Spectrum Weighting Function Method for In-Situ Fast Neutron and Gamma-Ray Response Measurements in Fusion Integral Experiments with an NE213 Scintillation Detector

1994 ◽  
Vol 26 (3P2) ◽  
pp. 1098-1102 ◽  
Author(s):  
Yukio Oyama ◽  
Kazunori Sekiyama ◽  
Hiroshi Maekawa
Keyword(s):  
Fast Neutron ◽  
Scintillation Detector ◽  
Function Method ◽  
Gamma Ray ◽  
Weighting Function

Efficient Prompt Scintillation and Fast Neutron-Gamma Ray Discrimination Using Amorphous Blends of Difluorenylsilane Organic Glass and in-situ Polymerized Vinyltoluene

2021 ◽  
pp. 1-1
Author(s):  
Nicholas R. Myllenbeck ◽  
Joseph S. Carlson ◽  
McKenzie A. Hunter ◽  
Huu M. Tran ◽  
Annabelle I. Benin ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Gamma Ray ◽  
Organic Glass

Application of a SrI2(Eu) scintillation detector to in situ gamma-ray spectrometry in the environment

2019 ◽  
Vol 122 ◽  
pp. 67-72 ◽  
Author(s):  
Young-Yong Ji ◽  
Hyun-Sock Chang ◽  
Taehyung Lim ◽  
Wanno Lee
Keyword(s):  
Scintillation Detector ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry

scholarly journals In-situ gamma-ray background measurements for next generation CDEX experiment in the China Jinping Underground Laboratory

2021 ◽  
Vol 128 ◽  
pp. 102560
Author(s):  
H. Ma ◽  
Z. She ◽  
W.H. Zeng ◽  
Z. Zeng ◽  
M.K. Jing ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Underground Laboratory ◽  
Next Generation

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Effective Neutron ◽  
Simulation Codes

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

Gamma-ray spectrometer calibration for field analysis of thorium, uranium and potassium

1970 ◽  
Vol 7 (4) ◽  
pp. 1093-1098 ◽  
Author(s):  
P. G. Killeen ◽  
C. M. Carmichael
Keyword(s):  
Regression Analysis ◽  
Gamma Ray ◽  
Laboratory Analysis ◽  
In Situ Analysis ◽  
Field Analysis ◽  
Gamma Ray Spectrometer ◽  
Nonlinear Relation ◽  
Using Data ◽  
Spectrometer Calibration

The calibration of a portable three-channel gamma-ray spectrometer for in situ analysis of thorium, uranium, and potassium is discussed. A method of regression analysis is suggested as the best means of including all of the data available from the calibration stations. Calibration indicates a nonlinear relation between count rates obtained in the field and concentrations in parts per million obtained from laboratory analysis. The range of radioelement content must be taken into consideration and appropriate sets of calibration constants applied. As an example of the method, calibration constants are calculated for a portable gamma-ray spectrometer using data for the Blind River uranium region of Ontario.

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