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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
Latest News
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
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.
