Завдання:
The objective of this WP is to collect information about the influence of basalt-boron fiber for neutron radiation shielding properties of concrete in case of different fiber dosages, different boron concentrations in basalt fiber and different B-10 enrichment in basalt fiber.
The modelling will be performed at the computing cluster of the UT High Performance Computing Center (Rocket and Vedur clusters)
Expected results and deliverables:
- Setting up computational models to calculate the attenuation of neutrons by GEANT4 and Serpent modelling codes;
- Preparation of different neutron energy spectra;
- Calculation of neutron transport for selected composite materials (with different fiber dosages, different boron content in basalt fiber and different boron enrichment in basalt fiber) by Serpent code;
- Calculation of neutron transport for selected composite materials (with different fiber dosages, different boron content in basalt fiber and different boron enrichment in basalt fiber) by GEANT4 code;
- Analysis of obtained results;
Current status:
- Models for neutron radiation shielding calculations with different source energy spectra have prepared in Serpent code.
- Calculation of neutron transport for selected composite materials (with different fiber dosages, different boron content in basalt fiber) by Serpent code have carried out.
- Recommendations for optimum content of proposed composite material from viewpoint of industrial implementation have prepared.
The spectrum of neutrons in detector (fission neutrons of U-235 after water layer).