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Conference Spotlight
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.
Gyuhong Roh, Hangbok Choi
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 128-151
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3134
Articles are hosted by Taylor and Francis Online.
Cell-code benchmark calculations have been performed for the standard CANDU and DUPIC CANDU fuel lattices compared with the MCNP-4B code. To consider the full isotopic composition and the temperature effect, new MCNP libraries have been generated from ENDF/B-VI release 3 and validated for typical benchmark problems. The lattice codes WIMS-AECL and HELIOS were then benchmarked by the MCNP code for the major physics parameters such as burnup reactivity, coolant void reactivity, fuel temperature coefficient, etc. The calculations have shown that the physics parameters estimated by the lattice codes are consistent with those by MCNP. However, there is a tendency that the error increases slightly when the fuel burnup is high. This study has shown that the WIMS-AECL produces reliable results for CANDU fuel analysis. However, it is recommended that the cross-section library be updated to be used for the high-burnup fuels even though the current results are generally acceptable. This study has also shown that the HELIOS code has the potential to be used for CANDU fuel lattice analysis in the future.
