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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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December 2024
Nuclear Technology
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November 2024
Latest News
Nuclear progress, but not much else, from COP29
COP29 was good for nuclear energy, but not so good for anything else.
That was one of Seth Grae’s takeaways from this year’s Conference of the Parties—or, United Nations Framework Convention on Climate Change (UNFCCC)—held for two weeks in November in Baku, Azerbaijan. Grae, chief executive of Lightbridge Corporation and chair of the American Nuclear Society’s International Council, attended with four other ANS delegates: ANS President Lisa Marshall, Gale Hauck, Shirly Rodriguez, and Andrew Smith.
William J. Walters, Nathan J. Roskoff, Alireza Haghighat
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 21-39
Technical Paper | doi.org/10.1080/00295639.2018.1497395
Articles are hosted by Taylor and Francis Online.
The Real-time Analysis for Particle transport and In-situ Detection (RAPID) code uses a unique, extremely fast, fission matrix–based methodology to compute the eigenvalue, and three-dimensional, pinwise fission source distribution for reactor, spent fuel pool, and spent fuel cask problems. In this paper, the RAPID fission matrix method is described and analyzed for application to several large pressurized water reactor problems, based on the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Monte Carlo Performance Benchmark problem. In the RAPID methodology, fission matrix coefficients precalculated using the Serpent Monte Carlo code, are then coupled together and solved for different core arrangements. A boundary correction method is used to obtain more accurate fission matrix values near the radial and axial reflectors. Eigenvalues and fission source distributions are compared between RAPID and Serpent reference calculations. In most cases, the eigenvalue differences between methods are less than 10 pcm. For a uniform core model, pinwise fission distributions between the methods differ by a root-mean-square value of , compared to a Serpent uncertainty of . The pinwise, axially dependent (100 axial levels) differences are , compared to a similar Serpent uncertainty of . To achieve these levels of uncertainty, the RAPID calculations are over 2500 times faster than Serpent, not counting the precalculation time.