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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
B. A. Worley, R. Q. Wright, F. G. Pin, W. V. Harper
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 180-191
Technical Paper | doi.org/10.13182/NSE86-A27452
Articles are hosted by Taylor and Francis Online.
An application of an automated procedure called GRESS for adding derivative-taking capability to FORTRAN computer codes is presented. The efficiency and usefulness of GRESS for enhancing the point depletion and radioactive decay code ORIGEN2 are discussed. A new version of ORIGEN2 is now available that has the capability of calculating first derivatives and sensitivities of any variable in the code with respect to any other variable. The capabilities of the enhanced version, ORIGEN2G, are exemplified by its use in a sensitivity study of a high-level nuclear waste disposal problem. By using GRESS, the enhanced version ORIGEN2G was produced, tested, and verified in 2 man-months compared to an estimated 1 to 2 man-yr of effort to program a code with comparable capabilities.
