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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
A. Hemmendinger, C. E. Ragan, Jon M. Wallace
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 274-280
Technical Paper | doi.org/10.13182/NSE79-A20148
Articles are hosted by Taylor and Francis Online.
The specific production of tritium in a 600-mm-diam sphere of 6LiD irradiated by a central source of 14-MeV neutrons has been determined by measuring the tritium radioactivity in samples of 6LiH and 7LiH embedded in the sphere. Results are reported for several samples of each isotope at each of five different radii in the assembly. The entire process of decomposing the LiH samples, transferring the evolved gas into counters, and determining the decay rate was standardized by processing LiH samples irradiated by thermal neutrons, for which the 6Li(n,α) cross section is well known. These experiments provide benchmark measurements for checking calculations of neutron transport and tritium production in 6LiD. Tritium production in each ampule, as calculated using a three-dimensional Monte Carlo code, is in reasonable agreement with the experiment. For 7Li, discrepancies between calculation and experiment seem to be due to errors in the tritium production cross sections.
