Articles in Scholarly Journals [Incomplete List]

1. RELAP5/MOD3.3 Code Validation with Plant Abnormal Event
   Science and Technology of Nuclear Installations, vol. 2008, Article ID 745178, 10 pages, 2008
2. Genetic algorithm optimisation of the maintenance scheduling of generating units in a power system
   Reliability Engineering & System Safety, 2007
3. Prediction of light gas distribution in experimental containment facilities using the CFX4 code
   Nuclear Engineering and Design, 2007
4. Modeling of containment atmosphere mixing and stratification experiment using a CFD approach
   Nuclear Engineering and Design, vol. 236, no. 14-16, pp. 1682–1692, 2006
5. Quantitative assessment of thermal–hydraulic codes used for heavy water reactor calculations
   Nuclear Engineering and Design, vol. 236, no. 3, pp. 295–308, 2006
6. Comparison of heat transfer conditions in tube bundle cross-flow for different tube shapes
   International Journal of Heat and Mass Transfer, vol. 49, no. 5-6, pp. 1027–1038, 2006
7. Simulation of void fraction profile evolution in subcooled nucleate boiling flow in a vertical annulus using a bubble-tracking approach
   Heat and Mass Transfer, vol. 42, no. 6, pp. 552–561, 2006
8. Heat Transfer Conditions in Flow Across a Bundle of Cylindrical and Ellipsoidal Tubes
   Numerical Heat Transfer: Part A: Applications, vol. 49, no. 7, pp. 699–715, 2006
9. Drag Coefficient and Stanton Number Behavior in Fluid Flow Across a Bundle of Wing-Shaped Tubes
   Journal of Heat Transfer, vol. 128, no. 9, p. 969, 2006
10. Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices
    Journal of Nuclear Science and Technology, vol. 43, no. 10, pp. 1258–1269, 2006
11. European Master of Science in Nuclear Engineering
    Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 165–172, 2005
12. Hierarchic modeling of heat transfer processes in heat exchangers
    International Journal of Heat and Mass Transfer, vol. 48, no. 2, pp. 361–371, 2005
13. Calculation of conjugate heat transfer problem with volumetric heat generation using the Galerkin method
    Applied Mathematical Modelling, vol. 29, no. 5, pp. 477–495, 2005
14. Quantitative assessment of MCP trip transient in a VVER
    Nuclear Engineering and Design, vol. 227, no. 1, pp. 85–96, 2004
15. Effect of axial conduction on the heat transfer in micro-channels
    International Journal of Heat and Mass Transfer, vol. 47, no. 12-13, pp. 2551–2565, 2004
16. Modelling of local two-phase flow parameters in upward subcooled flow boiling at low pressure
    International Journal of Heat and Mass Transfer, vol. 47, no. 6-7, pp. 1499–1513, 2004
17. Wall Properties and Heat Transfer in Near-Wall Turbulent Flow
    Numerical Heat Transfer: Part A: Applications, vol. 46, no. 7, pp. 717–729, 2004
18. Modelling of low-pressure subcooled flow boiling using the RELAP5 code
    Nuclear Engineering and Design, vol. 220, no. 3, pp. 255–273, 2003
19. Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM)
    Nuclear Engineering and Design, vol. 217, no. 1-2, pp. 179–206, 2002
20. A dynamic fault tree
    Reliability Engineering & System Safety, vol. 75, no. 1, pp. 83–91, 2002
21. Component reliability assessment using quantitative and qualitative data
    Reliability Engineering & System Safety, vol. 71, no. 1, pp. 81–95, 2001
22. DNS of Turbulent Heat Transfer in Channel Flow With Heat Conduction in the Solid Wall
    Journal of Heat Transfer, vol. 123, no. 5, p. 849, 2001
23. Fault tree developed by an object-based method improves requirements specification for safety-related systems
    Reliability Engineering & System Safety, vol. 63, no. 2, pp. 111–125, 1999
24. Safety and availability of steam generator tubes affected by secondary side corrosion
    Nuclear Engineering and Design, vol. 185, no. 1, pp. 11–21, 1998
25. Probabilistic safety assessment improves surveillance requirements in technical specifications
    Reliability Engineering & System Safety, vol. 56, no. 1, pp. 69–77, 1997
26. Influence of specific data on a research reactor probabilistic model
    Reliability Engineering & System Safety, vol. 52, no. 1, pp. 55–63, 1996
27. Analysis of operator actions during the accident caused by total loss of secondary heat sink
    Nuclear Engineering and Design, vol. 159, no. 2-3, pp. 169–175, 1995
28. Feed-and-bleed procedure mitigating the consequences of a steam generator tube rupture accident
    Nuclear Engineering and Design, vol. 154, no. 1, pp. 51–59, 1995
29. Propagation of stress corrosion cracks in steam generator tubes
    International Journal of Pressure Vessels and Piping, vol. 63, no. 1, pp. 35–43, 1995
30. On the risk-based steam generator lifetime optimisation
    Theoretical and Applied Fracture Mechanics, vol. 23, no. 2, pp. 129–137, 1995
31. Application of first and second order reliability methods in the safety assessment of cracked steam generator tubing
    Nuclear Engineering and Design, vol. 147, no. 3, pp. 359–368, 1994
32. Mixture continuum formulation of convection-conduction energy transport in multiconstituent solid-liquid phase change systems for BEM solution techniques
    Engineering Analysis with Boundary Elements, vol. 11, no. 2, pp. 109–117, 1993