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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
L. Popescu, J. Heyse, J. Wagemans, C. Wagemans
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 204-209
Technical Paper | doi.org/10.13182/NSE11-65
Articles are hosted by Taylor and Francis Online.
An experimental program was set up at SCKCEN to determine the thermal neutron-induced fission cross section of curium isotopes. These transuranium nuclei are produced in nuclear reactors and are candidates for transmutation. This paper presents our 243Cm(n,f) measurement, yielding a cross-section value of (667 ± 26) b. A detailed analysis of the experimental results published by previous groups is performed, and the renormalized values are compared with our result. In general, a good agreement with old data is observed, questioning the values adopted by different nuclear data libraries.