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.
Explore membership for yourself or for your organization.
Conference 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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Joint NEA project performs high-burnup test
An article in the OECD Nuclear Energy Agency’s July news bulletin noted that a first test has been completed for the High Burnup Experiments in Reactivity Initiated Accident (HERA) project. The project aim is to understand the performance of light water reactor fuel at high burnup under reactivity-initiated accidents (RIA).
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.