On the problem of criticality with a feedback
19th Symposium of AER on VVER Reactor Physics and Reactor Safety (2009, Varna, Bulgaria)
Spectral and Core Calculations
In this contribution, the problem of criticality for neutron transport equation is studied. It is assumed that the medium considered is moving in general while its temperature, density and velocity are part-by part continuous functions of the space variables. Next it is supposed that effective cross-sections of neutron scattering, absorption and of fission are either real functions or distributions of neutron velocity and of medium temperature and velocity.
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