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.
K. R. Rempe, K. S. Smith, A. F. Henry
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 334-342
Technical Paper | doi.org/10.13182/NSE89-A23686
Articles are hosted by Taylor and Francis Online.
Pin power reconstruction capability has recently been added to the SIMULATE-3 nodal reactor analysis code. Detailed descriptions of the models employed are presented. This reconstruction method is based on single-assembly (not colorset) form functions, and a detailed treatment of spectral interaction between assemblies is introduced. This pin power reconstruction method produces accurate calculation of pin powers throughout depletion and fuel shuffling. Comparisons with multigroup transport calculations and with measured critical assembly power distributions demonstrate that the pin power reconstruction method is comparable in accuracy to fine-mesh methods. The high numerical efficiency of the reconstruction method permits economical calculation of three-dimensional pin power distributions in light water reactors.