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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
S. Murakami, M. Mizuno
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 219-227
Technical Paper | Material | doi.org/10.13182/NT91-A34558
Articles are hosted by Taylor and Francis Online.
The constitutive equations for creep, swelling, and damage under irradiation are discussed in terms of incorporating the transient behavior of swelling after the incubation fluence as well as the effect of transient creep. Creep during irradiation is assumed to consist of irradiation-induced creep and irradiation-affected thermal creep, and the dilatational part of irradiation-induced creep is identified with swelling. The irradiation-induced creep is formulated by postulating the stress-induced preferential absorption mechanism. Then, the continuous transition of swelling after the incubation fluence is formulated using the curvature parameter of Bates and Korenko. For transient creep, on the other hand, the McVetty creep law and the Kachanov-Rabotnov creep damage theory are modified to describe irradiation-affected thermal creep. The resulting equations are applied to predict creep before, during, and after irradiation of 20% cold-worked Type 316 stainless steel at elevated temperatures, and the validity of the equations is discussed by comparison with experiments. Finally, the bulging and rupture process in fast breeder reactor fuel cladding is analyzed using the equations.
