scholarly journals SB3. Experiment on secondary gamma-ray production cross sections averaged over a fast-neutron spectrum for each of 13 different elements plus a stainless steel

1976 ◽  
Author(s):  
R. E. Maerker
Keyword(s):  
Stainless Steel ◽  
Fast Neutron ◽  
Neutron Spectrum ◽  
Cross Sections ◽  
Gamma Ray ◽  
Production Cross ◽  
Fast Neutron Spectrum

scholarly journals NEW VALIDATION OF SI CROSS-SECTION USING SILICA SAND

2021 ◽  
Vol 247 ◽  
pp. 10001
Author(s):  
Tomáš Czakoj ◽  
Michal Košťál ◽  
Evžen Losa ◽  
Vojtěch Rypar
Keyword(s):  
Silicon Dioxide ◽  
Fast Neutron ◽  
Neutron Spectrum ◽  
Cross Sections ◽  
Silica Sand ◽  
Spectrum Measurement ◽  
Thermal Scattering ◽  
Fast Neutron Spectrum ◽  
Validation Experiments ◽  
Criticality Safety

Silicon cross-sections, being important for a criticality safety of final spent fuel disposals, were recently reevaluated within the IAEA INDEN project. Similarly, the thermal Scattering Law matrix for silicon dioxide, which is also important for criticality safety, was also reevaluated in the ENDF/B-VIII.0 library. Due to these reasons, a series of validation experiments with silica sand were performed at the LR-0 reactor. This paper describes these validation experiments, which used two different amounts of silica sand placed in the core. The first part of validation was carried out as critical experiments in order to benefit from the suitability of integral experiments for validation. The second part -fast neutron spectrum measurement in the sand -was performed in order to obtain knowledge of its characteristics and its agreement with a calculation. The results showed significant improvement of the Thermal Scattering Law matrix for silicon dioxide available in the ENDF/B-VIII.0 library. They also showed that the new INDEN evaluation of silicon cross-sections, together with its description in the ENDF/B-VIII.0 gives disagreement rate closest to the experiments carried out without silica sand insertions. The spectrum measurement showed that the calculations of fast neutron spectra in the sand show only slight differences between different evaluations of silicon cross-sections. However, the fast neutron spectrum is not dependent on the Thermal Scattering Law. The calculated spectra show relatively good agreement with the measurement.

Gamma-Ray-Production Cross Sections for Fast Neutron Interactions with Several Elements

1970 ◽  
Vol 40 (2) ◽  
pp. 294-305 ◽  
Author(s):  
Darrell M. Drake ◽  
John C. Hopkins ◽  
C. S. Young ◽  
H. Condé
Keyword(s):  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Production Cross

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.

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