"Pressurized Water Reactor Systems" trang 1 - tải miễn phí từ tailieunhanh
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
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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
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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
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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
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Antioxidant capacities of the extracts from Perilla frutescens L. leaves using pressurized liquid extraction and conventional techniques

Antioxidant capacities of the extracts from Perilla frutescens L. leaves using pressurized liquid extraction and conventional techniques
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The effect of temperature and methanol–water mixture on pressurized hot water extraction (PHWE) of anti-HIV analogoues from Bidens pilosa

The effect of temperature and methanol–water mixture on pressurized hot water extraction (PHWE) of anti-HIV analogoues from Bidens pilosa
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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
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Feasibility of pressurized irrigation in canal command area of Samrat Ashok sagar project a case study

Feasibility of pressurized irrigation in canal command area of Samrat Ashok sagar project a case study
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Pressurized Water Reactor Systems

Pressurized Water Reactor Systems
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Pressurized hot water extraction of hydrosable tannins from Phyllanthus tenellus Roxb.

Pressurized hot water extraction of hydrosable tannins from Phyllanthus tenellus Roxb.
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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
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Numerical prediction of a flashing flow of saturated water at high pressure

Numerical prediction of a flashing flow of saturated water at high pressure
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Effect of irrigation methods on yields attributes and water productivity of wheat in vertisol of betwa river basin commands of Vidisha district of M.P, India

Effect of irrigation methods on yields attributes and water productivity of wheat in vertisol of betwa river basin commands of Vidisha district of M.P, India
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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
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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
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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
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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
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A study on the core loading pattern of the VVER-1200/V491

A study on the core loading pattern of the VVER-1200/V491
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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
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Hydraulic and statistical study of metastable phenomena in PWR rod bundles

Hydraulic and statistical study of metastable phenomena in PWR rod bundles
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