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.
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
DOE tags Los Alamos to lead $9.25 million molten salt computational research program
The Department of Energy has chosen Los Alamos National Laboratory to lead a $9.25 million collaborative project to model the behavior and properties of structural materials in molten salt through the Scientific Discovery through Advanced Computing (SciDAC) program and announced the news August 9. The team working on the five-year project includes experts from LANL; Carnegie Mellon University; and Idaho, Lawrence Berkeley, and Sandia national laboratories.
J. C. Wang, Gary L. Jensen, J. B. Czirr
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 77-85
Technical Paper | dx.doi.org/10.13182/NSE93-A23995
Articles are hosted by Taylor and Francis Online.
Rigorous tests of the Monte Carlo transport code MCNP have been performed by measuring the efficiency of a 6Li-glass moderating neutron detector using Lucite as the moderator relative to the efficiency of the detector using mineral oil as the moderator, and comparing this with the MCNP predicted value. The tests were done using both 252Cf fission-source neutrons and 1.2-MeV neutrons produced by a Van de Graaff accelerator.