The stochastic behavior of the eigenvalue due to spatial perturbation in the fuel distribution of the one-speed slab reactor

Nuclear Science and Engineering

Volumn 130, Issue 1, 1998, Pages 85-97

  Jahshan, Salim N ^a  

^a NONE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0001904170     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE98-A1992     Document Type: Article

References (21)

1. M. M. R. WILLIAMS, "The Effects of Random Material Density on Reactor Criticality." Atomkernenergie, 22, 248 (1974)
2. M. M. R. WILLIAMS, Random Processes in Nuclear Reactors, Pergamon Press, Elmsford, New York (1974).
3. E. G. SAKHNOVSKII. Atomnaya Energiya, 42, 2, 141 (1977) (in Russian); see also Sov. J. At. Energy, for English translation.
4. E. G. SAKHNOVSKII. Atomnaya Energiya, 42, 2, 141 (1977) (in Russian); see also Sov. J. At. Energy, for English translation.
5. M. M. R. WILLIAMS, "Stochastic Processes in Nuclear Reactors," SCOPE Series on Random Processes, CNEN, Rome, Italy (1980).
6. A. D. GALANIN, Atomnaya Energiya, 60, 4, 267 (1986) (in Russian); see Sov. J. At, Energy for English translation.
7. A. D. GALANIN, Atomnaya Energiya, 60, 4, 267 (1986) (in Russian); see Sov. J. At, Energy for English translation.
8. E. G SAKHNOVSKY, "Comments on 'The Effect of Random Material Density on Reactor Criticality,'" Nucl. Sci. Eng., 104, 197 (1990).
9. M. M. R. WILLIAMS, "Additional Comments on 'The Effect of Random Material Density on Reactor Criticality,'"' Nucl, Sci. Eng., 104, 198 (1990).
10. G. C. POMRANING, "The Effect of Random Material Density on Reactor Criticalily,'" Nucl. Sci. Eng., 108, 325 (1991).
11. G. C. POMRANING, Linear Kinetic Theory and Particle Transport in Stochastic Mixtures. World Scientific. Singapore (1991).
12. "MCNP - A General Monte Carlo N-Particle Transport Code," Version 4A, I.A-12625-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (Nov. 1993).
13. S. N. JAHSHAN, C. A. WEMPLE, and B. D. GANAPOL, "Comparison of Analytical Transport and Stochastic Solutions for Neutron Slowing Down in an Infinite Medium," Proc. Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe, Germany, April 1993, p. 742.
14. B. D. GANAPOL. D. W. NIGG, S. N. JAHSHAN. and C. A. WEMPLE, "The Searchlight Problem for Neutrons in Semi-Infinite Medium," Proc. Mathematical Methods and Supercomputing in Nuclear Applications. Karlsruhe, Germany, April 1993,p. 137.
15. B. D. GANAPOL, D. E. KORNREICH, J. A. DAHL, D. W. NIGG, S. N. JAHSHAN, and C. A. WEMPLE. "The Searchlight Problem for Neutrons in a Semi-Infinite Medium," Nucl. Sci. Eng., 118, 38 (1994).
16. N One Speed Transport Solution in a Heterogeneous Slab to a Monte Carlo Energy independent Solution,"' Proc. Topl. Mtg. Radiation Protection and Shielding, North Falmouth, Massachusetts, April 21-25, 1996, Vol. 1,p. 353, American Nuclear Society (1996).
17. G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, Van Nostrand Reinhold (1970).
18. R C. SINGLETERRY, Jr., "Neutron Transport Associated with the Galactic Cosmic Ray Cascade," Doctoral Dissertation, University of Arizona (1993).
19. W. W, ENGLE, Jr., "A Users Manual for ANISN, A One-Dimensional Discrete Ordinate Transport Code with Anisotropie Scattering," K-1693, Oak Ridge National Laboratory (1967).
20. R. SANCHEZ, O. ZUCHUAT, F. MALVAGI, and I. ZMIJAREVIC. "Symmetry and Translations in Mathematical Line Statistics," J. Quant. Spectrosc. Radiat. Transfer. 51, 801 (1994).
21. W. H. PRESS, S. A. TEUKOLOSKY, W.T. VERTERLING, and B. P. FLANNERY. Numerical Recipes in FOSTRAN - The Art of Scientific Computing, Cambridge Press (1992).