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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.
I. Soares, W. F. Miller, Jr., R. T. Perry
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 160-167
Technical Note | doi.org/10.13182/NSE93-A24028
Articles are hosted by Taylor and Francis Online.
The viability of the use of the ONEDANT discrete ordinates code for the calculation of the Doppler coefficient of reactivity for a pressurized water reactor is investigated. The ONEDANT results are compared with benchmark results from a Monte Carlo code, MCNP-3A. A comparison with the results obtained using the CELL-2 and WIMS-AECL codes is also included. The influences of certain variables, such as spatial mesh, SN angular quadrature order, interaction convergence criterion, boundary conditions, PN order, and number of energy groups, are analyzed. An alternative benchmark calculation to the Monte Carlo result is attempted to provide some feel for the approximate accuracy of the Monte Carlo calculation. Such an alternative answer is important when less approximate methods are compared with these results.