참고문헌
- H. G. Joo, D. Barber, G. Jiang, and T. Downar, "PARCS: A Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method," PUNE- 98-26, Purdue University (1998).
- N. Crouzet and P. Turinsky, "A Second-Derivative-Based Adaptive Time-Step Method for Spatial Kinetics Calculations," Nucl. Sci. Eng., 123, 206 (1996). https://doi.org/10.13182/NSE96-A24183
- A. E. Aboanber, Y. M. Hamada, "Generalized Runge-Kutta method for two- and three-dimensional space-time diffusion equation, Ann. Nucl. Energy, 35, 1024-1040 (2008). https://doi.org/10.1016/j.anucene.2007.10.008
- C.W. Gear, "The Simultaneous Numerical Solution of Differential-Algebraic Equations," IEEE Trans. Circuit Theory, TC 18 (1) 89-95 (1971). https://doi.org/10.1109/TCT.1971.1083221
- L. F. Shampine, "Numerical solution of ordinary differential equations," p. 181, Chapman & Hall (1994).
- Y. A. Chao and A. Attard, "A Resolution of the Stiffness Problem of Reactor Kinetics," Nucl. Sci. Eng., 90, 40-46 (1985). https://doi.org/10.13182/NSE85-A17429
- D. Ginestar, G. Verdu, V. Vidal, R. Bru, J. Marin, and J. L. Munoz-Cobo, "High order backward discretization of the neutron diffusion equation", Ann. Nucl. Energy, Vol 25, pp. 47-64 (1998). https://doi.org/10.1016/S0306-4549(97)00046-7
- Victor M. Garcia, V. Vidal, G. Verdu, J. Garayoa, and R. Miro, "Parallel Resolution of the Two-Group Time Dependent Neutron Diffusion Equation with Public Domain ODE Codes", Lecture Note in Computer Science, Vol. 3402, pp. 457-497 (2005).
- Alan C. Hindmarsh, Peter N. Brown, Keith E. Grant, Steven L. Lee, Radu Serban, Dan E. Shumaker, and Carol S. Woodward, "SUNDUALS : Suite of Nonlinear and Differential/Algebraic Equation Solvers", ACM Transactions on Mathematical Software, Vol. 31, No. 3, PP 363-396 (2005). https://doi.org/10.1145/1089014.1089020
- J. I. Yoon and H. G. Joo," Two-Level Coarse Mesh Finite Difference Formulation with Multigroup Source Expansion Nodal Kernels," J. Nucl. Sci. Technol., 45, 668-682 (2008). https://doi.org/10.3327/jnst.45.668
- H. Finnemann and A. Galati, "NEACRP 3D LWR Core Transient Benchmark-Final Specification", NEACRP-L- 335 (Rev. 1), Nuclear Energy Agency Committee on Reactor Physics (1992).
- R. Fraikin, "PWR Benchmark on Uncontrolled Rods Withdrawal at Zero Power," Final Report, NEA/NSC/ DOC(96)20 (1997).
- M. Zhuang and W. Mathis, "Research on Stepsize Control in the BDF Method for Solving Differential-Algebraic Equations," IEEE Proceedings (ISCAS94) 229-232 (1994).
- S. Aoki, T. Suemura, J. Ogawa and T. Takeda, "The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems," J. Nucl. Sci. Technol., 44, 862-868 (2007). https://doi.org/10.3327/jnst.44.862
- M. P. Knight and P. Bryce, "Derivation of a refined PANTHER solution to the NEACRP PWR rod ejection transients," Proc. Joint Int. Conf. Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, N.Y., 302-313 (1997)
피인용 문헌
- Impact of Dynamic Condensation of Energy Groups on Convergence Behavior of One-Node CMFD Method for Neutron Diffusion Problem vol.174, pp.3, 2013, https://doi.org/10.13182/NSE12-27
- Experimental Methods for Developing Kinetic Models for Hydrocracking Reactions with Slurry-Phase Catalyst Using Batch Reactors vol.30, pp.6, 2016, https://doi.org/10.1021/acs.energyfuels.5b01953
- Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code vol.42, pp.1, 2017, https://doi.org/10.1002/er.3828
- Fourier Convergence Analysis of the Infinite Homogenous Multigroup Time-Dependent Boltzmann Transport Equation Using Discrete Ordinates Formulation vol.186, pp.1, 2017, https://doi.org/10.1080/00295639.2016.1272387
- Application of Backward Differentiation Formulas to Neutron Kinetics Problems vol.80, pp.8, 2017, https://doi.org/10.1134/S106377881708018X