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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Takaaki Mochida, Katsumasa Haikawa, Jun-Ichi Yamashita, Akira Nishimura, Yutaka Iwata, Shiroh Arai
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 91-107
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35314
Articles are hosted by Taylor and Francis Online.
A boiling water reactor (BWR) core design for better uranium utilization is presented, and its validity is demonstrated through simulation and operation data. Together with the axial power flattening obtained by an axially zoned enrichment core, uranium utilization improvement techniques such as an axial blanket for neutron leakage reduction, a low leakage loading pattern, an improved local enrichment distribution in the fuel bundle, and spectral shift operation method are promising design features to be applied to the BWR core. Quantitative studies for the amount of burnup increase and power peaking rise are made to estimate a level of effective uranium utilization. The improvements in uranium utilization are confirmed not only in the computational core design study, but also in empirical data from a commercial BWR. Operating experience proves the adequacy of the core design. A uranium utilization improvement of >10% is obtained without a loss of load factor.