ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
Latest Magazine Issues
Apr 2024
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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
DOE awards $59.7 million for university nuclear R&D in 2024; $1 billion in 15 years
The Office of Nuclear Energy is awarding $59.7 million to 25 U.S. colleges and universities, two national laboratories, and one industry organization to support nuclear energy research and development and provide access to world-class research facilities, the Department of Energy announced on April 15.
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.