References
- M. M. R. WILLIAMS, “The Effect of Random Geometry on the Criticality of a Multiplying System,” Ann. Nucl. Energy, 27, 143 (2000).
- M. M. R. WILLIAMS, “The Effect of Random Geometry on the Criticality of a Multiplying System II: Extension to Resonance Absorption,” Ann. Nucl. Energy, 27, 517 (2000).
- R. C. LLOYD, “Buckling Measurements of Fuel Elements in Random Arrays,” HW-57853, U.S. Atomic Energy Commission/General Electric (1958).
- R. V. MEGHREBLIAN and D. K. HOLMES, Reactor Analysis, McGraw-Hill Book Company, New York (1960).
- A. D. GALANIN, Thermal Reactor Theory, Pergamon Press, Oxford, United Kingdom (1960).
- W. A. HORNING, “A Summary of Small Source Theory Applied to Thermal Reactors,” HW-34021, U.S. Atomic Energy Commission/General Electric (1954).
- J. D. STEWART, “AMicroscopic-Discrete Theory of Thermal Neutron Piles,” NEI-13, Atomic Energy of Canada Ltd. (1952), re-issued as AECL-1470 (1962).
- P. M. MORSE and H. FESHBACH, Methods of Theoretical Physics, Part I, McGraw-Hill Book Company, New York (1953).
- IMSL Library of Subroutines, Visual Numerics, United States of America (1998).
- J. R. LAMARSH, Introduction to Nuclear Engineering, 2nd ed., Addison-Wesley, Reading, Massachusetts (1983).
- M. M. R. WILLIAMS, “On Galanin’s Constant in the Source-Sink Method,” Ann. Nucl. Energy, 29, 385 (2002).
- E. INONU, “On the Definition of the Extrapolated Surface for Bare Homogeneous Thermal Reactors,” Proc. 2nd Int. Conf. Peaceful Uses of Atomic Energy, Vol. 16, p. 701 (1958).
- M. M. R. WILLIAMS, “On a Probability Distribution Function Arising in Stochastic Neutron Transport Theory,” J. Phys. A, 34, 4653 (2001).
- J. B. KELLER, “Stochastic Equations and Wave Propagation in Random Media,” Proc. Symp. Appl. Math., 16, 145 (1964).
- U. FRISCH, Probabilistic Methods in Applied Mathematics, Vol. 1, A. T. BHARUCHA-REID, Ed., Academic Press, New York (1968).
- A. RADKOWSKY, Naval Reactors Physics Handbook, Vol. 1, U.S. Atomic Energy Commission (1964).
- A. V. STEPANOV, “Neutron Transfer Theory for Inhomogeneous Media,” Proc P.N. Lebedev Phys. Inst., 44, 193 (1971).
- M. M. R. WILLIAMS, Random Processes in Nuclear Reactors, Pergamon Press, Oxford, United Kingdom (1974).
- G. C. POMRANING, Linear Kinetic Theory and Particle Transport in Stochastic Mixtures, World Scientific, River Edge, New Jersey (1991).
- H. VAN DAM, “Reactivity Effects and Space Domain Noise Caused by Randomly Dispersed Materials in a Reactor Core,” Prog. Nucl. Energy, 1, 273 (1977).
- S. YAMADA, M. NISHIMURA, and K. SUMITA, “Reactivity Effects and Flux Perturbations due to Spatial Random Dispersal in the Number Densities of Core Materials,” Ann. Nucl. Energy, 7, 561 (1980).
- S. YAMADA, C. YAMAGOE, and K. SUMITA, “Analysis of the Reactivity Effect of Spatial Noise in the Framework of Two-Group Diffusion Theory,” Ann. Nucl. Energy, 7, 655 (1980).
- F. C. DIFILIPPO, “Application of the Theory of Random Matrices to a Reactor Noise Problem,” Ann. Nucl. Energy, 9, 532 (1982).
- F. C. DIFILIPPO, “Probability Distributions for First Neighbour Distance Between Resonances That Belong to Two Different Families,” Ann. Nucl. Energy, 21, 219 (1994).
- M. M. R. WILLIAMS, “Neutron Transport in Spatially Random Media: An Assessment of the Accuracy of First Order Smoothing,” Nucl. Sci. Eng., 135, 123 (2000).
- M. M. R. WILLIAMS and E. W. LARSEN, “Neutron Transport in Spatially Random Media: Eigenvalue Problems,” Nucl. Sci. Eng., 139, 66 (2001).
- C. E. PORTER, Statistical Theories of Spectra: Fluctuations, Academic Press, New York (1965).
- T. T. SOONG and J. L BOGDANOFF, “On the Natural Frequencies of a Disordered Linear Chain of N Degrees of Freedom,” Int. J. Mech. Sci., 5, 237 (1963).
- M. M. R. WILLIAMS, “The Interaction Effect Between Two Neutron Absorbers Using Wallace’s Method,” Can. J. Phys., 78, 1035 (2000).
- M. M. R. WILLIAMS, “Transport Theory Corrections to the Source-Sink Method for Reactor Lattice Calculations,” Ann. Nucl. Energy, 27, 1695 (2000).
- T. AUERBACH, “Heterogeneous Theory of Finite Reflected Lattices 1. Two-Dimensional Multigroup Theory with One Thermal Group and Flux Independent Cross Section,” Institute for Reactor Research, Wurenligen, Switzerland, EIR Bericht Nr 100 (1967).
- S. UKAI, “A Study of Approximate Methods for Calculating the Neutron Flux in a Heterogeneous Reactor,” J. Nucl. Energy, 24, 479 (1970).
- W. MAGNUS, F. OBERHETTINGER, and R. P. SONI, Formulas and Theorems for the Special Functions of Mathematical Physics, 3rd ed., Springer-Verlag, New York (1966).