Neutron flux trang 1 tải miễn phí từ TAILIEUCHUNG

"Neutron flux" trang 1 - tải miễn phí từ Tailieuchung

Visualization of crust in metallic piping through real time neutron radiography obtained with low intensity thermal neutron flux

Visualization of crust in metallic piping through real time neutron radiography obtained with low intensity thermal neutron flux

6 74 0

Thermal neutron albedo and flux for different geometries neutron guide

Thermal neutron albedo and flux for different geometries neutron guide

6 58 0

Neutron activation analysis: Modelling studies to improve the neutron flux of AmericiumeBeryllium source

Neutron activation analysis: Modelling studies to improve the neutron flux of AmericiumeBeryllium source

5 81 0

Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel

Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel

6 26 3

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 42 3

Determination of thermal neutron flux distribution at rotary rack served for elemental concentration analysis using the K0-INAA method

Determination of thermal neutron flux distribution at rotary rack served for elemental concentration analysis using the K0-INAA method

10 1 1

The proposal for a new neutron imaging facility at Dalat research reactor

The proposal for a new neutron imaging facility at Dalat research reactor

10 1 1

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 55 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 36 0

Simulation of absorbed doses distribution in a polyethylene phantom for BNCT application at the Dalat research reactor

Simulation of absorbed doses distribution in a polyethylene phantom for BNCT application at the Dalat research reactor

7 47 3

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 54 0

Sensitivity analysis of core neutronic parameters in electron accelerator driven subcritical advanced liquid metal reactor

Sensitivity analysis of core neutronic parameters in electron accelerator driven subcritical advanced liquid metal reactor

9 49 0

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