"neutron absorbing materials" trang 13 - tải miễn phí từ tailieunhanh
Sensitivity and uncertainty analysis of beff for MYRRHA using a Monte Carlo technique

Sensitivity and uncertainty analysis of beff for MYRRHA using a Monte Carlo technique
7    97    0
Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
15    86    0
Development and validation of uncertainty neutron transport calculations at an industrial scale

Development and validation of uncertainty neutron transport calculations at an industrial scale
6    99    0
Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments

Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments
9    110    0
From fission yield measurements to evaluation: status on statistical methodology for the covariance question

From fission yield measurements to evaluation: status on statistical methodology for the covariance question
7    101    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
Breed-and-burn fuel cycle in molten salt reactors

Breed-and-burn fuel cycle in molten salt reactors
10    71    0
Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation

Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation
19    78    0
Reflector features and physics consideration issued from the Jules Horowitz Reactor design analyses

Reflector features and physics consideration issued from the Jules Horowitz Reactor design analyses
8    62    0
Beam dynamics and electromagnetic studies of a 3 MeV, 325 MHz radio frequency quadrupole accelerator

Beam dynamics and electromagnetic studies of a 3 MeV, 325 MHz radio frequency quadrupole accelerator
17    64    0
The characterization of radioactive waste: a critical review of techniques implemented or under development at CEA, France

The characterization of radioactive waste: a critical review of techniques implemented or under development at CEA, France
24    90    0
Monte Carlo MSM correction factors for control rod worth estimates in subcritical and near-critical fast neutron reactors

Monte Carlo MSM correction factors for control rod worth estimates in subcritical and near-critical fast neutron reactors
9    46    0
New composite material based on heavy concrete reinforced by basalt-boron fiber for radioactive waste management

New composite material based on heavy concrete reinforced by basalt-boron fiber for radioactive waste management
8    70    0
Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations
11    69    0
Towards spatial kinetics in a low void effect sodium fast reactor: core analysis and validation of the TFM neutronic approach

Towards spatial kinetics in a low void effect sodium fast reactor: core analysis and validation of the TFM neutronic approach
14    77    0
Correlation n¯¯p − s − x in the fast neutron range via integral information

Correlation n¯¯p − s − x in the fast neutron range via integral information
8    100    0
Nghiên cứu lý thuyết và thực nghiệm mật độ mức và hàm lực bức xạ của hạt nhân nguyên tử tại Việt Nam

Nghiên cứu lý thuyết và thực nghiệm mật độ mức và hàm lực bức xạ của hạt nhân nguyên tử tại Việt Nam
8    99    1
Tạp chí Khoa học và Công nghệ hạt nhân: Số 63/2020

Tạp chí Khoa học và Công nghệ hạt nhân: Số 63/2020
46    106    1
Xác định hàm chuẩn tuyến tính phân tích boron trong mẫu bằng hệ phổ kế PGNAA

Xác định hàm chuẩn tuyến tính phân tích boron trong mẫu bằng hệ phổ kế PGNAA
8    73    1
Phát triển phương pháp chuẩn nội trong phân tích kích hoạt Neutron tại lò phản ứng hạt nhân Đà Lạt

Phát triển phương pháp chuẩn nội trong phân tích kích hoạt Neutron tại lò phản ứng hạt nhân Đà Lạt
11    65    3