References
- Smith , K. S. 1985 . “QPANDA: An advanced nodal method for LWR analyses” . Trans. Am. Nucl. Soc. , 50 : 532
- Smith , K. S. 1986 . “Assembly homogenization techniques for light water reactor analysis” . Prog. Nucl. Energy , 17 ( 3 ) : 303
- Kosaka , S. Saji , E. 2000 . “Enhancements of BWR core analysis code” . In Proc. Advances in Reactor Physics and Mathematics and Computation into the Next Millennium Pittsburgh , Pennsylvania CD-ROM
- Tatsumi , M. and Yamamoto , A. 2003 . “Advanced PWR core calculation based on multi-group nodal-transport method in three-dimensional pin-by-pin geometry” . J. Nucl. Sci. Technol. , 40 ( 6 ) : 376
- Okumura , K. Mori , T. 2000 . “Validation of a continuous-energy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment” . J. Nucl. Sci. Technol. , 37 ( 2 ) : 128
- Kosaka , S. and Takeda , T. 2004 . “Verification of 3D heterogeneous core transport calculation utilizing non-liner iteration technique” . J. Nucl. Sci. Technol. , 41 ( 6 ) : 645
- Joo , H. G. Kim , H. Y. 2003 . “Effectiveness of the whole core transport calculation with pin-wise thermal feedback” . In Proc. Advances in Nuclear Fuel Management III(ANFM 2003) Hilton Head Island , , USA Oct. 5–8, CD-ROM
- Knott , D. G. and Edenius , M. 1993 . “Validation of the CASMO-4 transport solution” . In Proc. Math. Methods and Supercomputing in Nuclear Application Vol. 2 , Karlsruhe , , Germany 547
- Smith , K. S. and Rhodes , J. 2000 . “CASMO-4 characteristics methods for two-dimensional PWR and BWR core calculations” . Trans. Am. Nucl. Soc. , 83 : 322