The Design of Fuel Elements for Gas-Cooled Nuclear Reactors

Fermi E. ‘Experimental production of a divergent chain reaction’, Am. J. Phys. 1952 20, 536.

Ritz H. L. ‘The polyzonal spiral fuel element’, 2nd U.N. Conference on the Peaceful Uses of Atomic Energy, Geneva 1958 7, 725.

Cunningham C. Slack M. R. ‘Heat transfer and pressure drop performance of spiral polyzonal heat transfer surfaces for gas-cooled reactors’, Brit. Nucl. En. Conf. J. 1961 6, 348.

Poulter D. R. , (Ed.) The design of gas-cooled graphite-moderated reactors 1963, 267 (Oxford University Press).

Walker V. ‘The improvement of fuel element heat transfer by surface roughening’, Nuclear Engng 1961 (April), 144.

Symposium: Calder works nuclear power plant. Brit. Nucl En. Conf. J. 1957 2, 41.

Stewart J. C. C. ‘Development and manufacture of Magnox fuel’, Proc. Instn mech. Engrs 1963–64 178, 227.

Brown G. Packman G. Greenough G. B. Fuel elements: Symposium on the advanced gas-cooled reactor. Brit. Nucl. En. Soc. J. 1963 2, 186.

Samuels G. ‘Fuel elements for gas-cooled reactors’. Symposium: Gas-cooled reactors, 1960, 138 (The Franklin Institute and The American Nuclear Society).

Glasstone S. Edlund M. C. The elements of nuclear reactor theory 1952, 213 (D. van Nostrand).

Diamond J. Hall W. B. ‘Heat removal from nuclear power reactors’, Brit. Nucl. En. Conf. J. 1956 1, 227.

Rapier A. C. Jones T. M. McIntosh J. E. ‘The thermal conductance of uranium dioxide/stainless steel interfaces’, Int. J. Heat Mass Transfer 1963 6, 397.

Guggenhiem E. A. Compressible flow of perfect gas with heat input distributed symmetrically about middle of channel. Document MT.137, National Research Council, Montreal Laboratory (1945). Reprinted by Atomic Energy of Canada Limited as AECL-1279 (1961).

Patterson J. Durrands K. J. ‘Dimensionless kinetic energy: A new parameter for gas flow in ducts with application to nuclear-power reactors’, J. mech. Engng Sci. 1961 3, 267.

Watts M. J. Waters J. D. ‘Evaluation of maximum can temperature for WAGR Mk 2 fuel charge’, U.K.A.E.A., TRG Memo. 1571 (R), 1963.

Gittus J. H. Sumner G. ‘General law for the fatigue of bodies having statistically distributed deformability’, Nature 1965 206 (3rd April), 81.

Symposium: Studies to determine the safety margins available on Magnox-type gas-cooled reactors in a depressurization accident’, Brit. Nuc. En. Soc. J. 1964 3, 173.

Brown G. Nichols R. W. ‘Review of materials for gas-cooled reactors’, Nuclear Metallurgy 1962 8 (A.I.M.E.).

Glasstone S. Edlund M. C. The elements of nuclear reactor theory 1952, 335–38 (D. van Nostrand).

Greenough G. B. Nairn J. S. Thorn J. D. ‘Progress towards the design of AGR fuel elements for power reactors’. 3rd U.N. Conference on the Peaceful Uses of Atomic Energy, Geneva 1964, P/149.

Colmer F. C. W. Littler D. J. Nucleonics 1951 8, 3.

Nuclear Engineering Apl. 1956 1.

Vaughan R. D. ‘Bradwell Nuclear Power Station’, Symposium on Berkeley and Bradwell nuclear power stations 1964 (Instn Mech. Engrs).