Neutronic Characteristics of the Novosibirsk GDT-NS Fusion Material Irradiation Facility

Journal Article · Tue Jan 15 04:00:00 EST 2002 · Fusion Science and Technology

OSTI ID:20845823

Robouch, Benjamin V; Volosov, Vadim I; Ivanov, Aleksandr A; Tsidulko, Yurii A; Zouev, Yurii N; Ingrosso, Luigi; Brzosko, Jan S

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 10{sup 18} D-T neutrons/s over 10 yr (3 x 10{sup 26} neutrons). 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 m{sup 3} of irradiation space around the plasma column: 0.06 m{sup 3} receives 0.3 x 10{sup 14} thermonuclear uncollided 14-MeV n{sub DT}-neutrons/cm{sup 2}.s (0.5 MW/m{sup 2}), and 0.7 x 10{sup 14} with collision degraded energies ({approx}0.7 MW/m{sup 2} total), over 7 of the 8 m of intense flux axial length, the largest nontokamak 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/m{sup 2})

• OSTI ID: 20845823
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 1 Vol. 41; ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BENCHMARKS
BREEDING BLANKETS
COMPUTERIZED SIMULATION
EXTRACTION
IRRADIATION
MEV RANGE
MONTE CARLO METHOD
NEUTRON FLUX
NEUTRON SOURCES
NEUTRONS
NUCLEAR DATA COLLECTIONS
PLASMA
SHIELDING
TEST FACILITIES
THERMONUCLEAR REACTOR MATERIALS
TRAPS
TRITIUM
WELDED JOINTS