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NRC grants license for TRISO-X fuel manufacturing using HALEU
The Nuclear Regulatory Commission has granted X-energy subsidiary TRISO-X a special nuclear material license for high-assay low-enriched uranium fuel fabrication. The license applies to TRISO-X’s first two planned commercial facilities, known as TX-1 and TX-2, for an initial 40-year period. The facilities are set to be the first new nuclear fuel fabrication plants licensed by the NRC in more than 50 years.
Apil Tamang, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE13-42
Articles are hosted by Taylor and Francis Online.
We present a computational method for adequate and efficient coupling of the multigroup neutron transport equation with the precursor and heat transfer equations. It is based on the multilevel nonlinear quasi-diffusion (QD) method for solving the multigroup transport equation. The system of equations includes the time-dependent high-order transport equation and time-dependent multigroup and effective one-group low-order QD equations. We also apply the α-approximation for the time-dependent high-order transport equation. This approach enables one to avoid storing the angular flux from the previous time step. Numerical results for model transient problems are presented.