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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.
William P. Kelleher, J. Wiley Davidson, Gary R. Thayer, Donald J. Dudziak
Fusion Science and Technology | Volume 17 | Number 3 | May 1990 | Pages 466-475
Technical Note | Shielding | doi.org/10.13182/FST90-A29221
Articles are hosted by Taylor and Francis Online.
A radiation shielding analysis was performed on the Confinement Physics Research Facility (CPRF) under construction at Los Alamos National Laboratory. A reversed-field pinch device, the ZTH, was examined in an effort to obtain an estimate of the spatial distribution of the dose seen by both personnel and electronic components. In the Monte Carlo transport analysis, the MCNP code was used to estimate the neutron and gamma-ray doses and differential flux (in energy) spectra at ten locations within the CPRF. The complex geometry of the ZTH dictated that the problem be solved in a two-step process: First, a cylindrical surface source enclosing the ZTH was computed, and then this source was used as the radiation source for the CPRF building calculations. Using a source strength of 1015 neutrons, identical calculations were performed for both deuterium-deuterium and deuterium-tritium fusion plasmas.