1. D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, ERDA, USA (1974).
2. C. Vitanza, E. Kolstad and U. Graziani, Fission Gas Release from UO2 Pellet Fuel at High Burn-up, ANS Topical Meeting on LWR Fuel Performance, Portland, WA, USA (1979) p. 361.
3. A.H. Booth, A Method of Calculating Fission Gas Diffusion from UO2 Fuel and its Application to the X-2-f Loop Test, Rapport Atomic Energy of Canada Limited CRDC-721 (1957).
4. M.V. Speight, Nucl. Sci. Eng. 31 (1969) 180.
5. J.A. Turnbull, J. Nucl. Mater. 50 (1974) 62.