Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 439-448
Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25540
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The use of B4C for the control of a sodium-cooled reactor is considered from a design standpoint. Nuclear, mechanical, and physical properties as well as irradiation data are presented. The ability of the B4C lattice structure to retain helium produced from the neutron capture of B10 is discussed.