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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
J. C. Rook, K. P. Weber, E. C. Corcoran
Nuclear Technology | Volume 206 | Number 12 | December 2020 | Pages 1861-1874
Technical Paper | doi.org/10.1080/00295450.2020.1720557
Articles are hosted by Taylor and Francis Online.
For irradiation experiments (e.g., of per- and polyfluoroalkyl substances), values of nuclear particle flux and absorbed dose rates were obtained for the Safe LOW-POwer Kritical Experiment-2 (SLOWPOKE-2) nuclear reactor at the Royal Military College of Canada using extensive simulations of the reactor core via the Monte Carlo N-Particle code, version 6 (MCNP6). Calculations from this work were compared to data from previously conducted experimental and simulation work to ensure simulation fidelity. In addition, reactor core burnup calculations were conducted using the fuel-depletion capability in MCNP6.1 to address the 30+ years of SLOWPOKE-2 reactor use. The combined absorbed dose rate in the inner irradiation sites was simulated to be 36 ± 1 kGy h−1 at a 10-kW(thermal) power setting, specifically, 20 ± 6 kGy h−1 from neutrons and 16 ± 5 kGy h−1 from photons.