Articles in Scholarly Journals [Incomplete List]

1. Utilization of two-dimensional deterministic transport methods for analysis of pebble-bed reactors
   Annals of Nuclear Energy, vol. 34, no. 5, pp. 396–405, 2007
2. Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis
   Annals of Nuclear Energy, vol. 34, no. 6, pp. 501–513, 2007
3. The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems
   Nuclear Engineering and Design, vol. 236, no. 5-6, pp. 657–668, 2006
4. Development of enriched Gd-155 and Gd-157 burnable poison designs for a PWR core
   Annals of Nuclear Energy, vol. 33, no. 5, pp. 439–445, 2006
5. Application of genetic algorithms to optimize burnable poison placement in pressurized water reactors
   Annals of Nuclear Energy, vol. 33, no. 5, pp. 446–456, 2006
6. Sensitivity study on determining an efficient set of fuel assembly parameters in training data for designing of neural networks in hybrid genetic algorithms
   Annals of Nuclear Energy, vol. 33, no. 5, pp. 457–465, 2006
7. Evaluation and enhancement of COBRA-TF efficiency for LWR calculations
   Annals of Nuclear Energy, vol. 33, no. 9, pp. 837–847, 2006
8. Modeling and optimization of existing beam port facility of PSBR
   Annals of Nuclear Energy, vol. 33, no. 17-18, pp. 1391–1395, 2006
9. OECD/DOE/CEA VVER-1000 coolant transient (V1000CT) benchmark – A consistent approach for assessing coupled codes for RIA analysis
   Progress in Nuclear Energy, vol. 48, no. 8, pp. 728–745, 2006
10. Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models
    Progress in Nuclear Energy, vol. 48, no. 8, pp. 746–763, 2006
11. 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
12. Introduction to the special issue on the OECD/DOE/CEA V1000CT-1 benchmark
    Progress in Nuclear Energy, vol. 48, no. 8, pp. 727–727, 2006
13. Simulation of the VVER-1000 pump start-up experiment of the OECD V1000CT benchmark with CATHARE and TRAC-PF1
    Progress in Nuclear Energy, vol. 48, no. 8, pp. 922–936, 2006
14. Development of the VVER core loading optimization system
    Annals of Nuclear Energy, vol. 31, no. 7, pp. 747–772, 2004
15. Minimizing the gamma radiation effects to spent fuel pool walls
    Annals of Nuclear Energy, vol. 31, no. 5, pp. 459–480, 2004
16. Helios, current coupling collision probability method, applied for solving the NEA C5G7 MOX benchmark
    Progress in Nuclear Energy, vol. 45, no. 2-4, pp. 119–124, 2004
17. Investigation of spatial coupling aspects for coupled code application in PWR safety analysis
    Annals of Nuclear Energy, vol. 30, no. 2, pp. 189–209, 2003
18. Developing and modeling of the “Laguna Verde” BWR CRDA benchmark
    Annals of Nuclear Energy, vol. 29, no. 5, pp. 585–593, 2002
19. Improved cross-section modeling methodology for coupled three-dimensional transient simulations
    Annals of Nuclear Energy, vol. 29, no. 8, pp. 937–966, 2002
20. HELIOS: analysis of MOX critical experiments
    Annals of Nuclear Energy, vol. 29, no. 14, pp. 1633–1640, 2002
21. Temporal adaptive algorithm for TRAC-BF1/NEM/COBRA-TF coupled calculations in BWR safety analysis
    Annals of Nuclear Energy, vol. 29, no. 18, pp. 2127–2141, 2002
22. TRAC-BF1/NEM stability methodology for BWR core wide and regional stability analysis
    Annals of Nuclear Energy, vol. 27, no. 11, pp. 985–994, 2000
23. TRAC-BF1/NEM Modeling and results of OECD/NEA BWR core transient benchmarks
    Annals of Nuclear Energy, vol. 27, no. 12, pp. 1051–1058, 2000
24. Improved verification methodology for TRAC-PF1/NEM using NEA/OECD core transient benchmarks
    Annals of Nuclear Energy, vol. 27, no. 14, pp. 1319–1331, 2000
25. Statistical methods used for code-to-code comparisons in the OECD/NRC PWR MSLB benchmark
    Annals of Nuclear Energy, vol. 27, no. 17, pp. 1589–1605, 2000
26. Nodal kinetics model upgrade in the Penn State coupled TRAC/NEM codes
    Annals of Nuclear Energy, vol. 26, no. 13, pp. 1205–1219, 1999
27. Features and performance of a coupled three-dimensional thermal-hydraulic/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code
    Annals of Nuclear Energy, vol. 26, no. 15, pp. 1407–1417, 1999
28. Comparative study of a boron dilution scenario in VVER reactors
    Annals of Nuclear Energy, vol. 26, no. 15, pp. 1331–1339, 1999
29. Comparative analysis of WWER-1000 benchmark calculations and improvements in hexagonal-Z diffusion methodology
    Annals of Nuclear Energy, vol. 25, no. 1-3, pp. 83–95, 1998
30. Numerical diffusion and the tracking of solute fields in system codes Part III. Application to a boron dilution transient analysis in the AP600
    Nuclear Engineering and Design, vol. 179, no. 3, pp. 345–356, 1998
31. An effective solution scheme of a three-dimensional reactor core model in hexagonal geometry
    Computer Physics Communications, vol. 82, no. 1, pp. 1–16, 1994