A theory is proposed, relating irradiation swelling in metal fuel with burn-up, and used to predict fuel-element behaviour under various fast reactor conditions; good agreement is obtained with known behaviour sufficient to substantiate the general conclusion that fission-product gas accumulation is chiefly responsible. It would appear impossible to eliminate such swelling, only to reduce and accommodate it. Based on this principle, a fast reactor fuel-element is suggested using unalloyed uranium, with substantial voidspace in a strong can. This should be capable of 4 per cent average burn-up at 700°C centre temperature under practical fast reactor conditions, which should be sufficient to ensure economic power. With oxide fuel it would appear that, in order to satisfy the essential safety and economic requirements in a fast reactor, it is also necessary to incorporate considerable voidage in the fuel and to employ a strong can; safety requirements could also lead to double-canning. Such an arrangement could possibly attain 10 per cent burn-up, which is comparable to 4 per cent with metal fuel. A cermet of UO 2-PuO 2 dispersed in uranium metal, again in a strong can and with void space in the fuel, appears a suitable way of combining the good properties of both oxide and uranium fuel, and could result in an excellent high burn-up fuel for fast reactors, though its behaviour is more uncertain to predict.
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