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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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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Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.
