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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Parveen K. Jain
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 301-311
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33768
Articles are hosted by Taylor and Francis Online.
A first-principle model has been developed to perform steady-state and transient analyses of pressurized water reactor plants on microcomputers. The model includes representations for all major components and control systems of the nuclear steam supply systems of plants that have U-tube steam generators. The process of inputting data is simple, and it is easy to set up for simulations of various transient scenarios. The model is accompanied by sophisticated preand postprocessors to help users define or modify input files, start model executions, and analyze output results. It has been benchmarked against plant data and RELAPS for various steady-state and transient scenarios. Satisfactory comparisons have been obtained. Results are presented for full-power steady-state conditions and for a steam generator tube rupture transient.
