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108    CHAPTER 9 Space-time kinetics





                         9.4 Calculation requirements
                         Planning and operating a nuclear power reactor requires a detailed knowledge of the
                         spatial neutron flux and reaction rates. Both steady-state and transient analyses are
                         required. Enumerating the conditions to be analyzed and the information needed for
                         performing the analyses illustrates the enormity of the problem.
                            A typical light water reactor contains as many as 40,000 or more individual fuel
                         rods. As the reactor operates, the composition of the rods changes significantly.
                         Operation depletes fissile material, produces new fissile material, produces fission
                         products, and produces actinides. The concentrations of all of these materials depend
                         on neutron flux at all positions during prior reactor operation. The flux depends on
                         the localized isotopic concentrations, history of power generation, and history of
                         control rod positions. The fuel rods typically stay in the reactor for four years in light
                         water reactors and are moved during refueling. It is necessary to calculate the local
                         isotope concentrations before a new neutron diffusion calculation of the new flux
                         distribution can begin. The nuclear cross sections of all of the isotopes must be
                         known because they influence the neutron population and must be addressed in a
                         detailed analysis. It is clear that the analyst must know the concentrations of hun-
                         dreds of isotopes at hundreds of positions.
                            Reactivity feedback must be addressed along with neutron diffusion in a power
                         reactor space-time analysis. Space-dependent feedbacks occur simultaneously with
                         space-dependent power changes and these feedbacks alter the power distribution.
                         Therefore, a comprehensive simulation would require modeling the feedback pro-
                         cesses simultaneously with the neutronics.





                         9.5 Computer software
                         Powerful software provides computational capability for reactor analysis using
                         Boltzmann transport theory or neutron diffusion theory. The elementary theory pre-
                         sented above serves to help understand the phenomena that occur in a reactor rather
                         than to provide a basis for practical computations. But users of the available software
                         must understand the underlying phenomena for proper interpretation of computed
                         results.




                         9.6 Models and computational methods
                         Space-time models usually rely on the multi-group neutron diffusion equations.
                         Independent variables include time, group energies, and one to three position coor-
                         dinates. Various methods have been developed to solve the equations. These
                         methods include the following:
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