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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
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
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
J. B. Yang, X. G. Tuo, Z. Li, Y. Cheng, L. Wang, H. H. Wang, B. Cai, M. Z. Liu
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 233-238
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A22318
Articles are hosted by Taylor and Francis Online.
To improve the yield of online prompt gamma neutron activation analysis, the Monte Carlo N-Particle Transport Code (MCNP) is used to simulate the computation and analysis of the material and thickness of reflectors on both sides of the sample chamber as well as the type and thickness of the neutron-absorbing material in front of the detector. The simulation shows that the optimal thickness of the reflecting material is [approximately]100 mm when heavy water is added on both sides of the sample chamber and the optimal thickness of the neutron-absorbing material is [approximately]50 mm when polyethylene-containing boron is added in front of the detector. The experiment demonstrated that the yield of prompt gamma rays of the main elements in the cement sample increased to some extent.