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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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
A. Badawi, A.R. Raffray, A. Ying, M.A. Abdou
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1532-1537
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29559
Articles are hosted by Taylor and Francis Online.
This paper presents an analysis of the tritium release and inventory in the US-ITER solid breeder blanket, based on the MISTRAL code. Since the effect of LiOT formation and precipitation at low temperature can be quite important in Li2O, the selected solid breeder for the blanket, these processes have to be accounted for in the calculations. A simple way of estimating the LiOT precipitation as a function of temperature and moisture partial pressure was added to MISTRAL by including the calculations of T2O, H2O and HTO concentrations in the pore, in addition to T2, H2 and HT. The analysis was carried out for both steady state and transient cases. The transient cases are based on the given burn and dwell times during the Physics and Technology Phases and the corresponding temperature profile and tritium generation history in the solid breeder region. For the steady state case, a tradeoff analysis is done for the helium purge flow rate, based on an acceptable tritium inventory which imposes a lower limit on the purge flow rate and an acceptable purge pressure drop which imposes a higher limit on the purge flow rate.