Application of SAXS to the study of microporosity of graphitic materials for high‐temperature nuclear reactors | Zendy

Krautwasser P. | Zendy; Koizlik K. | Zendy; Nickel H. | Zendy; Koss P. | Zendy; Ruland W. | Zendy

AI Assistant Blog Pricing

Home ZAIA Blog

Premium

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.

This content is not available in your region!

Continue researching here.

Having issues? You can contact us here

Accelerating Research