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.
Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
C. Ertek
Nuclear Science and Engineering | Volume 89 | Number 2 | February 1985 | Pages 191-196
Technical Note | doi.org/10.13182/NSE85-A18193
Articles are hosted by Taylor and Francis Online.
Three different problems are selected for the comparison of results obtained by two different neutron flux density spectrum unfolding codes, LOUHI and SAND-II. In the first two problems, a light-water-reactor-type spectrum is considered. For both problems the same input spectrum, the same reaction rates, and the same neutron cross-section data library (ENDF/B-IV) is used. The third problem deals with the betatron-associated neutron flux density spectrum using LOUHI and SAND-II codes in the same way. This technique proved to be very useful in finding in a very practical way the problematic reaction rates, like 27Al(n, α)24Na, 48Ti(n, p)48Sc, 115In(n, n)115mIn, 127I(n, 2n)126I, and 232Th(n, f), in neutron spectrum unfolding.
