"neutron absorbing materials" trang 3 - tải miễn phí từ tailieunhanh
Measurement of thermal neutron capture cross section and resonance integral for the 45Sc(n, γ)46Sc reaction with pulsed neutrons

Measurement of thermal neutron capture cross section and resonance integral for the 45Sc(n, γ)46Sc reaction with pulsed neutrons
9    70    1
Khảo sát thông lượng Neutron nhiệt của lò phản ứng hạt nhân Opr1000 với hệ mô phỏng Cosi Opr1000

Khảo sát thông lượng Neutron nhiệt của lò phản ứng hạt nhân Opr1000 với hệ mô phỏng Cosi Opr1000
11    115    0
Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors

Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors
10    100    0
Performance evaluation of METAMIC neutron absorber in spent fuel storage rack

Performance evaluation of METAMIC neutron absorber in spent fuel storage rack
6    59    0
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
Sensitivity analyses of the use of different neutron absorbers on the main safety core parameters in mtr type research reactor

Sensitivity analyses of the use of different neutron absorbers on the main safety core parameters in mtr type research reactor
8    68    0
Study of core support barrel vibration monitoring using ex core neutron noise analysis and fuzzy logic algorithm

Study of core support barrel vibration monitoring using ex core neutron noise analysis and fuzzy logic algorithm
11    69    0
Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor

Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor
8    72    0
Dose Calculation and Measurement from B10(n, α)Li7 Reaction Using Filtered Neutron Beam at Nuclear Research Institute

Dose Calculation and Measurement from B10(n, α)Li7 Reaction Using Filtered Neutron Beam at Nuclear Research Institute
7    48    0
Characterization of an 241Am-Be neutron irradiation facility at Institute for Nuclear Science and Technology

Characterization of an 241Am-Be neutron irradiation facility at Institute for Nuclear Science and Technology
9    101    0
Calculation of response functions for cylindrical nested neutron spectrometer

Calculation of response functions for cylindrical nested neutron spectrometer
5    71    3
Resolution-elastic neutron scattering by correlation techniques

Resolution-elastic neutron scattering by correlation techniques
8    69    0
Characteristics of simulated workplace neutron standard fields

Characteristics of simulated workplace neutron standard fields
8    58    0
Integrated cross sections of the photo-neutron reactions induced on 197AU with 60 mev bremsstrahlung

Integrated cross sections of the photo-neutron reactions induced on 197AU with 60 mev bremsstrahlung
11    71    0
Template for estimating uncertainties of measured neutron-induced fission cross-sections

Template for estimating uncertainties of measured neutron-induced fission cross-sections
9    83    0
Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems

Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems
17    96    0
Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources

Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources
9    52    0
Khóa luận tốt nghiệp Kỹ sư kỹ thuật hạt nhân: Tính toán thiết kế hệ phổ kế neutron xếp lồng và phát triển kỹ thuật định liều neutron dựa trên phương pháp trí tuệ nhân tạo

Khóa luận tốt nghiệp Kỹ sư kỹ thuật hạt nhân: Tính toán thiết kế hệ phổ kế neutron xếp lồng và phát triển kỹ thuật định liều neutron dựa trên phương pháp trí tuệ nhân tạo
51    177    4
A review of nuclear data for the k0-based neutron activation analysis

A review of nuclear data for the k0-based neutron activation analysis
6    36    2
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