Novosibirsk GDT-NS Fusion Material Irradiation Facility: Neutronic Characteristics and Potentialities

The paper briefly recalls the results of previously reported numerical studies on the feasibility of protective neutron shielding of the vital parts of the Fusion Material Irradiation Facility (FMIF) Neutron Source (NS) based on the Novosibirsk Gas Dynamic Trap (GDT). The work stresses the neutronic potentialities of the facility. This mirror-type machine is designed to produce 10¹⁸D-T neutrons/s over 10 years (3×10²⁶ neutrons). Simulations use the 3DAMC-VINIA Monte Carlo code with its drizzle-shower splitting technique and two-step cascade (bilinear functional) treatment, ENDF/B6 files, and an engineering design model that precisely reproduces critical parts of the facility. The proposed shielding ensures survival of the facility, as per project tolerances, with further shield reduction and optimization possible. Present partial shield reductions around the plasma column consent 2.5m³ of irradiation space, with 0.06m³ at 0.3×10¹⁴ thermonuclear uncollided n_DT-neutrons/cm²s (0.5 MW/m²) and 0.7×10¹⁴ collided ones, axial damage gradients ⩽l%/cm over 7.8m, and ∼30 dpa in Fe-type materials at end of life.