"analysis of nuclear reactors" trang 5 - tải miễn phí từ tailieunhanh
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    71    0
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor

Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
7    80    0
Physics study of Canada deuterium uranium lattice with coolant void reactivity analysis

Physics study of Canada deuterium uranium lattice with coolant void reactivity analysis
11    74    0
Development of a computer code for thermalehydraulic design and analysis of helically coiled tube once-through steam generator

Development of a computer code for thermalehydraulic design and analysis of helically coiled tube once-through steam generator
8    82    0
Mechanical analysis of surface-coated zircaloy cladding

Mechanical analysis of surface-coated zircaloy cladding
13    52    0
Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions

Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions
7    86    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    62    0
Three dimensional analysis of temperature effect on control rod worth in TRR

Three dimensional analysis of temperature effect on control rod worth in TRR
11    84    1
OECD/NEA benchmark for uncertainty analysis in modeling (uam) for lwrs – summary and discussion of neutronics cases (phase i)

OECD/NEA benchmark for uncertainty analysis in modeling (uam) for lwrs – summary and discussion of neutronics cases (phase i)
30    65    0
On the fly estimation strategy for uncertainty propagation in two step monte carlo calculation for residual radiation analysis

On the fly estimation strategy for uncertainty propagation in two step monte carlo calculation for residual radiation analysis
8    79    0
Steam generator tube integrity analysis of a total loss of all heat sinks accident for wolsong NPP unit 1

Steam generator tube integrity analysis of a total loss of all heat sinks accident for wolsong NPP unit 1
8    96    0
Development of an alpha fast-slow coincidence counter for analysis of 223Ra and 224Ra in seawater

Development of an alpha fast-slow coincidence counter for analysis of 223Ra and 224Ra in seawater
5    84    0
Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations
11    69    0
Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module

Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module
14    68    0
Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system

Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system
10    86    0
Size matters: Three methods for estimating nuclear size in mycorrhizal roots of Medicago truncatula by image analysis

Size matters: Three methods for estimating nuclear size in mycorrhizal roots of Medicago truncatula by image analysis
14    38    1
Ki-67 is a valuable prognostic predictor of lymphoma but its utility varies in lymphoma subtypes: Evidence from a systematic meta-analysis

Ki-67 is a valuable prognostic predictor of lymphoma but its utility varies in lymphoma subtypes: Evidence from a systematic meta-analysis
13    46    1
HiCdat: A fast and easy-to-use Hi-C data analysis tool

HiCdat: A fast and easy-to-use Hi-C data analysis tool
6    53    1
Determination of thermal neutron flux distribution at the rotary rack served for elemental concentration analysis using the k0-INAA method

Determination of thermal neutron flux distribution at the rotary rack served for elemental concentration analysis using the k0-INAA method
10    58    3
Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel

Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel
6    41    3