"analysis of nuclear reactors" trang 3 - tải miễn phí từ tailieunhanh
Application of internal mono standard neutron activation analysis method in elemental analysis of car glasses for forensic study

Application of internal mono standard neutron activation analysis method in elemental analysis of car glasses for forensic study
8    18    1
Nuclear data uncertainty and sensitivity analysis with xsusa for fuel assembly depletion calculations

Nuclear data uncertainty and sensitivity analysis with xsusa for fuel assembly depletion calculations
10    70    0
Quantitative Analysis in Nuclear Medicine Imaging

Quantitative Analysis in Nuclear Medicine Imaging
592    52    0
Solving point burnup equations by Magnus method

Solving point burnup equations by Magnus method
5    65    0
In vivo functional analysis of a nuclear restorer PPR protein

In vivo functional analysis of a nuclear restorer PPR protein
12    74    0
Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method

Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method
22    91    0
Possible in-vessel corium progression way in the Unit 1 of Fukushima Dai-ichi nuclear power plant using a phenomenological analysis

Possible in-vessel corium progression way in the Unit 1 of Fukushima Dai-ichi nuclear power plant using a phenomenological analysis
8    86    0
A mutation screening of oncogenes, tumor suppressor gene TP53 and nuclear encoded mitochondrial complex I genes in oncocytic thyroid tumors

A mutation screening of oncogenes, tumor suppressor gene TP53 and nuclear encoded mitochondrial complex I genes in oncocytic thyroid tumors
7    52    1
Combining ability for grain yield and its components involving alloplasmic iso-nuclear lines of pearl millet

Combining ability for grain yield and its components involving alloplasmic iso-nuclear lines of pearl millet
8    48    1
Molecular targets and signaling pathways regulated by nuclear translocation of syndecan-1

Molecular targets and signaling pathways regulated by nuclear translocation of syndecan-1
20    27    1
Verification of a real-time interactive transient simulator for Dalat nuclear research reactor

Verification of a real-time interactive transient simulator for Dalat nuclear research reactor
8    68    3
Sensitivity and uncertainty analysis on reactivity for HEU and LEU fuel assemblies of dalat nuclear research reactor using monte carlo code and ENDF/B-VII.0 and ENDF/B-VII.1 nuclear libraries

Sensitivity and uncertainty analysis on reactivity for HEU and LEU fuel assemblies of dalat nuclear research reactor using monte carlo code and ENDF/B-VII.0 and ENDF/B-VII.1 nuclear libraries
14    28    1
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations

Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations
25    14    1
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    16    1
On nuclear-coupled thermal-hydraulic instability analysis of Super-CriticalLight-Water-cooled-reactor (SCLWR)

On nuclear-coupled thermal-hydraulic instability analysis of Super-CriticalLight-Water-cooled-reactor (SCLWR)
20    17    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    5    1
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3

Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
12    12    1
A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel

A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel
7    17    1
Comparative analysis of the differential evolution and genetic algorithm applied to the nuclear reactor fuel reloading optimization

Comparative analysis of the differential evolution and genetic algorithm applied to the nuclear reactor fuel reloading optimization
9    13    1
Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides by Relative and Internal Monostandard Neutron Activation Analysis Methods

Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides by Relative and Internal Monostandard Neutron Activation Analysis Methods
7    86    0