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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
H. Küsters
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 296-313
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT85-A33728
Articles are hosted by Taylor and Francis Online.
The improvements of the neutron data for minor actinide (MINAC) isotopes in uranium-plutonium fuel cycles, the qualification of these data by integral experiments, and remaining data requirements are summarized. In the last 10 yr, there has been a successful worldwide effort to improve the neutron data base of MINAC isotopes. Most of the discrepancies that were observed in 1975 were reduced to an acceptable level in 1984. Tests of nuclear data in thermal and fast reactors before 1984 only revealed a few important discrepancies: the (n,2n) reaction on 237Np and the neutron capture in 243Am (mainly in thermal reactors). New measurements by N. V. Kornilov et al. on the 237Np(n,2n) reaction leading to the short-lived state of 236Np, presented in May 1984, solve the important discrepancies concerning this reaction.