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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Eldon Schmidt, Philip F. Rose
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 300-304
Technical Note | doi.org/10.13182/NSE83-A17800
Articles are hosted by Taylor and Francis Online.
A modern continuous energy-angle Monte Carlo program has been used to perform neutron shielding calculations for a fusion shield. The SAM-CE Monte Carlo program developed by the Mathematical Applications Group has been used for a demonstration calculation of an Oak Ridge National Laboratory fusion shield benchmark with a deuterium-tritium neutron source. Calculations were made for three shielding configurations. They were compared with experiment and also with previous calculations using Sn with first- and last-flight modifications. Agreement with experiment was found to be good at high (>14-MeV) and low (<5-MeV) energies. At intermediate energies where the fluxes are much lower, the agreement was less accurate differing by as much as factors of 2 or 3 in extreme cases. An improved resolution broadening function for the NE-213 detectors helped reduce some of these differences.