"nuclear reactor vessel water level prediction during severe accidents" trang 3 - tải miễn phí từ tailieuXANH
Development of an evaluation method for nuclear fuel debrisefiltering performance

Development of an evaluation method for nuclear fuel debrisefiltering performance
7    166    0
Development of earthquake instrumentation for shutdown and restart criteria of the nuclear power plant using multivariable decision-making process

Development of earthquake instrumentation for shutdown and restart criteria of the nuclear power plant using multivariable decision-making process
9    77    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
Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves

Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves
9    79    0
Application of particle filtering for prognostics with measurement uncertainty in nuclear power plants

Application of particle filtering for prognostics with measurement uncertainty in nuclear power plants
10    68    0
Special issue on the International Symposium on Future Instrumentation and Control for Nuclear Power Plants (ISOFIC2017)

Special issue on the International Symposium on Future Instrumentation and Control for Nuclear Power Plants (ISOFIC2017)
1    92    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
Big Data Analysis of Public Acceptance of Nuclear Power in Korea

Big Data Analysis of Public Acceptance of Nuclear Power in Korea
5    214    0
Unsteady heat exchange at the dry spent nuclear fuel storage

Unsteady heat exchange at the dry spent nuclear fuel storage
6    67    0
Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants

Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants
9    81    0
Neutron and gamma-ray energy reconstruction for characterization of special nuclear material

Neutron and gamma-ray energy reconstruction for characterization of special nuclear material
4    81    0
U.s. fuel cycle technologies R&D program for next generation nuclear materials management

U.s. fuel cycle technologies R&D program for next generation nuclear materials management
8    72    0
Wavelet operator for multiscale modeling of a nuclear reactor

Wavelet operator for multiscale modeling of a nuclear reactor
11    82    0
Review of the regulatory periodic inspection system from the viewpoint of defense-in-depth in nuclear safety

Review of the regulatory periodic inspection system from the viewpoint of defense-in-depth in nuclear safety
9    68    0
Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
8    64    0
Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site

Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
9    64    0
Development of the nuclear safety trust indicator

Development of the nuclear safety trust indicator
5    153    0
Radioactive iodine analysis in environmental samples around nuclear facilities and sewage treatment plants

Radioactive iodine analysis in environmental samples around nuclear facilities and sewage treatment plants
9    67    0
Processing and benchmarking of evaluated nuclear data file/b-viii.0b4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

Processing and benchmarking of evaluated nuclear data file/b-viii.0b4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016
7    59    0
Korean students’ behavioral change toward nuclear power generation through education

Korean students’ behavioral change toward nuclear power generation through education
12    53    0
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