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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.
Heba Louis, Esmaat Amin, Moustafa Aziz, Ibrahim Bashter
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 61-65
Technical Paper | doi.org/10.13182/NSE11-11
Articles are hosted by Taylor and Francis Online.
The accelerator-driven system (ADS) is an innovative reactor that is being considered as a dedicated high-level-waste burner in a double-strata fuel cycle. (“Double-strata fuel cycle” means a partitioning and transmutation system for long-lived radioactive nuclides.) The target is the physical and functional interface between the accelerator and the subcritical reactor in the ADS, so it is probably the most innovative component of the ADS. Key parameters of ADS are the number of neutrons emitted per incident proton, the neutron multiplicity (n/p), the mean energy deposited in the target for neutrons produced, the neutron energy spectrum, and the spallation product spatial distribution. This paper focuses on the production of neutrons in the spallation reactions. The neutrons produced in the spallation reactions can be characterized by their energy and spatial distributions and multiplicity. The present calculations have been performed using the Monte Carlo code MCNPX. The Monte Carlo simulations have been performed to investigate the neutron multiplicity as a function of incident proton beam energy, as well as a function of target material and target size. Neutron flux distributions at the target surface are calculated and compared with different target materials and proton energies. A comparison of MCNPX with experimental results is made.