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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Nuclear fuel cycle reimagined: Powering the next frontiers from nuclear waste
In the fall of 2023, a small Zeno Power team accomplished a major feat: they demonstrated the first strontium-90 heat source in decades—and the first-ever by a commercial company.
Zeno Power worked with Pacific Northwest National Laboratory to fabricate and validate this Z1 heat source design at the lab’s Radiochemical Processing Laboratory. The Z1 demonstration heralded renewed interest in developing radioisotope power system (RPS) technology. In early 2025, the heat source was disassembled, and the Sr-90 was returned to the U.S. Department of Energy for continued use.
Conny B. O. Holmstroem, Tor Endestad, Knut Follesoe, Nils T. Foerdestroemmen, Kjell Haugset, Frode Strand Volden
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 83-92
Technical Paper | Special on ANP ’92 Conference / Reactor Control | doi.org/10.13182/NT94-A35000
Articles are hosted by Taylor and Francis Online.
The concept of an integrated surveillance and control system (ISACS) has been developed into a first prototype, ISACS-1, which is now in operation at the pressurized water reactor simulator-based experimental control room HAMMLAB of the Organization for Economic Cooperation and Development’s Halden Reactor Project, Halden, Norway. It is characteristic of ISACS that it covers the whole interface between the process and the operator, and this interface is fully computerized using tools like cathode ray tubes and dynamic keyboards. In addition, a large number of computerized operator support systems are included in ISACS. The ISACS-1 is presently subject to extensive evaluation. The test and evaluation program aims at both providing design feedback and addressing general human-machine topics in advanced control rooms. The program is separated into three stages, starting with basic human factors work concerning layout and coding remedies. The next stage focuses on the qualitative aspects of the ISACS interface. In the final stage, the evaluation addresses higher level human factors issues, including experiments to evaluate ISACS’s impact on the operator’s overview and understanding of the current status of the process. The goal is to investigate how modern computer technology can be used to improve operational safety and efficiency of nuclear power plants and other complex processes.