ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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!
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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.
Jingshang Zhang
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 207-219
Technical Paper | doi.org/10.13182/NSE02-02
Articles are hosted by Taylor and Francis Online.
Theoretical improvements have been made in the unified Hauser-Feshbach and exciton model. The angular momentum conservation is considered in reaction processes for both equilibrium and preequilibrium mechanisms. The recoil effects in varied emission processes are taken into account strictly so the energy balance can be held exactly. A method for calculating double-differential cross sections of composite particles is proposed. Based on this theoretical frame, the UNF code (2001 version) for calculating neutron-induced reaction data of structural materials below 20 MeV was issued. The functions of the UNF code are introduced.
