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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
B.V. Robouch (guest), V.I. Volosov, A.A. Ivanov, Yu.A. Tsidulko, L. Ingrosso, J.S. Brzosko
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 228-232
Oral Presentations | doi.org/10.13182/FST99-A11963857
Articles are hosted by Taylor and Francis Online.
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 nDT-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.
