TWO-GROUP CONSTANTS FOR REACTOR MATERIALS

descriptionPublicationkeyboard_double_arrow_right Report , Other literature type 01 May 1958 United States Publisher:Office of Scientific and Technical Information (OSTI)

Authors: Stanley, Mary J.;

doi: 10.2172/4144648

TWO-GROUP CONSTANTS FOR REACTOR MATERIALS

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Abstract

In order to facilitate reactor design studies a compilation of calculated two-group constants averaged over the infinite-medium flux produced by a fission source was made for approximately 80 materials of interest to reactor engineers. A comparison with available experimental age measurements is included. (auth)

Country

United States

Related Organizations

University of North Texas
United States
Oak Ridge National Laboratory
United States

Keywords

Fission, Neutron Flux, Slowdown, Fissionable Materials, Physics, Fermi Age, Reactors, Mathematics

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