Published: 1997-09-25

Articles

Trends in Design & Manufacture of Nuclear Fuels in India

K.K. Sinha

18-28

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Canadian Fuel Development Program in 1997/98

J.H. Lau, E. Kohn, R. Sejnoha, D.S. Cox, N.N. Macici, R.G. Steed

29-39

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CANDU, Building the Future

F. Stern

40-45

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Some Considerations in the CANFLEX-NU Fuel Design

K.S. Sim, Ho Chun Suk, M. Tayal, P. Alavi, I.E. Oldaker, J.H. Lau

46-61

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The Use of Graphite in CANDU Fuel with Recovered Uranium

B.J. Min, B.G. Kim, K.S. Sim, Ho Chun Suk

62-71

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The Effect of Microstructure and Geometry on the Fatique Behaviour of Bundle Assembly Welds

B.A. Surette, M. Gabbani

72-82

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Verification of the Thermal Module in the ELESIM Code and the Associated Uncertainty Analysis

V.I. Arimescu, A.F. Williams, M.E. Klein, W.R. Richmond, M. Couture

83-99

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FACTAR 2.0 Code Validation

P.B. Middleton, R.C. Rock, S.L. Wadsworth

100-114

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The Manufacturing Role in Fuel Performance

A.P. Barr

115-123

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Fuel Performance in Indian PHWR

M. Ravi, P.N. Prasad, A.G. Chhatre, S.A. Bhardwaj

124-133

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Assessments of Sheath Strain and Fission Gas Release Data From 20 Years of Power Reactor Fuel Irradiations

P.L. Purdy, A.M. Manzer, R.H. Hu, R.A. Gibb, E. Kohn

134-147

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Fuel Condition in Canadian CANDU 6 Reactors

R.H. Hu, N.N. Macici, R.A. Gibb, P.L. Purdy, A.M. Manzer, E. Kohn

148-167

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Quality Assurance in CANDU-Type Fuel Manufacturing

Y.K. Afifi, E. El-Hakim

168-177

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Evolution of the ELOCA Code: Mk6 to the Present

V.I. Arimescu, M.E. Klein, J.R. Gauld, Z.W. Lian, L.N. Carlucci

178-187

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Understanding CANDU Fuel Bowing in Dryout: An Industry Approach

E. Kohn, R.H. Hu, G.I. Hadaller, R.A. Fortman

188-198

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The Parallex Project: CANDU MOX Fuel Testing with Weapons Derived Plutonium

D.S. Cox, F.C. Dimayuga, G.L. Copeland, K. Chidester, S.A. Antipov, V.A. Astafiev

199-209

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Development of Inert-Matrix Materials for Pu-Burning or Actinide-Waste Annihilation

R.A. Verrall, H.R. Andrews, P.S. Chan, I.M. George, P.J. Hayward, P.G. Lucuta, S. Sunder, M.D. Vlajic, V.D. Krstic

210-221

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EDF Fragment Relocation Model Based on the Displacement of Rigid Bodies

Christelle Callu, Daniel Baron, Jean-Marc Ruck

222-235

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Nuclear Fuel Performance in Embalse NPP, Design Optimizations and Manufacturing Improvements

L.A. Alvarez, J.A. Casario, J. Valesi, R. Olezza

236-242

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Bundle Uranium Content and Performance of CANDU Fuel

S.J. Palleck, R. Sejnoha, B.J. Wong

243-255

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Progress in Development of a Technique to Measure the Axial Thermal Diffusivity of Irradiated Reactor Fuel Pellets

R. Hutcheon, J. Mouris

256-268

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