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Nuclear Technology Volume 44, 1979 - Issue 3
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Technical Paper

ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements

M. J. F. NotleyAtomic Energy of Canada Limited Chalk River Nuclear Laboratories, Fuel Materials Branch Chalk River, Ontario, KOJ IJO, Canada
Pages 445-450 | Published online: 10 May 2017

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Brent J. Lewis, Roderick D. MacDonald, Nicholas V. Ivanoff & Fernando C. Iglesias. (1993) Fuel Performance and Fission Product Release Studies for Defected Fuel Elements. Nuclear Technology 103:2, pages 220-245.
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Brent J. Lewis, Fernando C. Iglesias, David S. Cox & Elena Gheorghiu. (1990) A Model for Fission Gas Release and Fuel Oxidation Behavior for Defected UO2 Fuel Elements. Nuclear Technology 92:3, pages 353-362.
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Simcha Stroes-Gascoyne, Lawrence H. Johnson & Dennis M. Sellinger. (1987) The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel. Nuclear Technology 77:3, pages 320-330.
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Mukesh Tayal, Ed Mischkot, Harve E. Sills & A. W. L. Segel. (1987) ELOCA-A: A Code for Radial and Axial Behavior of CANDU Fuel Elements at High Temperatures. Nuclear Technology 76:2, pages 209-220.
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Roderick D. MacDonald & Ian J. Hastings. (1985) Graphite Disk UO2 Fuel Elements Designed for Extended Burnups at High Powers. Nuclear Technology 71:2, pages 430-444.
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L. H. Johnson, K. I. Burns, H. H. Joling & C. J. Moore. (1983) Leaching of 137Cs, 134Cs, and 129I from Irradiated UO2 Fuel. Nuclear Technology 63:3, pages 470-475.
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Henry H. Wong, Ertugrul Alp, W. R. Clendening, M. Tayal & Lloyd R. Jones. (1982) ELESTRES: A Finite Element Fuel Model for Normal Operating Conditions. Nuclear Technology 57:2, pages 203-212.
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H.J. Matzke. (1980) Gas release mechanisms in UO2—a critical review. Radiation Effects 53:3-4, pages 219-242.
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