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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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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.
Luciano Burgazzi
Nuclear Technology | Volume 173 | Number 2 | February 2011 | Pages 153-161
Technical Paper | Reactor Safety | doi.org/10.13182/NT11-A11544
Articles are hosted by Taylor and Francis Online.
This paper describes a modeling and analysis approach for reliability prediction based on degradation modeling, considering multiple degradation measures and with respect to the thermal-hydraulic passive systems.Previous research on the topic has drawn attention to the susceptibility of passive systems to several modes of failure. In fact, it has been recognized that a system may have, in addition to component mechanism failures, multiple degradation paths, so it is necessary to simultaneously consider multiple degradation measures. Also, many research efforts on degradation analysis were initiated by making assumptions about the degradation mechanism. In reality, often there is very limited understanding about the concerned degradation mechanisms together with their interdependencies.In this paper, an analysis procedure is developed to address this aspect. Simulated data have been used to illustrate the applicability of this approach. Results on the application of the methods to a simplified model of the passive residual heat transport system in water-cooled reactors is presented. It was verified that when the multiple degradation measures in a system are correlated, an incorrect independence assumption may overestimate the system reliability.