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
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
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.
