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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 367-395
Technical Paper | Fuel | doi.org/10.13182/NT72-A31203
Articles are hosted by Taylor and Francis Online.
Two instrumented fuel assemblies, containing Zircaloy-clad UO2 fuel, namely IF A-132 (pellet, 95% TD, 10.0 wt% 235U) and IFA-133 (vibrocompacted powder, 85% TD, 10.0 wt% 235U) were irradiated in the Halden Boiling Water Reactor (HBWR) in Norway, in order to investigate the performance of fuel pins under central melting conditions; the maximum linear heat generation rate (LHGR) was about 1400 W/cm and the final burnup was 11 000 MWd/MTU. The initial molten zone covered about 35 and 65% of the fuel radius for the pelleted and vibrocompacted fuel, respectively. By means of the in-pile instrumentation, the dimensional changes vs generated power were recorded during irradiation. Furthermore through extensive postirradiation examinations the in-pile behavior of fuel and cladding was evaluated. In spite of incipient burnout condition, contact of molten or plastic fuel with the cladding, and localized overheating up to 900°C, the overall behavior gave no indication that irradiation to a higher burnup could not proceed satisfactorily. On the basis of this experiment it seems justified to assume that central fuel melting should not be considered as a primary constraint in the fuel design criteria.