ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
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.
Itsuro Kimura, Katsuhei Kobayashi
Nuclear Science and Engineering | Volume 106 | Number 3 | November 1990 | Pages 332-344
Technical Paper | doi.org/10.13182/NSE90-A29061
Articles are hosted by Taylor and Francis Online.
Thermal-neutron-driven fast neutron fields using a fission plate and a 6LiD converter are briefly reviewed. The characteristics of a large (27-cm-diam × 1.1-cm-thick) fission plate made of highly enriched uranium and a sandwich-type 6LiD converter (two 10-cm-square × 1-cm-thick 6LiD plates) are presented, both of which have been used at the heavy water thermal neutron facility at the Kyoto University Reactor. The neutron spectra in both fields were calculated by the MCNP Monte Carlo code. The average neutron energy and the neutron spectrum of the 6LiD converter were measured and the results agree with the predicted values. Using both fields, we measured the average cross sections for some threshold reactions, 6 with the fission plate and 23 with the 6LiD converter. The results are compared with evaluated values and previous measurements.
