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GAIN makes diverse selections for its third round of awards this year
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear has recently awarded four third-round fiscal year 2026 vouchers to support the development of innovative nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards Idaho National Laboratory, Oak Ridge National Laboratory, and Sandia National Laboratories are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
K. Oishi, Y. Ikeda, C. Konno, H. Maekawa, T. Nakamura
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 579-584
Fusion Nucleonics Experiments | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24806
Articles are hosted by Taylor and Francis Online.
Irradiation of concrete aggregates by 14 MeV neutrons was performed to investigate the activation characteristics of concrete, and to verify the calculation code system THIDA using the FNS facility. From the result it was proven that 42K, 24Na, 43K, 48Sc, 47Ca, 46Sc, and 54Mn, in half life order, make an important contribution to the total activity. In addition, a comparison between experiment and calculation was made. For 24Na and 54Mn, whose cross sections were well estimated, good agreement between experiment and calculation was obtained, which proved the validity of the calculational code. For reaction rates caused by calcium and titanium isotopes, however, calculational results that differed from experimental ones between −20 % to +40 % were obtained. This inconsistency was caused by the uncertainty of the cross section around 14 MeV, because the incident neutron energy was almost 14 MeV. Cross section measurements around 14 MeV of these reactions were performed systematically. Since all samples, except 48Ca, were separated isotopes and were irradiated in the same irradiation field, highly precise data with small relative error could be obtained. Consequently, calculations were performed again using measured cross section values, and then agreement between experiment and calculation was improved with ± 10 %.