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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.
