References
- C. P. REDDY et al., “Comparison of Measured and Calculated Core Parameters in FBTR Using Different Cross Section Sets,” presented at Indo-USSR Seminar on FBR Core Physics, Kalpakkam, India, March 1990; see also S. M. LEE et al., “Core Physics Parameters Measured in the Carbide Fuelled Fast Breeder Test Reactor,” presented at Int. Conf. Physics of Reactor Operation Design and Computation, Marseilles, France, April 23–26, 1990.
- G. R. KEEPIN, Physics of Nuclear Kinetics, Addison-Wesley Publishing Co., Reading, Massachusetts (1956).
- R. J. TUTTLE, “Delayed-Neutron Data for Reactor-Physics Analysis,” Nucl. Sci. Eng., 56, 37 (1976).
- M. C. BRADY and T. R. ENGLAND, “Delayed Neutron Data and Group Parameters for 43 Fissioning Systems,” Nucl. Sci. Eng., 103, 129 (1989).
- T. R. ENGLAND, M. C. BRADY, and B. F. RIDER, “Recent Advances in the U.S. Fission Yield and Delayed Neutron Evaluations,” Trans. Am. Nucl. Soc., 92, 508 (1992).
- D. J. HUGHES et al., Phys. Rev., 73, 111 (1948).
- S. A. COX, “Delayed Neutron Data-Review and Evaluation,” ANL/NDM-5, Argonne National Laboratory (1974); Updated for ENDF/B-V by R. E. KAISER and S. G. CARPENTER (unpublished).
- T. R. ENGLAND, W. B. WILSON, R. E. SCHENTER, and F. M. MANN, “Aggregate Delayed Neutron Intensities and Spectra Using Augmented ENDF/B-V Precursor Data,” Nucl. Sci. Eng., 85, 139 (1983).
- “Nuclear Safeguards Research and Development — Program as Status Report April–June 1969,” LA-4227-MS, G. R. KEEPIN, Ed., Los Alamos National Laboratory (1969).
- F. M. MANN et al., “Evaluation of Delayed Neutron Emission Probabilities,” Nucl. Sci. Eng., 87, 418 (1984).
- S. M. LEE et al., “Specifications for the Computer Code ALCIALMI,” Internal Report FBTR/01100/70/N7, IGCAR, Kalpakkam (1970).
- T. M. JOHN, “NEWPERT—Perturbation Code for Two Dimensional Diffusion Equation,” Internal Report, REDG/01150/RP-253, IGCAR, Kalpakkam (1984).
- V. GOPALAKRISHNAN and P. MOHANAKRISHNAN, “Average Delayed Neutron Fractions from ENDF/B-VI,” RG/RPD/NDS/50, IGCAR, Kalpakkam (Dec. 1992).
- L. G. LeSAGE et al., “International Comparison Calculation of a Large Sodium Cooled Fast Breeder Reactor,” Proc. Specialist Mtg. Int. Comparison Calculation of a Large Sodium Cooled Fast Breeder Reactor, Argonne, Illinois, February 1978, ANL-80-78, Argonne National Laboratory (1980).
- N. SATHYABAMA, P. MOHANAKRISHNAN, and S. M. LEE, “Comparison of Transport and Diffusion Theory Analysis with Experimental Results in FBTR,” Proc. Int. Conf. Reactor Physics and Reactor Computations, Tel Aviv, Israel, January 23–26, 1994.
- G. D. SPRIGGS, “In-Pile Measurement of the Decay Constants and Relative Abundances of Delayed Neutrons,” Nucl. Sci. Eng., 114, 342 (1993).