"Sodium cooled Fast Reactor Safety" trang 1 - tải miễn phí từ tailieunhanh
Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor

Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
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Safety aspects of intermediate heat transport and decay heat removal systems of sodium cooled fast reactors

Safety aspects of intermediate heat transport and decay heat removal systems of sodium cooled fast reactors
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Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor

Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor
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Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance

Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
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Metal fuel development and verification for prototype generation IV sodium-cooled fast reactor

Metal fuel development and verification for prototype generation IV sodium-cooled fast reactor
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Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea

Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea
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Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour

Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour
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On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor
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Drop performance test of conceptually designed control rod assembly for prototype generation iv sodium cooled fast reactor

Drop performance test of conceptually designed control rod assembly for prototype generation iv sodium cooled fast reactor
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On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes

On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes
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The investigation of burnup characteristics using the serpent monte carlo code for a sodium cooled fast reactor

The investigation of burnup characteristics using the serpent monte carlo code for a sodium cooled fast reactor
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Evolution of the collective radiation dose of nuclear reactors from the 2nd through to the 3rd generation and 4th generation sodium-cooled fast reactors

Evolution of the collective radiation dose of nuclear reactors from the 2nd through to the 3rd generation and 4th generation sodium-cooled fast reactors
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Nuclear transmutation of long-lived fission product I-129 in radial blanket of sodium-cooled fast reactor

Nuclear transmutation of long-lived fission product I-129 in radial blanket of sodium-cooled fast reactor
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Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior

Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior
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Characteristics of a gas-cooled fast reactor with minor actinide loading

Characteristics of a gas-cooled fast reactor with minor actinide loading
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An experimental study on pool sloshing behavior with solid particles

An experimental study on pool sloshing behavior with solid particles
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Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments

Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments
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An improved method to evaluate the “Joint Oxyde-Gaine” formation in (U,Pu)O2 irradiated fuels using the GERMINAL V2 code coupled to Calphad thermodynamic computations

An improved method to evaluate the “Joint Oxyde-Gaine” formation in (U,Pu)O2 irradiated fuels using the GERMINAL V2 code coupled to Calphad thermodynamic computations
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