Sodium cooled fast reactor trang 1 tải miễn phí từ TAILIEUCHUNG

"Sodium cooled fast reactor" trang 1 - tải miễn phí từ Tailieuchung

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

5 87 0

Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor

Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor

12 67 0

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

8 71 0

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

13 55 0

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

12 78 0

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

9 59 0

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

10 84 0

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

13 69 0

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

6 45 0

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

8 34 3

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

11 81 0

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

7 58 0

Characteristics of a gas-cooled fast reactor with minor actinide loading

Characteristics of a gas-cooled fast reactor with minor actinide loading

9 78 0

An experimental study on pool sloshing behavior with solid particles

An experimental study on pool sloshing behavior with solid particles

11 72 0

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

12 60 0

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