Articles in Scholarly Journals [Incomplete List]

1. Use of coupled code technique for Best Estimate safety analysis of nuclear power plants
   Progress in Nuclear Energy, vol. 49, no. 1, pp. 1–13, 2007
2. A model for the analysis of loss of decay heat removal during loss of coolant accident in MTR pool type research reactors
   Annals of Nuclear Energy, vol. 33, no. 5, pp. 405–414, 2006
3. RELAP5/3.2 assessment against low pressure onset of flow instability in parallel heated channels
   Annals of Nuclear Energy, vol. 33, no. 6, pp. 510–520, 2006
4. Analysis of the Peach Bottom flow stability test number 3 using the coupled RELAP5/PARCS code
   Annals of Nuclear Energy, vol. 33, no. 7, pp. 646–652, 2006
5. Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermalâ??hydraulic 3D kinetics code
   Nuclear Engineering and Design, vol. 236, no. 12, pp. 1240–1255, 2006
6. Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code
   Progress in Nuclear Energy, vol. 48, no. 8, pp. 806–819, 2006
7. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core
   Annals of Nuclear Energy, vol. 32, no. 15, pp. 1679–1692, 2005
8. Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code
   Nuclear Engineering and Design, vol. 235, no. 6, pp. 661–674, 2005
9. Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test
   Nuclear Engineering and Design, vol. 235, no. 16, pp. 1727–1736, 2005
10. Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code
    Annals of Nuclear Energy, vol. 31, no. 12, pp. 1385–1402, 2004