"Nuclear PWR core" trang 1 - tải miễn phí từ tailieuXANH
Verification and validation of STREAM/RAST-K for PWR analysis

Verification and validation of STREAM/RAST-K for PWR analysis
13    45    0
Investigation of burst pressures in pwr primary pressure boundary components

Investigation of burst pressures in pwr primary pressure boundary components
10    201    0
Propagation of nuclear data uncertainties for pwr core analysis

Propagation of nuclear data uncertainties for pwr core analysis
14    54    0
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing

Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
11    42    0
Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/ 152 welds in simulated PWR primary water

Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/ 152 welds in simulated PWR primary water
10    66    0
ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions
8    69    0
Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup

Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup
10    36    0
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    60    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    55    0
Low-frequency modes in the fluid-structure interaction of a U-tube model for the steam generator in a PWR

Low-frequency modes in the fluid-structure interaction of a U-tube model for the steam generator in a PWR
9    57    0
Reactivity feedback effect on loss of flow accident in PWR

Reactivity feedback effect on loss of flow accident in PWR
12    40    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    57    0
Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core

Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core
9    45    0
Recent improvements in the cupid code for a multi dimensional two-phase flow analysis of nuclear reactor components

Recent improvements in the cupid code for a multi dimensional two-phase flow analysis of nuclear reactor components
12    72    0
Evaluation of relevant information for optimal reflector modeling through data assimilation procedures

Evaluation of relevant information for optimal reflector modeling through data assimilation procedures
8    219    0
Preliminary analysis of an integral Small Modular Reactor operating in a submerged containment

Preliminary analysis of an integral Small Modular Reactor operating in a submerged containment
10    5    1
Analysis of flammability in the attached buildings to containment under severe accident conditions

Analysis of flammability in the attached buildings to containment under severe accident conditions
16    6    1
Studies on some of mechanical properties of SS304L material under different heat treatment conditions

Studies on some of mechanical properties of SS304L material under different heat treatment conditions
9    41    0
Pin to pin neutron flux reconstruction in a PWR reactor using support vector regression (SVR) technique

Pin to pin neutron flux reconstruction in a PWR reactor using support vector regression (SVR) technique
9    251    0
Measurement of the residual stresses in a PWR Control Rod Drive Mechanism nozzle

Measurement of the residual stresses in a PWR Control Rod Drive Mechanism nozzle
9    5    1
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