Functional Investigation and Kernel Expansion Technique for the System of Integral Equations Governing the Stationary Anisotropic Transport of Monoenergetic Neutrons in Three-dimensional Media

摘要

While in the early stage of historical development of nuclear reactor design neutron calculations had to be perfor¬med by using very simple codes, mainly based on neutron diffusion theory, at the present time the optimization of many features in nuclear power plants, like e.g. efficiency, reliabi¬lity and safety, requires a much greater accuracy in evalua¬ting the neutron flux distribution.nThis problem is of basic practi¬cal interest in nuclear reactor theory and outlines the ac¬tual physical situation very closely especially when multi-group approach is adopted;nevertheless a rigorous treatment and satisfactory solution for this problem is still lacking.