"Nuclear models" trang 1 - tải miễn phí từ tailieuXANH
Ebook Introductory nuclear physics (2nd edition): Part 2

Ebook Introductory nuclear physics (2nd edition): Part 2
256    98    0
Development of an information reference system using reconstruction models of nuclear power plants

Development of an information reference system using reconstruction models of nuclear power plants
7    95    0
Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors
4    62    0
Lecture Physics A2: Intro to Nuclear Physics - Huynh Quang Linh

Lecture Physics A2: Intro to Nuclear Physics - Huynh Quang Linh
39    130    1
Two-way fluid-structure interaction simulation for steady-state vibration of a slender rod using URANS and LES turbulence models

Two-way fluid-structure interaction simulation for steady-state vibration of a slender rod using URANS and LES turbulence models
6    65    0
Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses

Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
10    87    0
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    21    1
Báo cáo y học:

Báo cáo y học: "The utility of pathway selective estrogen receptor ligands that inhibit nuclear factor-κB transcriptional activity in models of rheumatoid arthrits"
12    50    0
Physics in Nuclear Medicine Second Edition

Physics in Nuclear Medicine Second Edition
16    44    0
descriptions of selected accidents that have occurred at nuclear reactor

descriptions of selected accidents that have occurred at nuclear reactor
158    38    0
digital instrumentation and control systems in nuclear power plants

digital instrumentation and control systems in nuclear power plants
127    39    0
navy nuclear aircraft carrier cvn homeporting at mayport

navy nuclear aircraft carrier cvn homeporting at mayport
57    30    0
navy nuclear powered surface ships

navy nuclear powered surface ships
33    37    0
Reactivity feedback effect on loss of flow accident in PWR

Reactivity feedback effect on loss of flow accident in PWR
12    40    0
Artificial neural network surrogate development of equivalence models for nuclear data uncertainty propagation in scenario studies

Artificial neural network surrogate development of equivalence models for nuclear data uncertainty propagation in scenario studies
15    54    0
Dose and temperature distribution in spent fuel containing material

Dose and temperature distribution in spent fuel containing material
6    63    0
SMOQ: A tool for predicting the absolute residue-specific quality of a single protein model with support vector machines

SMOQ: A tool for predicting the absolute residue-specific quality of a single protein model with support vector machines
8    61    0
Inferring the physical properties of yeast chromatin through Bayesian analysis of whole nucleus simulations

Inferring the physical properties of yeast chromatin through Bayesian analysis of whole nucleus simulations
15    160    2
Analysis of the Molten salt fast reactor using reduced-order models

Analysis of the Molten salt fast reactor using reduced-order models
14    14    1
Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments
11    8    1
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