Published: 1997-09-25

Articles

CANDU Advanced Fuel R and D Programs for 1997-2006 in Korea

Ho Chun Suk, M.S. Yang, K.S. Sim, K.J. Yoo

1-10

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Romanian Nuclear Fuel Program: Past, Present and Future

Octavian Budan, Ioan Rotaru, Constantin A. Galeriu

11-22

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Nuclear Fuel Supply View in Argentina

R.O. Cirimello

23-31

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Development of the CANDU Reactor

A.S. Bain

32-42

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Early Days of CANDU Fuel

R.D. Page

43-51

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Design Verification of the CANFLEX Fuel Bundle - Quality Assurance Requirements for Mechanical Flow Testing

P. Alavi, I.E. Oldaker, C.H. Chung, Ho Chun Suk

52-59

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Performance of the CANFLEX Fuel Bundle under Mechanical Flow Testing

C.H. Chung, S.K. Chang, Ho Chun Suk, I.E. Oldaker, P. Alavi

60-69

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Thermalhydraulic Performance of CANFLEX Fuel

G.R. Dimmick, D.E. Bullock, A. Hameed, J.H. Park

70-81

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Explicit Core-Follow Simulations for a CANDU 6 Reactor Fuelled with Recovered-Uranium CANFLEX Bundles

M.J. DAntonio, James V. Donnelly

82-90

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R and D Activities on CANDU-Type Fuel in Indonesia

A. Suripto, M. Badruzzarnan, A. Latief

91-99

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Recent Activities of the Nuclear Fuel Technology

S. Can, M.T. Aybers, B. Kopuz, Y. Bayram, L. Gureli, F. Can, A. Yayli, L. Colak, K. Cimcim, I. Yurtseven, S. Acarkan, N. Bekdemir, I. Yildiz, S. Albayrak

100-107

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Impact of Reactor Water Chemistry on Cladding Performance

B. Cox

108-117

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Simulation of the Transport of Volatile Fission Products within the Fuel-to-Sheath Gap of Defective CANDU Reactor Fuel Rods

H.W. Bonin, Brent J. Lewis

118-132

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Modelling the Release of Volatile Fission Product Cesium from CANDU Fuel Under Severe Accident Conditions Using Artificial Neural Networks

W.S. Andrews, Brent J. Lewis, D.S. Cox

133-144

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Vaporization of Low-Volatile Fission Products Under Severe CANDU Reactor Accident Conditions

Brent J. Lewis, B.J. Corse, W.T. Thompson, M.H. Kaye, F.C. Iglesias, P. Elder, R. Dickson, Z. Liu

145-159

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Quality Evaluation of the Nuclear Fuel Manufactured in Romania before 1990

Octavian Budan, Constantin A. Galeriu, Axente Pascu, Ana Bailescu, Gheorghe Andrei

160-169

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Nuclear Fuel Fabrication - Developing Indigenous Capability

U.C. Gupta, R.N. Jayaraj, R. Meena, V.S. Sastry, C. Radhakrishna, S.M. Rao, K.K. Sinha

170-180

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Quality Surveillance Experience of PHWR Fuel

P.G. Kulkarni, A.K. Bandyopadhyay, B.K. Shah

181-187

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Ceramic UO2 Powder Production at CAMECO Corporation

A.K. Kwong, S.M. Kuchurean

188-197

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Six-Sigma Quality for Fuel Manufacturing

Michael D. Gabbani, Tom Onderwater

198-210

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Technical Specifications and Performance of CANDU Fuel

Roman Sejnoha

211-218

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Fuel Defect Root Cause Investigation at Wolsong-1

Hyun-Taek Park, Hwee-Soo Jun, A.M. Manzer, S.J. Palleck, J.W. Love

219-228

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The Effect of Element Bow on Dryout Power and PDO Heat Transfer in CANDU Fuel Bundles

S.C. Sutradhar, J.R. Schenk

229-238

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Preliminary Results of the BTF-1OSA Test: An In-Reactor Instrument Development and Fuel Behaviour Test

J.W. DeVaal, J.D. Irish, L.W. Dickson, S.T. Craig, M.G. Jonckheere, L.R. Bourque

239-251

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Large-Break LOCA Assessment for the Highly Advanced Core Design

F.J. Doria, V.I. Nath, K.F. Hau, R.F. Dam, J. Vecchiarelli

252-266

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The Utilization of Russian Weapons Plutonium in Canadian CANDU Reactors: A Feasibility Study

E.G. Kudriavtsev, E.I. Tyurin, L. Petrova, A.I. Tokarenko, R.D. Gadsby, L.R. Jones, J.I. Saroudis, E.G. Bazeley

267-278

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Quantitative WDS Analysis to Determine Pu Homogeneity in CANDU MOX Fuel

Z. He, D. Rose, F. Szostak, F.C. Dimayuga, M.H. Schankula

279-288

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Fabrication of Simulated Mid-Burnup CANDU Fuel in the RFFL

F.C. Dimayuga

289-299

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AECL's Progress in DUPIC Fuel Development

J.D. Sullivan, M.A. Ryz, J.W. Lee

300-310

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Computer Simulation of the Behaviour and Performance of a CANDU Fuel Rod

Armando Carlos Marino

311-320

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Source 2.0 Model Development: UO, Thermal Properties

P.J. Reid, M.J. Richards, F.C. Iglesias, A.C. Brito

321-341

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Quantification of Factors Affecting Thermally-Induced Bow in a CANDU Fuel Element Simulator

P.M. Mathew, S. Baset, J. Veeder, E. Kohn

342-350

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Modelling Transient Two-Dimensional Nonlinear Temperatures in Nuclear Fuel Using the Feat Code

M. Tayal, S.D. Yu, C. Manu, R. Aboud, D. Bowslaugh, L. Flatt

351-362

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Creep Bowing in CANDU Fuel: Modelling and Application

S.D. Yu, M. Tayal, Z. Xu

363-375

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Investigation of the CANLUBJSheath Interface in CANDU Fuel at Extended Burnup by XPS and SEMIWDX

W.H. Hocking, R. Behnke, A.M. Duclos, A.F. Genving, P.K. Chan

376-392

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Spent Fuel Dry Storage Experience at Gentiliy 2 NGS

Nicolas N. Macici

393-402

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Waste Management Issues and their Potential Impact on Technical Specifications of CANDU Fuel Materials

J.C. Tait, L.H. Johnson

403-414

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Effects of Adsorbates on Zircaloy Oxidation in Air

Yoonchul Cho, Yun-Goo Kim, Kwangheon Park

415-424

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Quantitative Procedure to Determine the Rate of U3O8 Formation on UO

P. Taylor, R.J. McEachern

425-434

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