Fuel design trang 1 tải miễn phí từ TAILIEUCHUNG

"Fuel design" trang 1 - tải miễn phí từ Tailieuchung

Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes

Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes

12 64 0

Computational design and characterization of a subcritical reactor assembly with TRIGA fuel

Computational design and characterization of a subcritical reactor assembly with TRIGA fuel

8 67 0

FUEL CELLS Problems and Solutions

FUEL CELLS Problems and Solutions

394 50 0

Fuel Cell Handbook

Fuel Cell Handbook

352 61 1

Structural integrity assessment and stress measurement of chasnupp-1 fuel assembly skeleton: under tensile loading condition

Structural integrity assessment and stress measurement of chasnupp-1 fuel assembly skeleton: under tensile loading condition

6 80 0

Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant

Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant

5 1 1

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

11 1 1

Neutronic design of a PWR fuel assembly with accident tolerant-composite fuel using SRAC code

Neutronic design of a PWR fuel assembly with accident tolerant-composite fuel using SRAC code

12 1 1

Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design

Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design

6 41 3

Ebook Design of automotive engines

Ebook Design of automotive engines

430 79 1

Neutronic analysis of fuel design for the long-life core in a pressurized water reactor

Neutronic analysis of fuel design for the long-life core in a pressurized water reactor

7 2 1

Comparison of deterministic and stochastic depletions in graphite-filled mox fuel assembly design

Comparison of deterministic and stochastic depletions in graphite-filled mox fuel assembly design

10 37 1

Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing

Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing

11 1 1

Effect of heat transfer correlations on the fuel temperature prediction of SCWRs

Effect of heat transfer correlations on the fuel temperature prediction of SCWRs

11 50 0

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance

6 52 0

CANDU-6 fuel optimization for advanced cycles

CANDU-6 fuel optimization for advanced cycles

14 2 1

Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel

Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel

10 2 1

Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations

Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations

7 1 1

Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system

Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system

9 1 1

Infrared observation of ballooning and burst of nuclear fuel cladding tubes

Infrared observation of ballooning and burst of nuclear fuel cladding tubes

9 1 1

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