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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
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.
Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 282-292
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3762
Articles are hosted by Taylor and Francis Online.
Exploratory analyses were performed by the RANNS code for simulated tests of the reactivity-initiated accident with two high-burnup pressurized water reactor rods in the Nuclear Safety Research Reactor (NSRR). The code performs thermal and finite element mechanical calculations in an axis-symmetrical cylinder geometry. On the basis of the irradiation-induced rod conditions including bonding, the code analyzed a strong pellet-clad mechanical interaction process that would often lead to low-strain split failure. The predicted quantities such as temperature and stress strain of cladding were discussed and compared with the experimental observations. The calculated cladding permanent strain has a reasonable agreement with postirradiation examination data. The process from crack initiation to final split failure was accounted for by the plastic strain occurrence in the cladding.