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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Chris Wagner: The role of Eden Radioisotopes in the future of nuclear medicine
Chris Wagner has more than 40 years of experience in nuclear medicine, beginning as a clinical practitioner before moving into leadership roles at companies like Mallinckrodt (now Curium) and Nordion. His knowledge of both the clinical and the manufacturing sides of nuclear medicine laid the groundwork for helping to found Eden Radioisotopes, a start-up venture that intends to make diagnostic and therapeutic raw material medical isotopes like molybdenum-99 and lutetium-177.
Hyeong Il Kim, M. Herman, S. F. Mughabghab, P. Oblozinský, D. Rochman, Young-Ouk Lee
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 168-189
Technical Paper | doi.org/10.13182/NSE160-168
Articles are hosted by Taylor and Francis Online.
Neutron cross sections for a complete set of Nd isotopes, 142,143,144,145,146,147,148,150Nd, were evaluated in the incident energy range from 10-5 eV to 20 MeV. In the low-energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances, Fifth Edition: Resonance Parameters and Thermal Cross Sections, Z = 1 - 100. In the unresolved resonance region, we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI.8, JENDL-3.3, and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations, and they were adopted by the new U.S. evaluated nuclear data ENDF/B-VII.0, released in December 2006.