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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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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
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Hyunsuk Lee, Sooyoung Choi, Deokjung Lee
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 69-85
Technical Paper | doi.org/10.13182/NSE13-102
Articles are hosted by Taylor and Francis Online.
This paper proposes a new hybrid method combining the Monte Carlo (MC) method and the Method of Characteristics (MOC). The hybrid method employs MC and MOC together to solve a neutron transport problem. The two different methods are applied to different neutron energy ranges. The MC method is used to obtain accurate solutions in the resonance energy range, and the MOC is used for high and low neutron energy ranges to achieve high performance of the new method. The two methods are consistently coupled through scattering and fission source terms during the power iterations and group sweepings. Numerical tests with a model problem confirm that the hybrid method can produce a more accurate solution than a conventional MOC by a factor of 10 and much higher computational efficiency than a conventional MC method by a factor of 90.