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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Benjamin V. Robouch, Vadim I. Volosov, Aleksandr A. Ivanov, Yurii A. Tsidulko, Yurii N. Zouev, Luigi Ingrosso, Jan S. Brzosko
Fusion Science and Technology | Volume 41 | Number 1 | January 2002 | Pages 44-52
Technical Paper | doi.org/10.13182/FST02-A199
Articles are hosted by Taylor and Francis Online.
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 1018 D-T neutrons/s over 10 yr (3 × 1026 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 m3 of irradiation space around the plasma column: 0.06 m3 receives 0.3 × 1014 thermonuclear uncollided 14-MeV nDT-neutrons/cm2s (0.5 MW/m2), and 0.7 × 1014 with collision degraded energies (~0.7 MW/m2 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/m2).
