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Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
Ken Nakajima, Masanori Akai
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 375-379
Technical Note | Fission Reactor | doi.org/10.13182/NT96-A35217
Articles are hosted by Taylor and Francis Online.
To investigate the accuracy of the neutronic calculations in various neutron spectra, the modified conversion ratios [(MCR): ratio of 238U capture rate-to-total fission rate] of four kinds of light water-moderated UO2 fuel lattices were measured. In the measurements, the relative reaction rates of 238U capture and total fission were obtained from the nondestructive gamma-ray spectrometry of 239Np and 143 Ce, respectively, which accumulated in the fuel rod irradiated at the Tank-Type Critical Assembly. The moderator-to-fuel volume ratios Vm/Vf of the measured lattices were 1.50 (undermoderate) to 3.00 (overmoderate). The measured MCRs were 0.477 ± 0.014(Vm/Vf = 1.50), 0.434 ± 0.013(1.83), 0.383 ± 0.011(2.48), and 0.356 ± 0.011(3.00), respectively. The Monte Carlo calculation employing the JENDL-3 library showed good agreement with the experiments for all the cores, although they showed a tendency of overestimation for larger values of MCR, as shown in the case of UO2 tight lattices. Therefore, it was concluded that, for the cores investigated, the accuracy of the neutronic calculation method currently used was very good.