"nuclear reactor vessel water level prediction during severe accidents" trang 6 - tải miễn phí từ tailieuXANH
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
Distinct properties of tungsten austenitic stainless alloy as a potential nuclear engineering material

Distinct properties of tungsten austenitic stainless alloy as a potential nuclear engineering material
8    114    0
Fragility assessment for electric cabinet in nuclear power plant using response surface methodology

Fragility assessment for electric cabinet in nuclear power plant using response surface methodology
10    63    0
The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling

The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
4    49    0
A core review of nuclear medicine: Part 1

A core review of nuclear medicine: Part 1
140    267    3
A core review of nuclear medicine: Part 2

A core review of nuclear medicine: Part 2
162    306    1
Development of field programmable gate arrayebased encryption module to mitigate man-in-the-middle attack for nuclear power plant data communication network

Development of field programmable gate arrayebased encryption module to mitigate man-in-the-middle attack for nuclear power plant data communication network
8    53    0
Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO

Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO
7    57    0
Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
12    58    0
Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
17    77    0
Examination of different socioeconomic factors that contribute to the public acceptance of nuclear energy

Examination of different socioeconomic factors that contribute to the public acceptance of nuclear energy
6    73    0
Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards

Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards
11    44    0
Development of an earthquake-induced landslide risk assessment approach for nuclear power plants

Development of an earthquake-induced landslide risk assessment approach for nuclear power plants
15    49    0
Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression

Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression
8    42    0
Model-based predictions for nuclear excitation functions of neutron-induced reactions on 64,6668Zn targets

Model-based predictions for nuclear excitation functions of neutron-induced reactions on 64,6668Zn targets
10    69    0
An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process

An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process
17    123    0
Identification of nonregular indication according to change of grain size/surface geometry in nuclear power plant (NPP) reactor vessel (RV)-upper head alloy 690 penetration

Identification of nonregular indication according to change of grain size/surface geometry in nuclear power plant (NPP) reactor vessel (RV)-upper head alloy 690 penetration
13    46    0
Modal characteristic analysis of the apr1400 nuclear reactor internals for seismic analysis

Modal characteristic analysis of the apr1400 nuclear reactor internals for seismic analysis
10    46    0
Potentiality of using vertical and threedimensional isolation systems in nuclear structures

Potentiality of using vertical and threedimensional isolation systems in nuclear structures
15    73    0
Semisupervised classification for fault diagnosis in nuclear power plants

Semisupervised classification for fault diagnosis in nuclear power plants
11    65    2
Đã phát hiện trình chặn quảng cáo AdBlock
Trang web này phụ thuộc vào doanh thu từ số lần hiển thị quảng cáo để tồn tại. Vui lòng tắt trình chặn quảng cáo của bạn hoặc tạm dừng tính năng chặn quảng cáo cho trang web này.