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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
W. J. Lindsey, P. L. Roggenkamp, W. K. Woods
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 78-82
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31069
Articles are hosted by Taylor and Francis Online.
Small-scale test irradiations of 237Np in the Richland and Savannah River production reactors have provided substantial empirical information on the mechanisms for formation of 236Pu. Application of this information to the design of larger scale irradiations in the Savannah River high flux reactor has resulted in successful production of 2 kg of 238Pu, meeting current isotopic specifications for the heart program. Further work is planned to develop practical technology of producing still larger amounts. The optimum location for target 237Np in the D2O reflector of the high flux charge has been established. Tests have demonstrated that matrix material for the targets is an important variable, and that the use of aluminum should be avoided. Irradiations of kilogram quantities of 241 Am have been completed and most of the resulting 242Cm will be allowed to decay into 238Pu before chemical processing (about two years). However, small amounts of the irradiated 241Am will be processed promptly to provide 242Cm for decay into ultra-high purity 238Pu.