Pressurized water reactor trang 1 tải miễn phí từ TAILIEUCHUNG

"Pressurized water reactor" trang 1 - tải miễn phí từ Tailieuchung

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

8 52 0

Validation of computational fluid dynamics calculation using rossendorf coolant mixing model flow measurements in primary loop of coolant in a pressurized water reactor model

Validation of computational fluid dynamics calculation using rossendorf coolant mixing model flow measurements in primary loop of coolant in a pressurized water reactor model

11 70 0

Investigation of a hydrogen mitigation system during large break loss of coolant accident for a two-loop pressurized water reactor

Investigation of a hydrogen mitigation system during large break loss of coolant accident for a two-loop pressurized water reactor

10 62 0

Pressurized Water Reactor Systems

Pressurized Water Reactor Systems

24 63 0

Nonlinear control for core power of pressurized water nuclear reactors using constant axial offset strategy

Nonlinear control for core power of pressurized water nuclear reactors using constant axial offset strategy

11 45 0

Simulation for neutron transport in pwr reactor moderator and evaluation for proper thickness of light water reflector

Simulation for neutron transport in pwr reactor moderator and evaluation for proper thickness of light water reflector

6 52 0

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

A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics

A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics

15 3 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

Probabilistic assessment of structural integrity of reactor pressure vessel in severe loading conditions caused by various transients

Probabilistic assessment of structural integrity of reactor pressure vessel in severe loading conditions caused by various transients

6 1 1

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

12 58 0

Numerical prediction of a flashing flow of saturated water at high pressure

Numerical prediction of a flashing flow of saturated water at high pressure

11 51 0

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

13 56 0

Eddy current testing system for bottom mounted instrumentation welds

Eddy current testing system for bottom mounted instrumentation welds

8 93 0

Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment

Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment

11 49 0

A study on the core loading pattern of the VVER-1200/V491

A study on the core loading pattern of the VVER-1200/V491

7 39 1

Contribution to the study of ﬁssion products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation

Contribution to the study of ﬁssion products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation

10 43 0

Hydraulic and statistical study of metastable phenomena in PWR rod bundles

Hydraulic and statistical study of metastable phenomena in PWR rod bundles

7 46 0

Neutron cross section generation of PWR MOX fuel assemblies with scale and serpent

Neutron cross section generation of PWR MOX fuel assemblies with scale and serpent

5 1 1

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