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Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Dov Ingman, Leib Reznik
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 243-259
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33827
Articles are hosted by Taylor and Francis Online.
A multicomponent system, specified by a high level of power generation and transformation as a thermodynamics system with strong interaction between the elements, is considered in the reliability analysis. The reliability of each system element is dependent on the average energy of the system. The approach, which aims to give proper consideration to the system / element interaction, is based on the energy accumulation aspects of various processes of the element and the system deterioration. The phenomena of coherent blockages of core coolant channels for different geometrical configurations serve to demonstrate that there exists, in principle, a possibility of failure of the system through cooperative failures of its elements. The investigation is based on statistical thermodynamics, particularly on the approach of “phase transitions,” and also on the percolation theory results. The developed model has been employed to evaluate the propagation rate of the subchannel blockages under critical conditions. In spite of the simplified character of the model, it has demonstrated the necessity of including consideration of collective phenomena in the reliability analysis of multicomponent systems characterized by a high power level. The developed approach permits construction of a minimum set of generalized system parameters that describe the critical system behavior. A quantitative determination of these parameters and an application of the model to specific reactor core designs and severe transient scenarios will be the subject of further investigation.