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INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
Misako Ishiguro, Yuji Koshi
Nuclear Science and Engineering | Volume 80 | Number 2 | February 1982 | Pages 322-328
Technical Note | doi.org/10.13182/NSE82-A21434
Articles are hosted by Taylor and Francis Online.
Parallel computations of the finite difference approximation to the neutron diffusion equation, especially for three-dimensional problems, are investigated in anticipation of the use of high-speed vector computers such as the CRAY-1. Several general methods of solution of the seven-point formula are numerically studied from the viewpoint of the feasibility of their simultaneous calculations on vector computers. The time required for diffusion calculations can be reduced by a factor of 3 through vectorizing the inner iteration by the multidimensional ADC code. It is found that a checkerboard ordering in the overrelaxation method and a recently developed modified SLOR method avoid the degradation of convergence in vector iterations compared with traditional SOR and SLOR.