pipe, the pressurizer, the steam generator, the turbine and the condenser were established for the Qinshan-I nuclear power plant based on the related technical materials. The responses of the optimal targets to the changes of the design variables were studied by the sensitivity analyses. The non-dominated solution front of the nuclear power plant was obtained by means of the immune memory clone constrained multi-objective optimization algorithm. The study shows that the component mathematical models are reliable for the optimization process, the distribution of the non-dominated solution is decided by the steam generator secondary pressure. The volume and the weight of the system could be at least reduced by 23.0% and 9.5%, respectively.

scholarly journals Development of a Leading Performance Indicator from Operational Experience and Resilience in a Nuclear Power Plant

2016 ◽  
Vol 48 (1) ◽  
pp. 114-128 ◽  
Author(s):  
Pamela F. Nelson ◽  
Cecilia Martin-Del-Campo ◽  
Bruce Hallbert ◽  
Ali Mosleh
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Performance Indicator ◽  
Operational Experience

scholarly journals Nuclear media discourses after the closure of the Ignalina Nuclear Power Plant: Is the game over?

2019 ◽  
Vol 12 (3) ◽  
pp. 335-360
Author(s):  
Natalija Mažeikienė ◽  
Judita Kasperiūnienė ◽  
Ilona Tandzegolskienė
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Critical Discourse Analysis ◽  
Media Coverage ◽  
Nuclear Power ◽  
The Public ◽  
The Media ◽  
Definition Of ◽  
Media Discourses ◽  
The Town

The article presents a critical discourse analysis of media coverage of the most important Lithuanian strategic object — the Ignalina Nuclear Power Plant INPP — in the three biggest news portals. Media news focuses mostly on certain aspects of decommissioning of the INPP management issues and the transparency of financing mechanisms. Environmental and social aspects of the decommissioning are not sufficiently disclosed and discussed. The community of Visaginas the satellite town for the workers of the INPP remains an invisible and silent actor of the discourse. In the media news portals, the town is portrayed as disconnected from the INPP. This divide could be explained by assuming that after the closure of the INPP as a major feeding enterprise the town must search for a re-definition of its identity and construct this identity without nuclear energy and without the INPP. On the other hand, such a divide reflects a common trend characteristic of the entire nuclear discourse — to disempower communities and the public, create a boundary between the industry and the public, between the experts and ordinary citizens.

scholarly journals Improving collaborative work and project management in a nuclear power plant design team: A human-centered design approach

2016 ◽  
Vol 94 ◽  
pp. 555-565 ◽  
Author(s):  
Guy André Boy ◽  
Gopal Jani ◽  
Annalisa Manera ◽  
Matthew Memmott ◽  
Bojan Petrovic ◽  
...  
Keyword(s):  
Project Management ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Collaborative Work ◽  
Design Approach ◽  
Design Team ◽  
Plant Design ◽  
Human Centered Design
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