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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.
Hiroshi Takahashi
Fusion Science and Technology | Volume 5 | Number 1 | January 1984 | Pages 72-79
Deep Penetration: Problem and Method of Solution | Special Section Contents / Shielding | doi.org/10.13182/FST84-A23080
Articles are hosted by Taylor and Francis Online.
The integral transport method, which has been used in the early calculation of a beam hole tube in an experimental reactor and many reactor parameters of a power reactor; has been reviewed. The Generalized First-Flight Collision Probability (GFFCP) method, based on the integral transport equation, and the discrete ordinates method, based on the differential transport equation, are compared in the context of the deep penetration problem. The direct integral method derived from the partial integral transport equation, which eliminates many of the drawbacks of the GFFCP method, is discussed. A method similar to the GFFCP method, which needs spherical harmonics expansion instead of the discrete ordinates scheme, is presented. The future of these analytical methods is discussed in the comparison with the straight numerical method based on the differential transport calculation and the Monte Carlo calculation.