ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Kazuki Hida, Sadao Kusuno, Takeshi Seino
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 148-159
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A33857
Articles are hosted by Taylor and Francis Online.
The effects of 232U and 236U on uranium recycling in boiling water reactors are studied with the two-dimensional lattice physics code TGBLA. A simple analytic expression is proposed for reactivity compensation factor K, taking into account the self-shielding effect of resonance absorption in 236U: K = a + b/ (1 + ce6)1/2, where e6 denotes the 236U concentration. To output the same energy as the 3.0 wt% enrichment fuel free from 236U, the constants are determined to be a = 0.06, b = 0.23, and c = 1.9. The introduction of 1 ppb 232U increases the surface dose rate of the fuel assembly by 60% over the aged enriched natural uranium. Lead time is as important as cooling time in 232U production because of the presence of the chain that originates from the alpha decay of naturally occurring 234U. The natural uranium feed and the separative work requirement are evaluated on these bases, introducing typical recycling strategies, and it appears that uranium recycling saves 17 to 19% of the natural uranium but increases the separative work by 0 to 2%. The front-end cost analysis reveals the benefit of a concentrated utilization of reprocessed uranium, which results from the self-shielding effect of 236U and the assumption of a linear dependence of the front-end penalty on 232U concentration. Also studied are plutonium composition in irradiated fuels and the effects of extended burnup.
