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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
H. W. Kugel, C. W. Barnes, J. Gilbert, J. Greco, K. W. Hill, D. L. Jassby, L. C. Johnson, L. P. Ku, J. Levine, R. W. Motley, J. D. Strachan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1989-1995
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29633
Articles are hosted by Taylor and Francis Online.
Radiation measurements were made during recent high power, high neutron yield experiments, and used to calibrate the neutronics simulation of the radiation shielding system. The results indicate that the present radiation shielding is more effective than predicted by the initial design estimates. This is attributed to the effects of changes in the experimental configuration since the initial design and to the design margin included to accommodate initial uncertainties in material properties and distributions. With the present radiation shielding, the production of 5 × 1020 D-T neutrons/yr will result in a total annual dose equivalent at the PPPL property line of less than the 10 mrem/yr design objective.
