Perez, R., and Golbabai, M., 1995, .
Lee, J. K., and Han, B. S., 1998, “Modeling of Core Protection and Monitoring System for PWR Nuclear Power Plant Simulator,” Ann. Nucl. Energy, 25(7), pp. 409–420.
10.1016/S0306-4549(97)00075-3Kim, H. C., and Chang, S. H., 1997, “Development of a Back Propagation Network for One-Step Transient DNBR Calculations,” Ann. Nucl. Energy, 24(17), pp. 1437–1446.
10.1016/S0306-4549(97)00051-0Lee, G. C., and Chang, S. H., 2003, “Radial Basis Function Networks Applied to DNBR Calculation in Digital Core Protection Systems,” Ann. Nucl. Energy, 30, pp. 1561–1572.
10.1016/S0306-4549(03)00099-9Chang, S. H., and Baek, W. P., 2003, “Understanding, Predicting and Enhancing Critical Heat Flux,” 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea.
Yang, S. H., Chung, Y. J., and Kim, H. C., 2005, “Assessment of the MDNBR Enhancement Methodologies for the SMART Control Rods Banks Withdrawal Event,” Ann. Nucl. Energy, 32, pp. 1567–1583.
10.1016/j.anucene.2005.04.009Yasinsky, J. B., and Henry, A. F., 1965, “Some Numerical Experiments Concerning Space-Time Reactor Kinetics Behavior,” Nucl. Sci. Eng., 22, pp. 171–181.
Stacy, W. M., 1968, “A Variational Multichannel Space-Time Synthesis Method for Nonseparable Reactor Transients,” Nucl. Sci. Eng., 34(1), pp. 45–56.
Adams, C. H., and Stacy, W. M., 1967, “RAUMZEIT: A Program to Solve Coupled Time Dependent Diffusion Equations in One Space Dimension,” .
Fuller, E. L., Meneley, D. A., and Hetrick, D. L., 1970, “Weighted Residual Methods in Space Dependent Reactor Dynamics,” Nucl. Sci. Eng., 40(2), pp. 206–223.
Ott, K. O., and Meneley, D. A., 1969, “Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics,” Nucl. Sci. Eng., 36(3), pp. 402–411.
10.13182/NSE36-402Meneley, D. A., Ott, K. O., and Wiener, E. S., 1967, “Space Time Kinetics,” .
Diamond, D. J., et al. , 2001, “Intercomparison of Results for a PWR Rod Ejection Accident,” Nucl. Eng. Des., 208, pp. 181–189.
[CrossRef]Nakajima, T., 2002, “Realistic Analysis of RIA in PWR and BWR,” Proceedings of the Topical Meeting on RIA, Aix-en-Provence, France.
Riverola, J., Nunez, T., and Vicente, J., 2004, “RIA Analysis for PWR at Both HZP and HFP Operation and All Cycle Fuel Exposure with 3D Techniques,” Proceedings of the 2004 International Meeting on LWR Fuel Performance, Orlando, FL.
Kozlowski, T., and Downar, T. J., 2007, “PWR MOX/UO2 Core Transient Benchmark,” OECD/NEA No. 6048, NEA/NSC/DOC(2006)20.
Grgic, D., Bencik, V., and Sadek, S., 2013, “Coupled Code Calculation of Rod Withdrawal at Power Accident,” Nucl. Eng. Des., 261, pp. 285–305.
10.1016/j.nucengdes.2012.10.026Gensler, A., Kuhnel, K., and Kuch, S., 2015, “PWR Core Safety Analysis with 3-Dimensional Methods,” Ann. Nucl. Energy, 84, pp. 131–139.
10.1016/j.anucene.2014.11.006Turinsky, P. J., Al-Chalabi, R. M. K., Engrand, P., Sarsour, H. N., Faure, F. X., and Guo, W., 1994, “NESTLE: Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady State and Transient Problems,” Electric Power Research Center, North Carolina State University, Raleigh, NC.
Grundmann, U., and Rohde, U., 1996, “DYN3D—3-Dimensional Core Model for Steady-State and Transient Analyses of Thermal Reactors,” International Conference on the Physics of Reactors PHYSOR 96, Mito, Ibaraki, Japan.
Ivanov, K. N., Macian-Juan, R., Irani, A., and Baratta, A. J., 1999, “Features and Performance of a Coupled Three-Dimensional Thermal-hydraulic/Kinetics TRAC-PF1/NEM PWR Analysis Code,” Ann. Nucl. Energy, 26, pp. 1407–1417.
10.1016/S0306-4549(99)00017-1Downar, T., Lee, D., Xu, Y., and Kozlowski, T., 2004, “PARC v2.6: U.S. NRC Core Neutronics Simulator, Theory Manual,” Purdue University, West Lafayette, IN.
Kereszturi, A., et al. , 2003, “Development and Validation of the Three-Dimensional Dynamic Code KIKO3-D,” Ann. Nucl. Energy, 30, pp. 93–120.
10.1016/S0306-4549(02)00043-9Obaidurrahman, K., Doshi, J. B., Jain, R. P., and Jagannathan, V., 2010, “Development and Validation of Coupled Dynamics Code TRIKIN for VVER Reactors,” Nucl. Eng. Technol., 42(3), pp. 259–270.
10.5516/NET.2010.42.3.259Fraikin, R., and Finnemann, H., 1993, “NEA-NSC 3-D/1-D PWR Core Transient Benchmark: Uncontrolled Withdrawal of Control Rods at Zero Power, Final Specifications,” .
Jagannathan, V., Singh, T., Pal, U., Karthikeyan, R., and Sundaram, G., 2006, “Validation of Finite Difference Core Diffusion Calculation Methods with FEM and NEM for VVER-1000 MWe Reactor,” PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, BC, Canada.
Sanchez, J., 1989, “On the Numerical Solution of the Point Reactor Equations by Generalized Runge-Kutta Methods,” Nucl. Sci. Eng., 103(1), pp. 94–99.
Obaidurrahman, K., 2011, “Spatial Instability Analysis in Large Light Water Reactors,” Ph.D. thesis, Department of Energy Science and Engineering, Indian Institute of Technology Bombay, Mumbai, India.
Jain, R. P., and Obaidurrahman, K., 2012, “Validation of 3D Kinetics Code TRIKIN Using OECD PWR Core Transient Benchmark,” Int. J. Nucl. Energy Sci. Technol., 7(2), pp. 131–142.
10.1504/IJNEST.2012.048814Todreas, N. E., and Kazimi, M. S., 1990, Nuclear Systems-I: Thermal Hydraulic Fundamentals, Hemisphere Publishing, New York.
