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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Carroll B. Mills
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 133-138
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30921
Articles are hosted by Taylor and Francis Online.
Requirements for underseas nuclear reactor power systems for small vessels include: simplified small reactor and plant control and instrumentation; long-term compatibility of fuel, structure, and coolant; and extended fuel lifetime, safety, and low cost. Neutronic qualities that reflect these requirements are: lowest critical mass for low cost and small size; low fuel concentration in the fuel elements consistent with extended fuel lifetime, small fuel effects on fuel element materials properties, and small fission-product effects; negative temperature and core geometry coefficients of reactivity, in the interest of minimizing safety and control problems, 100-g fuel burnup (100 MWd of energy). A reactor design that has these qualities uses a pressurized water moderated, beryllium (4-in.) reflected, solid fuel geometry with 0.070 g/ml 235U in the core, and zirconium fuel elements, with a fuel mass including 0.1 kg for burnup of under 0.8 kg 235U. This reactor core is 8 in. long and 8 in. in diameter, and contains 85%, by volume, of water at an operating temperature around 500°F, for a power level of 300 kW(th).