Modelling of neutron radiation shielding properties for different concentrations of basalt-boron fiber reinforced concrete

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Objectives:

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:

  1. Setting up computational models to calculate the attenuation of neutrons by GEANT4 and Serpent modelling codes; 
  2. Preparation of different neutron energy spectra;
  3. 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;
  4. 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;
  5. Analysis of obtained results; 

Current status:

  1. Models for neutron radiation shielding calculations with different source energy spectra have prepared in Serpent code.
  2. Calculation of neutron transport for selected composite materials (with different fiber dosages, different boron content in basalt fiber) by Serpent code have carried out.
  3. Recommendations for optimum content of proposed composite material from viewpoint of industrial implementation have prepared.

Dependence the current transmission neutrons on number of layers concrete and dosage BBF for СcaBBF10.

 

The spectrum of neutrons in detector (neutrons wiht energy of 14 MeV).

The spectrum of neutrons in detector (fission neutrons of U-235 after water layer).