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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
Argonne research aims to improve nuclear fuel recycling and metal recovery
Servis
Scientists at Argonne National Laboratory are investigating a used nuclear fuel recycling technology that could lead to a scaled-down and more efficient approach to metal recovery, according to a recent news article from the lab. The research, led by Argonne radiochemist Anna Servis with funding from the Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E), could have an impact beyond the nuclear fuel cycle and improve other high-value metal processing, such as rare earth recovery, according to Argonne.
The research: Servis’s work is being carried out under ARPA-E’s CURIE (Converting UNF Radioisotopes Into Energy) program. The specific project—Radioisotope Capture Intensification Using Rotating Packed Bed Contactors—started in 2023 and is scheduled to end in January 2026.
Seonghee Hong, Myunghyun Kim
Fusion Science and Technology | Volume 75 | Number 6 | August 2019 | Pages 466-478
Technical Paper | doi.org/10.1080/15361055.2019.1609820
Articles are hosted by Taylor and Francis Online.
To enhance the practical application of a fusion-driven subcritical reactor, a system with constant fusion power by online feeding of molten salt fuel was designed. The system satisfies multiple purposes including waste transmutation, tritium breeding (TB), and energy multiplication (EM) through constant fusion power. All neutronic calculations were performed by SERPENT2.1.29 with the ENDF/B-VII.0 neutron cross-section library in order to simulate the online-feeding process.
A constant k-eff is maintained by the amount of the feeding being larger than the amount of the removed fission products. However, system performance is significantly improved by just reducting the reactivity swing with the feeding. Compared to a once-through cycle (OTC), the performance of TB and EM is significantly improved as the feeding rate increases. However, there is no deep burning effect like the OTC for waste transmutation.
The performance of waste transmutation is changed in the feeding scenarios. For the scenario with a high plutonium ratio, transmutation with plutonium is increased. On the other hand, for the feeding scenario with a high minor actinide ratio, transuranic waste is burned. However, the transmutation performance is degraded due to a low fission-to-capture ratio.
