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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
Akio Yamamoto, Masahiro Tatsumi, Naoki Sugimura
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 144-151
Technical Paper | doi.org/10.13182/NSE08-80
Articles are hosted by Taylor and Francis Online.
A new burnup calculation method, called the projected predictor-corrector (PPC) method, is proposed. In comparison with the conventional predictor-corrector (PC) method, a larger time-step size can be used in burnup calculation without losing calculational accuracy. The PPC method is especially useful for Gd-bearing fuel assemblies, for which a fine time step size is necessary in burnup calculations. The PPC method utilizes a correlation between the number density and the reaction rate in each burnable nuclide and improves the accuracy of the microscopic reaction rate in the corrector step by estimating the “projected” reaction rate. The additional computation time for the PPC method is negligible. Verification calculations are performed for 17 × 17 pressurized water reactor fuel assemblies with 16 Gd-bearing fuel rods. The content of Gd in Gd-bearing fuel rods is set to be 2 to 10 wt%. The calculation results indicate that the PPC method shows comparable accuracy to conventional PC methods whose step time size is about half; i.e., the number of burnup steps in the PPC method can be reduced to about half of that in the conventional PC method.