Patent Number: 041479386
Section: description

DETAILED DESCRIPTION OF A PREFERRED EMBODIMENT A spent nuclear fuel cask is generally designed to achieve at least the following goals to provide for the safe containment and transportation of spent nuclear fuel: (1) Prevention of escape of radioactive fission fragments, (2) Shielding of hazardous penetrating radiation, (3) Dissipation of thermal energy generated in radioactive decay, and (4) Assurance of the continued performance of the first three goals in spite of accidents such as collision, derailment, or fire. In FIG. 1 such a spent nuclear fuel cask 10 is seen employing the bimetallic band fire protector of this invention. Within the cask is a chamber 12 adapted for containing spent nuclear fuel. Also within the chamber there may be a heat transfer fluid for transmitting the heat generated by the fuel to the inner shell 14. This heat may be substantial, about 1 Kw per fuel pin with the surface temperature of the pin as high as 1000.degree. F. The heat transfer fluid may be a metal alloy such as lead-bismuth, sodium-potassium, or sodium; a gas such as helium or argon; a liquid such as water or organic compounds; or a heat transfer salt such as NaNO.sub.3 --NaNO.sub.2 --KNO.sub.2 ; or the like. The inner shell serves to contain the spent fuel and heat transfer fluid, provide a barrier to the spread of radioactive contamination, and provide structural strength to the cask. Surrounding the inner shell is a layer of nuclear shielding 16. The function of the nuclear shielding is to attenuate and absorb gamma and neutron radiation emitted by the spent nuclear fuel carried with the chamber 12. It may be advantageous to construct the nuclear shielding of multiple layers of different materials for attenuating the radiation and it may even be advantageous to place a portion of the shielding exterior to outer shell 18. Materials suitable for gamma shielding generally have high atomic weights and include lead, uranium, and depleted uranium. Materials suitable for neutron shielding generally have low atomic weights and include hydrogenous materials, water, metal hydrides, boron carbide, boron carbide-copper cermet, borated beachwood, hydrocarbons and the like. Suitable shielding materials also satisfactorily pass heat from the inner shell to the outer shell 18. The outer shell furnishes an additional barrier to the spread of radioactive contamination, provides additional structural strength, and supplies a convenient surface for the attachment of heat rejecting fins 20. The use of heat rejecting fins increases the surface area of the cask from which thermal energy can be rejected through the processes of radiation, conduction, or convection. In an accident environment, such as a fire, the heat rejecting fins may serve to conduct additional heat into the cask. This, of course, is undesirable insofar as it adversely affects the structural integrity of the cask or its contents. The method of the present invention utilizes a bimetallic band 22 to reduce the effective surface area of the fins during a fire and thus reducing the heat input to a cask during such as accidental occurrence. The bimetallic band, as 22a, is normally disposed between two adjacent fins and close to the outer surface of the outer shell where the band does not interfere with the rejection of heat by the fins. Should the cask be exposed to a high heat source such as a fire, the bimetallic band automatically expands outwardly, as 22b, interfering with radiation or convective heat transfer. The band may be restrained from over expanding by the use of a band retainer 24. As pictured, the band retainer may be a plurality of rods or pins positioned transverse to the fins, at the periphery of the fins. The bimetallic band may be fabricated from two strips of metal having dissimilar expansivities bent to a desired radius and affixed together along a side. It can be shown that a bimetallic strip of two dissimilar metals of equal thickness, t, will, if at an initial radius of curvature R.sub.1 expand to R.sub.2 in the temperature interval ##EQU1## The .alpha.'s and E's are the respective expansivities and elastic moduli of the component materials. The choice of materials is affected by the need for good response to a moderate rise in temperature, and the ability to withstand a high temperature. Although many such alloys will be obvious to those skilled in the art, two which may be used are type 304 stainless steel (18% Cr, 8% Ni, balance Fe) and Kovar (29% Ni, 17% Co, balance Fe). For 304SS-Kovar, .alpha..sub.a -.alpha..sub.b = 11 .times. 10.sup.-6 /.degree. C., and K = 1.34. For use in a cask with an exterior radius of 18.4 cm and a fin radius of 22.7 cm a 304SS-Kovar band with t of 0.076 cm will perform the desired expansion within a temperature change of 100.degree. C. The bimetallic band may be fabricated by forming the different metal strips to the desired radius of curvature and then affixing them together along one side with the higher expansivity metal being on the inside of the curve. It has been found that spot welding the strips at 1.8 cm intervals gives satisfactory results. The band may be fabricated such that the ends overlay in the normal position and so that full protection is afforded in the expanded position. Other materials which behave similarly to bimetallic strips may also be used. One example is the uranium-niobium alloy of U.S. Pat. No. 3,567,523 which displays thermally reversible, pseudo-plastic strain behavior. Referring now to FIG. 2, which is a fragmentary cross section of a nuclear fuel cask showing a portion of the outer shell 18 with three fins 20 attached to the outer surface, a bimetallic band 22a is shown in its normal position between two fins adjacent the surface of the outer shell. This bimetallic band is made up of two dissimilar metal strips 26 (Kovar) and 28 (304 stainless steel). The strip with the higher expansivity is located inwardly so as to cause an expansion or increase in the radius of curvature of the band upon application of heat. The band is also shown as 22b in its expanded position. It is restrained from overexpansion by band retainer 24 which may be an enlargement of the fin cross section near the periphery of the fin. As can be seen, much of the fin surface is exposed when the band is in its normal position; and much of the fin surface is hidden when the band is in its expanded position. EXAMPLE I A one-quarter scale simplified model of a spent nuclear fuel cask was constructed. The cask body was simulated by thirty-four circular steel plates 0.635 cm thick and 36.8 cm in diameter. The fin portion was simulated by seventeen circular copper plates 0.163 cm thick and 45.4 cm in diameter. These plates were stacked, alternating two steel plates with one copper plate, and bolted together to form a cylinder with radial fins. A 2.5 cm hole penetrated the center of each plate simulating a central cavity as well as affording access for chromel-alumel thermocouples. Bimetallic bands were fabricated from strips of 304 stainless steel and Kovar, each 0.076 cm thick, 1.22 cm wide, and 150 cm long. The strips were bent to the desired circular shape with the steel on the inside and then spot welded at 1.8 cm intervals. One bimetallic band was placed around the cask model and between each adjacent pair of fins. With thermocouples placed near the center and near the edge of the cask model, the model was subjected to a test fire. This test fire was simulated by a pair of butane torches, with 7 cm throats, directed at the side of the cask from a distance of 15 cm for one-half hour. Cask surface temperatures ran as high as 180.degree. C. for a band-protected cask, as opposed to as high as 295.degree. C. for an unprotected cask. Central temperatures were 115.degree. C. for a band-protected cask, as opposed to 145.degree. C. for an unprotected cask. EXAMPLE II Heat flow calculations were performed using the CINDA code (Chrysler Improved Numerical Differencing Analyzer for 3rd Generation Computers, Chrysler Corp. Space Div., New Orleans, LA). For the purposes of these calculations, the cask was assumed to be 3 meters long with an internal generation of 100 Kw of heat. With fin area equal to 15.times. cask surface area, a skin temperature of 82.degree. C. was calculated in an ambient temperature of 57.degree. C. A possible cross section of the cask was assumed to have the following radial dimensions: TABLE I ______________________________________ LAYER RADIAL DIMENSION ______________________________________ Central cavity 41 cm Inner steel shell 7 cm Uranium gamma shield 5 cm Lithium hydride neutron shield 5 cm Uranium gamma shield 6 cm Outer steel shell 6 cm Fin 16 cm ______________________________________ The assumed fire was at 802.degree. C. and lasted 0.5 hour; it was treated as a surface of unit emittance with all heat transferred by radiation. The results of the heat flow calculation are displayed in FIG. 3. Curve 1 shows the steady state temperatures with the cask surface fixed at 82.degree. C. and 100 Kw generated internally. Curve 2 shows the maximum internal temperatures due to exposure without fire protection. Curve 3 shows the maximum internal temperature with fire protection. The various features and advantages of the invention are thought to be clear from the foregoing description. However, various other features and advantages not specifically enumerated will undoubtedly occur to those versed in the art, as likewise will many variations and modifications of the preferred embodiment illustrated, all of which may be achieved without departing from the spirit and scope of the invention as defined by the following claims.