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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.
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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.
Daniel B. Bullen
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 29-45
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35197
Articles are hosted by Taylor and Francis Online.
A mathematical model to predict the cumulative failure distribution for the containment barrier system (CBS) employed in a deep geologic disposal facility is presented as a function of near-field environmental conditions expected at the Yucca Mountain site in Nevada. The model can address the effects of container design, areal power density, and dominant heat transfer mode on the cumulative container failure distribution. This model has been employed to describe the performance of the CBS as one part of a risk-based performance assessment of the Yucca Mountain site. The model employs Weibull and exponential distributions to describe container failures. Parameter values employed in the model are based on simple, time-dependent, mechanistic models and relevant corrosion data, which describe failure of individual components of the CBS as a function of environmental conditions. The relative importance of container design with respect to predicted container performance is demonstrated through comparison of the results for three candidate container designs. The best container performance was noted for the conduction-dominant heat transfer mode at an areal power density of 114 kW/acre for all container designs. Calculations for the titanium-clad, Alloy C-4 container design suggest that significant improvements in container performance may be achieved through the use of very high-performance alloys. The performance of the multipurpose container (MPC) design at the high areal power density (114 k W/acre) was only slightly better than the Alloy 825, single-barrier design. This was due to the potential deleterious effect of high-temperature oxidation on the carbon steel outer barrier of the MPC design.