Neutron absorbing article and method for manufacture of such...

G - Physics – 21 – F

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G21F 1/10 (2006.01) G21C 19/40 (2006.01)

Patent

CA 1113709

NEUTRON ABSORBING ARTICLE AND METHOD FOR MANUFACTURE OF SUCH ARTICLE ABSTRACT OF THE DISCLOSURE: A neutron absorbing article, preferably in long, thin, flat form, suitable for but not necessarily limited to use in storage racks for spent nuclear fuel at locations between volumes of such stored fuel to absorb neutrons from said spent fuel and prevent uncontrolled nuclear reaction of the spent fuel material, is composed of finely divided boron carbide particles and a solid, irreversibly cured phenolic polymer forming a continuous matrix about the boron carbide particles, in such proportions that at least 6% of B10 from the boron carbide content is present therein. The described structures possess a multiplicity of desirable properties for the` use mentioned, including withstanding thermal cycling from repeated spent fuel insertions and removals, withstanding radiation from said spent nuclear fuel over long periods of time without losing desirable neutron absorbing and physical properties, being sufficiently chemically inert to water so as to retain neutron absorbing properties if brought into contact with it, not being galvanically corroding and being sufficiently flexible so as to withstand operational basis earthquake and safe shutdown earthquake seismic events without loss of neutron absorbing capability and other desirable properties when installed in storage racks for spent nuclear fuel. In preferred embodiments of the invention - 1 - the phenolic polymer is a phenol formaldehyde type polymer, such as a trimethylol phenol formaldehyde type polymer, the boron carbide contains at least 12% of B10, the plate contains from 8.0 to 11.5% thereof, the plate density is 1.6 to 2.1 g./cc. and the proportions of boron carbide (which may be accompanied by limited amounts of certain impurities) and phenol formaldehyde type polymer (preferably free of halogens, mercury, lead and sulfur) are from 20 to 35% of the former and 65 to 80% of the latter. The invention also relates to a plurality of such neutron absorbing articles in a storage rack for spent nuclear fuel and to a method for the manufacture of the articles. In the manufacturing method a portion of the phenol formaldehyde type resin, in liquid state, is mixed with the boron carbide particles, compacted and cured, after which the cured article is impregnated with additional phenol formaldehyde type resin, which is then cured to make the final product.

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