Novosibirsk GDT-NS fusion material irradiation facility: Neutronic characteristics and potentialities

B.V. Robouch

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Abstract

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 (3×1026neutrons). Simulations use the 3DAMC-VINIA Monte Carlo code with its drizzleshower 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 2.5m3of irradiation space, with 0.06m3at 0.3×1014thermonuclear uncollided nDT-neutrons/cm2s (0.5 MW/m2) and 0.7×1014collided ones, axial damage gradients ≤1%/cm over 7.8m, and ∼30 dpa in Fe-type materials at end of life. Notabene-EPSand IAEA stand for.EPS: European Confon Controlled Fusion & Plasma Physics, Ed. European Physical Soc, Geneva; IAEA: Intern. Conf on plasma Physics & Controlled Nuclear Fusion Research, Ed. IAEA, Vienna.
Original languageEnglish
Pages (from-to)228 - 232
Number of pages5
JournalFusion Technology
Volume35
Issue number1 SPEC. ISS.
Publication statusPublished - 1999
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Engineering(all)

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