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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.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Hanford completes wastewater basin work to support tank waste treatment
Record-breaking heat and the vast size of the job did not stop the Department of Energy’s Office of River Protection and its tank operations contractor, Washington River Protection Solutions (WRPS), from completing a construction project critical to the Hanford Site’s Direct-Feed Low-Activity Waste program for treating radioactive tank waste.
B. H. Mills, B. Zhao, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 541-545
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-116
Articles are hosted by Taylor and Francis Online.
A new helium (He) loop was used to study the helium-cooled modular divertor with multiple jets (HEMJ) at incident heat fluxes q″ ≤ 6.6 MW/m2 as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). These studies were performed at prototypical pressures of 10 MPa and inlet temperatures ranging from 30 °C to 300 °C. The effect of varying the distance between the inner jets cartridge and the outer shell from 0.44 to 0.9 mm was also investigated.
The Nusselt number Nu results for two different tungsten-alloy test sections were in good agreement for q″ = 1.5−6.6 MW/m2. The experiments also suggest that the loss coefficient KL is essentially constant. These Nu and KL results were used to estimate the maximum heat flux q′′max that can be accommodated by the divertor under prototypical conditions and the coolant pumping power as a fraction of the incident thermal power β. The agreement over the broad range of experimental parameters studied suggests that these results at near-prototypical conditions can be extrapolated with reasonable confidence to the operating conditions expected for the HEMJ design.