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Estimation of heat sources in nuclear reactors
Author(s) -
Alexander Lloyd G.
Publication year - 1956
Publication title -
aiche journal
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.958
H-Index - 167
eISSN - 1547-5905
pISSN - 0001-1541
DOI - 10.1002/aic.690020210
Subject(s) - heat flux , neutron flux , nuclear engineering , dissipation , neutron temperature , nuclear reactor , flux (metallurgy) , nuclear fission , nuclear physics , neutron , thermal , heat transfer , fission , mechanics , physics , chemistry , thermodynamics , engineering , organic chemistry
Knowledge of local heating rates is needed for estimation of operating temperatures, thermal stresses, and cooling requirements in nuclear reactor components. Heat is liberated by the dissipation of the energy of fission fragments, beta particles, fast neutrons, and gamma photons. Heating rates are formulated in terms of either neutron or gamma flux densities, the corresponding collision probabilities, and appropriate energy transfer coefficients, the forms of which are given. Special methods of estimating the flux densities are discussed. The data on the magnitudes of the various energy sources are reviewed.