Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant

2021 ◽  
Vol 373 ◽  
pp. 111015
Author(s):  
Claudio Tripodo ◽  
Stefano Lorenzi ◽  
Antonio Cammi
2017 ◽  
Vol 48 ◽  
pp. 491-515 ◽  
Author(s):  
Karol Kulkowski ◽  
Michał Grochowski ◽  
Kazimierz Duzinkiewicz ◽  
Anna Kobylarz

Author(s):  
Tatiana Grebennikova ◽  
Abbie N Jones ◽  
Clint Alan Sharrad

Irradiated graphite waste management is one of the major challenges of nuclear power-plant decommissioning throughout the world and significantly in the UK, France and Russia where over 85 reactors employed...


2018 ◽  
Vol 212 ◽  
pp. 02010
Author(s):  
Vahe Davtyan

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.


2018 ◽  
Vol 4 (2) ◽  
Author(s):  
Tamás János Katona ◽  
András Vilimi

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.


Author(s):  
Horst Rothenho¨fer ◽  
Friedrich Scho¨ckle ◽  
Gu¨nter Ko¨nig

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.


Author(s):  
Masaaki Suzuki ◽  
Kazuyuki Demachi ◽  
Shigeru Takaya ◽  
Yoshitaka Chikazawa

In this study, we develop new indices that evaluate the response capability — response margin and response reliability — of a nuclear power plant in case of occurrence of a severe accident by considering the ability of the nuclear power plant to recover system safety functions, which may have been affected by the accident, to the minimum safety values. Further, we demonstrate a specific evaluation procedure for our proposed indices. While performing the evaluation, we consider margins with respect to a minimum safety function level and a time constraint along with their temporal changes. Additionally, for a simplified fast reactor (FR) plant model, we conduct a trial assessment of the recovery capacity of the system to ensure system safety based on the concept of new indices. Further, the applicability of the response reliability evaluation method to FR plants is discussed based on the viewpoints of reflecting the characteristics of each reactor type.


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