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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Framatome, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
Thomas V. Holschuh, Wade R. Marcum
Nuclear Technology | Volume 206 | Number 3 | March 2020 | Pages 428-434
Technical Paper | doi.org/10.1080/00295450.2019.1640515
Articles are hosted by Taylor and Francis Online.
Recently, techniques for qualitative inspections of spent fuel using Cherenkov light have advanced the International Atomic Energy Agency’s ability to perform defect verification measurements following discharge of the fuel from the reactor. Unfortunately, these measurements are limited in their value for safeguards and nuclear material accountancy since they do not quantify the fissile material quantities and cannot characterize a reactor during operations. The Cherenkov Radiation Assay for Nuclear Kinetics (CRANK) system has been devised to quantify the fissile material in the Oregon State TRIGA Reactor (OSTR) during two or more reactor pulses through the measurement of Cherenkov light. The results from the OSTR experiments have shown that the CRANK system is capable of determining the ratio of reactor kinetics parameters (RKP) through the measurement of Cherenkov light in an assay of a research reactor capable of pulsing. There exists excellent agreement between the declared value of the RKP ratio in the OSTR Final Safety Analysis Report and four separate reactor pulse comparisons using the CRANK system. Future applications of the CRANK system can provide independent determination of a pulsing research reactor with an unknown RKP ratio.