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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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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Abdellatif M. Yacout, Won-Sik Yang, Gerard L. Hofman, Yuri Orechwa
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 61-72
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35275
Articles are hosted by Taylor and Francis Online.
Integral parameters of reactor fuel pins are usually measured after long periods of irradiation, where each period can extend over a number of irradiation cycles. Examples of these parameters include cladding diametral strain and parameters involved in the evaluation of fuel/cladding chemical interaction and fuel restructuring. Analysis of these parameters requires knowledge of calculated irradiation parameters, which can vary between irradiation cycles and within the cycles. Irradiation temperature is one such parameter. A calculated weighted average temperature that takes into account the fluctuations in temperature between irradiation cycles is introduced. The work discusses the justification for using this temperature and a methodology for its validation. The methodology is based on comparing calculated average temperatures with temperatures inferred from the postirradiation examination of restructured binary metallic fuel pins in the Experimental Breeder Reactor II. The analysis shows reasonable agreement between the two temperatures. The peak irradiation temperatures, which are usually used in the analysis, were out of the range of the temperatures inferred from the experimental observations, showing the importance of using the average temperature.