Published: 1999-11-30

Articles

PHWR Fuel Experience in India

C. Ganguly

19-32

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The Experience in the Cernavoda Unit 1 Operation - A Stimulating Argument for Future Nuclear Power Development in Romania

Ioan Rotaru, I. Bucur, A.C. Galeriu, O. Budan

33-39

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Nuclear Fuel Cycle Activities in Argentina

P. Adelfang

40-51

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Experience in CANDU Fuel for KANUPP and Establishment of Supporting Facilities for Self Reliance

Muhammad Shabbir

52-65

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Canadian CANDU Fuel Development Program and Recent Operating Experience

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

66-77

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CANDU: Fuel for the Next Millennium

Peter G. Boczar

78-79

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Resolving the Controversy over Beneficial Effects of Ionizing Radiation

Jerry M. Cuttler

80-90

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CANFLEX Demonstration Irradiation at Point Lepreau: A Status Update

R.A. Gibb, R.W. Sancton, R.G. Steed, P.J. Reid, J. Bullerwell

91-102

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Full Scale Water CHF Testing of the CANFLEX Bundle

G.R. Dimmick, W.W. Inch, J.S. Jun, Ho Chun Suk, G.I. Hadaller, R.A. Fortman, R.C. Hayes

103-113

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An Update on the Design Verification of CANFLEX Fuel Bundle

P.K. Chan, B. Wong, M. Tayal, R. Sejnoha, D. Rattan, P.L. Purdy, J.H. Lau, G.G. Chassie, P. Alavi, Z. Xu

114-123

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Comparative Strength Assessment Between 43 and 37-element Fuel Bundles

G.G. Chassie, C. Manu, M. Tayal

124-136

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Fuel Re-ordering in the Bruce A Reactor Cores

E. Kohn, J. Novak, H. Bromfield, R. Day

137-153

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Hydrogen Gas in CANDU Fuel Elements

Roman Sejnoha

154-161

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Uprating Potential of a CANDU 6 Reactor with CANFLEX Fuel -A Safety Analysis Perspective

A. Grace, Z. Bilanovic

162-171

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Implementation of CANFLEX Bundle Manufacture - From Bench Scale to Production

A. Pant

172-183

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Performance of Indigenous Resistance Welding Equipment for PHWR Fuel Fabrication in NFC

G.V. Hemantha Rao, R.N. Jayaraj, M.S. Prakash, U.C. Gupta, C. Ganguly

184-191

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Approaching Six Sigma Quality in Nuclear Fuel Fabrication - An Indian Perspective

B. Laxminarayana, B. Kamalesh Kumar, N. Saratchandran, C. Ganguly

192-200

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New Fuel for Advanced Heavy Water Reactors

Carla Notari

201-205

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SEU Fuel In Atucha-1 NPP, A Valuable Experience for a CANDU-6 Core Enrichment

L. Alvarez, J. Casario, J. Fink, R. Perez, M. Higa

206-214

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Ref ming Practices in India to Produce Consistent Uranium Oxide Powder for PHWR Fuel Pellets

S.M. Rao, P.B. Ojha, C. Radhakrishna, U.C. Gupta, C. Ganguly

215-223

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Effect of Loading Pattern on High Temperature Sintering of UO2 Pellets

K.P. Chakraborty, R.N. Jayaraj, N.P. Katiyar, J.V. Kumar, V.K. Gopalakrishnan, S.M. Rao, C. Ganguly

224-234

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Novel Method for Recycle of Sintered UO2 Rejected Pellets

A.L. Reddy, E. Venkatesham, C. Radhakrishna, S.M. Rao, U.C. Gupta, C. Ganguly

235-240

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Fuel Element Sheath Strains at High Powers and Burnups: Rationalizing the Reference Bundle Overpower Envelope

E. Kohn, M.J. Notley

241-248

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Modelling of Intra-Granular Diffusion, Production and Removal in SOURCE 2.0

P.J. Reid, Brent J. Lewis, Fernando C. Iglesias, Duncan H. Barber

249-257

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CARA Fuel Bundle: A New Concept for HWR Present Situation

P.C. Florido, R.O. Cirimello, J.E. Bergallo, A.C. Marino, D.F. Delmastro, D.O. Brasnarof, J.H. Gonzalez, L.A. Juanico

258-267

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Investigations of Fuel-Bundle Motion and Fretting-Wear in the Chalk River Single-Channel Test Rig

V.P. Janzen, N.L. Fisher, B.A. Smith, C.E. Taylor, J.L. Gerardi, S.J. Palleck, J.S. Ryu, H.T. Chae, Y.G. Cho

268-277

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Probabilistic Assessment for Nuclear Fuel Rods Behavior

A.C. Marino

278-288

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