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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Latest News
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.”
Y. Ronen, M. Aboudy, D. Regev
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 224-233
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT06-A3702
Articles are hosted by Taylor and Francis Online.
There is growing interest in the use of 242mAm as a nuclear fuel. Since the thermal absorption cross section of 242mAm is very high (a = 8950 b), the best way to obtain 242mAm is by the capture of fast or epithermal neutrons in 241Am. As a result, we have considered replacing the radial blanket of a fast reactor, which is usually depleted uranium, with 241AmO2.We chose a 714-MW(thermal) MONJU reactor, and we replaced some of the radial blanket and the outer core assemblies with 10 676 kg of 241AmO2 fuel. We calculated the reactor core by using the MCNP Monte Carlo code.The total amount of 242mAm becomes stabilized after 16 yr, but the enrichment does not. In our calculation, ~7.2% enrichment is obtained after 18 yr. Obtaining higher enrichments might indicate that 242mAm nuclear fuel can be used without further enrichment in many cases.The results presented in this paper are considered an upper limit scenario. In particular the target 241Am loading is not likely to be available soon, but 242mAm production from lesser amounts is easily scaled down proportional to the actual mass irradiated.