A summarized update of neutronic studies on the Novosibirsk Gas Dynamic Trap (GDT) fusion material irradiation facility (FMIF) is presented. The GDT-FMIF neutron source project is based on a mirror-type machine designed to produce 1018D-T neutrons/s over 10 yr (3 × 1026neutrons). The proposed massive shielding, susceptible to further shield reductions and optimization, ensures proper shielding against radiation and/or heat overdeposition in accordance with project tolerances. The present shield configuration allows 3.3 m3of irradiation space around the plasma column: 0.06 m3receives 0.3 × 1014thermonuclear uncollided 14-MeV nDT-neutrons/cm2· s (0.5 MW/m2), and 0.7 × 1014with collision degraded energies (∼0.7 MW/m2total), over 7 of the 8 m of intense flux axial length, the largest non-tokamak availability. This allows the irradiation of large (up to 4.5 m long) life-size components (such as welds). The delivered neutron flux relative-gradients are small (< 6.3%/cm). Simulations use the 3DAMC-VINIA Monte Carlo code in its expanded version (drizzle-shower technique, two-step cascade, etc.), ENDF/B6 and EPDL nuclear data files, and a precise model of critical parts of the GDT. Results demonstrate that the GDT-FMIF is a very suitable irradiation test facility as per International Energy Agency specifications for an FMIF. With its 37.5-cm free depth of test space, GDT is the only dedicated facility suitable for a life-size blanket-tritium-breeding/ extraction benchmark at a significant neutron flux level (2 MW/m2).
|Pages (from-to)||44 - 51|
|Number of pages||8|
|Journal||Fusion Science and Technology|
|Publication status||Published - Jan 2002|
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Robouch, B. V., Volosov, V. I., Ivanov, A. A., Tsidulko, Y. A., Zouev, Y. N., Ingrosso, L., & Brzosko, J. S. (2002). Neutronic characteristics of the Novosibirsk GDT-NS fusion material irradiation facility. Fusion Science and Technology, 41(1), 44 - 51.