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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.
R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, T. A. Gabriel
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 278-289
Technical Paper | doi.org/10.13182/NSE90-A19192
Articles are hosted by Taylor and Francis Online.
The Monte Carlo codes MORSE and MCNP have been used to calculate the tritium production from ≈ 14-MeV neutron reactions in a Li2O assembly. Tritium production from neutron reactions with 6Li and 7Li nuclei were calculated along the central axis of a 0.60-m-diam × 0.60-m-long assembly and four additional assemblies where sheets of Type 304 stainless steel and polyethylene were placed in front of the Li2O to simulate first-wall and coolant materials. The calculated data are compared with measured data obtained at the Fusion Neutron Source at the Japan Atomic Energy Research Institute. The calculated data reproduce the measured data in shape, but differ from the measured data by 10 to 20% in the case of 6Li and as much as 30% at some spatial locations for the 7Li tritium production.
