Safety and cost analysis of a 1000 MWe sodium cooled fast power reactor

Safety and cost analysis of a 1000 MWe sodium cooled fast power reactor PDF Author: Dieter Smidt (Physicien nucléaire, Allemagne)
Publisher:
ISBN:
Category :
Languages : de
Pages :

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Safety and cost analysis of a 1000 MWe sodium cooled fast power reactor

Safety and cost analysis of a 1000 MWe sodium cooled fast power reactor PDF Author: Dieter Smidt (Physicien nucléaire, Allemagne)
Publisher:
ISBN:
Category :
Languages : de
Pages :

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Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor: Research and development program

Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor: Research and development program PDF Author: North American Aviation. Atomics International Division
Publisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages : 82

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Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor: Methods development

Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor: Methods development PDF Author: North American Aviation. Atomics International Division
Publisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages : 192

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Safety of Sodium-Cooled Fast Reactors

Safety of Sodium-Cooled Fast Reactors PDF Author: Songbai Cheng
Publisher: Springer Nature
ISBN: 9811661162
Category : Science
Languages : en
Pages : 313

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Book Description
This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems. Its safety is a critical issue during its R&D process. The book elaborates on research progresses in particle bed-related phenomena in terms of the molten-pool mobility, the molten-pool sloshing motion, the debris bed formation behavior, and the debris bed self-leveling behavior. The book serves as a good reference for researchers, professionals, and postgraduate students interested in sodium-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and light water reactors.

Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor

Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor PDF Author:
Publisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages :

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Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor

Feasibility Study of a 1000-Mwe Sodium-cooled Fast Reactor PDF Author: D. T. Eggen
Publisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages :

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Methods, System Optimization, and Safety Studies for a 1000 MWe Sodium-cooled Fast Reactor

Methods, System Optimization, and Safety Studies for a 1000 MWe Sodium-cooled Fast Reactor PDF Author: P. M. Murphy
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages :

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An Evaluation of Steam-cooled Fast Breeder Reactors

An Evaluation of Steam-cooled Fast Breeder Reactors PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 378

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The Industrial Sodium Cooled Fast Reactor

The Industrial Sodium Cooled Fast Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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This paper investigates the use of enrichment and moderator zoning methods for optimizing the r-z power distribution within sodium cooled fast reactors. These methods allow overall greater fuel utilization in the core resulting in more fuel being irradiated near the maximum allowed thermal power. The peak-to-average power density was held to 1.18. This core design, in conjunction with a multiple-reheat Brayton power conversion system, has merit for producing an industrial level of electrical output (2400MWth, 1000MWe) from a relatively compact core size. The total core radius, including reflectors and shields, was held to 1.78m. Preliminary safety analysis suggests that positive reactivity insertion resulting from a leak between the sodium primary loop and helium power conversion system can be mitigated using simple gas-liquid centripetal separation strategies in the plant's primary loop.

An Innovative Hybrid Loop-Pool SFR Design and Safety Analysis Methods

An Innovative Hybrid Loop-Pool SFR Design and Safety Analysis Methods PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
Investment in commercial sodium cooled fast reactor (SFR) power plants will become possible only if SFRs achieve economic competitiveness as compared to light water reactors and other Generation IV reactors. Toward that end, we have launched efforts to improve the economics and safety of SFRs from the thermal design and safety analyses perspectives at Idaho National Laboratory. From the thermal design perspective, an innovative hybrid loop-pool SFR design has been proposed. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to further improve economics and safety. From the safety analyses perspective, we have initiated an effort to develop a high fidelity reactor system safety code.