One-step curing method for manufacture of neutron absorbing...

G - Physics – 21 – F

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G21F 1/10 (2006.01) C08K 3/38 (2006.01)

Patent

CA 1114149

ONE-STEP CURING METHOD FOR MANUFACTURE OF NEUTRON ABSORBING PLATES ABSTRACT OF THE DISCLOSURE: A one-step curing method for the manufacture of neutron absorbing articles, such as those of long thin plate form for use in storage racks for spent nuclear fuel, includes curing a mixture of boron carbide particles, phenolic resin in liquid state and phenolic resin in particulate solid form at an elevated temperature to produce a neutron absorbing article containing at least 6% of B10 content from the boron carbide thereof, 60 to 80% of boron carbide particles and 40 to 60% of irreversibly cured phenolic polymer, with the proportion of weight of phenolic resin in liquid state to that of phenolic resin in solid state being within the range of about 1:0.5 to 1:4, the temperature of the cure being in the range of about 130 to 200°C. and the cure being effected over a period of about two to twenty hours. Although the liquid resins that are preferably employed are resols, novolaks plus curing agents are preferred solid resins. Because of the use of solid resin, in particulate form, together with the resin in liquid state, the neutron absorbing articles made include better bonds between the polymer and the boron carbide particles than would be obtainable by using the normally solid resin only and the phenolic polymer content of the article is greater than that which would be obtainable by a one-step cure effected when the curable - 1 - phenolic resin is all in the liquid state and the mixture is not held in article form under compacting or pressing pressure. As a result of the greater quantity of phenolic resin which may be incorporated in the product for curing by the one-step method of this invention the article or plate made possesses various desirable physical and chemical properties so that it can withstand thermal cycling from repeated spent fuel insertions and removals, can withstand radiation from spent nuclear fuel for long periods of time without losing desirable neutron absorbing and physical properties, is sufficiently chemically inert in water so as to retain neutron absorbing properties in the event of a leak which would allow the plates to be contacted by water, does not galvanically corrode and is sufficiently flexible so as to withstand operational basis earthquake and safe shutdown earthquake seismic events without objectionable loss of neutron absorbing capability and other desirable physical properties, when installed in a storage rack for spent nuclear fuel.

312638

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