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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
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.