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3. Neutron Flux and Importance Distribution by Collision Method, Starting from a Generalized Source
4. H. MITANI and H. KUROI, “Sensitivity Coefficient of Integral Data and Generalized Perturbation Method,” JAERI-M-4760, Japan Atomic Energy Research Institute (1972)(in Japanese).
5. M. F. JAMES and J. D. MATTHEWS, “A Perturbation Method Multigroup Neutron Transport Calculations in Plane Lattices,” AEEW-R-219, U.K. Atomic Energy Authority, Harwell (1962).