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Boron Concentration Gradient for Improved Thermal Reactor Performance of Boron-Stainless-Steel Control Rods

R. J. Beaver, A. E. Richt

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 187-196

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31185

An experimental plate-type neutron absorber assembly containing 10B dispersed in Type 200 austenitic stainless steel was irradiated in the active lattice of the 10 MW-SM-1 Reactor for 1.2 full power years. The 10B was distributed in a concentration gradient, increasing from 1 wt% in the surface layer to a maximum of 3 wt% 0.024 in. below the surface, to ensure a uniform burnup of 10B atoms in each volume increment through an exposure to thermal neutrons resulting in an average 10B burnup of 20 at.%. Postirradiation evaluation did not reveal any significant dimensional changes or structural damage to the dispersions at this burnup, which is a demonstration that the use of the boron concentration gradient results in at least a fourfold increase in the reactor performance capability of plate-type neutron absorbers containing dispersions of 10B in stainless steel.