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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.
Ansar Parvez
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 235-241
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Fuel Cycle | doi.org/10.13182/NT85-A33556
Articles are hosted by Taylor and Francis Online.
The effect of the introduction of 236U because of the recycling of nuclear fuel has been determined for a typical pressurized water reactor fuel cycle. It has been estimated that an extra 0.255 g of 235U is required for each gram of 236U present at the beginning of exposure. In terms of cost, the additional 235U translates into an ∼1% increase in the fuel cost for every gram of 236U. The value of the uranium component of the exposed fuel has also been calculated in terms of the savings in separative work and the feed requirements resulting from the use of recycled uranium. While the exact value depends on the fuel cycle component costs and the relative concentrations of 235U and 236U, it is estimated that even after accounting for the presence of 236U, the use of reprocessed uranium may result in a total saving of ∼14% in ore and enrichment costs. It was also found that upon repeated recycling, 236U reaches an equilibrium concentration, but only if the recycled fuel ratio in the feed to enrichment plant is limited to about 1 part in 5.