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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
J. R. Knight
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 239-245
Technical Paper | doi.org/10.13182/NSE61-A25998
Articles are hosted by Taylor and Francis Online.
Due to the interest in determining the dose received by persons near a criticality accident, a method for calculating the neutron spectra and neutron dose for highly enriched uranium solutions at various hydrogen to U235 atomic ratios has been developed. This method uses the output from a code for criticality calculations, and determines the average leakage neutron energy, the neutron leakage spectrum, the first collision neutron dose, and the total neutron dose. The results of these calculations show that the average energy of the leakage neutrons and the dose per incident leakage neutron per cm2 decrease somewhat with increased hydrogen to U235 atomic ratio, but it appears that this effect is sufficiently small so that an exact knowledge of the uranium concentration would not be necessary to obtain reasonable dose estimates. The effect of neutron scattering on the neutron spectra and doses is not evaluated. No attempt has been made to describe actual dose determination methods, since these have been adequately described elsewhere.