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.
Vijay R. Nargundkar, Tejen Kumar Basu, Om Prakash Joneja
Fusion Science and Technology | Volume 12 | Number 3 | November 1987 | Pages 380-394
Technical Paper | Blanket Engineering | doi.org/10.13182/FST87-A25070
Articles are hosted by Taylor and Francis Online.
Neutron multiplication measurements for 14-MeV neutrons were carried out in thick beryllium and graphite assemblies at the Institute for Reactor Development, Jülich, Federal Republic of Germany. Earlier Monte Carlo calculations using the ENDF/B-III library contained systematic errors that did not account for the predominant axial thermalization and non-1/v absorption in polyethylene. In addition, the calculational geometry differed considerably from the experimental geometry. These deficiencies have been eliminated in the present calculations, where the Los Alamos 30-group CLAW-IV library has been used. The anisotropy of the source in space and energy has also been taken into account. The results show that the calculated value of neutron multiplication is 20% higher (originally reported 30% higher) than the measured multiplication in beryllium. The results confirm the measurements made with BeO. For graphite and lead, excellent agreement is found between calculated and measured multiplication.