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Safety analysis of the IAEA reference research reactor during loss of flow accident using the code MERSAT
Authors:A. Hainoun  N. Ghazi
Affiliation:a Department of Nuclear Engineering, Atomic Energy Commission of Syria (AECS), P.O. Box 6091, 17th Nissan Street, Kafersouseh, Damascus, Syria
b National Atomic Energy Commission (NATEC), P.O. Box 4720, Sana’a, Yemen
Abstract:Using the thermal hydraulic code MERSAT detailed model including primary and secondary loop was developed for the IAEA's reference research reactor MTR 10 MW. The developed model enables the simulation of expected neutronic and thermal hydraulic phenomena during normal operation, reactivity and loss of flow accidents.Two different loss of flow accident (LOFA) have been simulated using slow and fast decrease time of core mass flow. In both cases the expected flow reversal from downward forced to upward natural circulation has been successfully simulated. The results indicate that in both accidents the limit of onset of subcooled boiling was not arrived and consequently no exceed of design limits in term of thermal hydraulic instability or DNB is observed. Finally, the simulation results show good agreement with previous international benchmark analyses accomplished with other qualified channel and thermal hydraulic system codes.
Keywords:LOFA, loss of flow accident   HEU, highly enriched uranium   LEU, low enriched uranium   MERSAT, (Model for Evaluation of Reactor Safety and Analysis of Thermal hydraulic)   DNB, departure from nucleate boiling   DBAs, design basis accidents   MTR, material testing reactor   SFE, standard fuel element   CFE, control fuel element   SS, steady state   PIEs, postulated initiating events   SLOFA, slow loss of flow accident   FLOFA, fast loss of flow accident   HTC, heat transfer coefficients   IAEA, International Atomic Energy Agency   AECS, Atomic Energy Commission of Syria   UPISA, University of PISA (Italy)   ANL, Argonne National Laboratory (USA)   LAS, Laboratoire d&rsquo  Analyse de Sû  reté   (Algeria)   JEN, Junta de Energia Nuclear (Spain)   JAERI, Japan Atomic Energy Research Institute (Japan)
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