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Application of SAXS to the study of microporosity of graphitic materials for high‐temperature nuclear reactors
Author(s) -
Krautwasser P.,
Koizlik K.,
Nickel H.,
Koss P.,
Ruland W.
Publication year - 1974
Publication title -
journal of applied crystallography
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.429
H-Index - 162
ISSN - 1600-5767
DOI - 10.1107/s0021889874009368
Subject(s) - porosity , graphite , materials science , irradiation , nuclear fission product , nuclear graphite , fission products , nuclear fission , diffusion , chemical engineering , matrix (chemical analysis) , porous medium , fission , composite material , radiochemistry , chemistry , nuclear physics , thermodynamics , neutron , physics , engineering
Measurements of microporosity changes in graphitic materials for high‐temperature reactors – pyrocarbon, graphite and matrix materials – during heat treatment and irradiation were expected to be of interest because of the following reasons: ( a ) porosity and pore‐size distribution seem to be primarily responsible for fission‐product transport, ( b ) irradiation experiments show a strong influence of density, i.e. of porosity, on the irradiation behaviour.