Published: 2001-09-27

Articles

Fabrication, Quality Assurance & Performance of PHWR Fuel in India

C. Ganguly

3-12

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Current Status and Future Prospect of CANDU Fuel Research & Development in Korea

Ho Chun Suk

13-26

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Dryout Power of a Canflex Bundle String With Raised Bearing Pads

L.K.H. Leung, J.S. Jun, G.R. Dimmick, D.E. Bullock, W.W.R. Inch, Ho Chun Suk

27-40

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A Refuelling Strategy of CANFLEX-RU Fuel in CANDU Reactors

S.Y. Kim, C.J. Jeong, B.J. Min, Ho Chun Suk

41-50

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Mechanical Fretting Endurance Test of CANFLEX Fuel Bundle

Seok-Kyu Chang, Ho Chun Suk

51-62

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Status of the Demonstration Irradiation Program of the New Fuel Bundle CANFLEX-NU in Korea

Ho Chun Suk, M.S. Cho, J.S. Jun, S.H. Lee, Y.B. Kim

63-76

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Development of CANDU-PHWR Neutronics Code SCAN

I.S. Hong, C.H. Kim, B.J. Min, Ho Chun Suk

77-86

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Application of Direct Search Technique to Optimal Refueling Channel Selection for CANDU Reactors

C.J. Jeong, H. Choi, Ho Chun Suk, N.Z. Cho

87-94

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New Selection Criteria for Channel Refueling of a CANDU-6 Reactor: Introduction to "Floppy Rules"

Denis Brissette

95-112

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Mathematical Modeling of CANDU-PHWR

Fatma Gaber, R.A. Aly, O. El-Shal

113-122

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Validation of MCNP-4B Code Against Measurement Data of Wolsong Nuclear Power Plant 2

Gyuhong Roh, Hangbok Choi, Chang-Joon Jeong

123-132

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Comparative Study of Turbo and Spray Drying Techniques in the Production of Nuclear Grade Uranium Dioxide

C. Radhakrishna, M. Ravindran, J.P.N. Srivastav, P.B. Ojha, M. Anuradha, T.K. Sinha, A.P. Kulkarni

133-142

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Optimising Welding and Assembling Processing for Manufacturing PHWR Fuel Element Bundle

D.S. Setty, U.K. Arora, A.R. Rao, G.V.S.H. Rao, R.N. Jayaraj

143-150

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New Development in PHWR Fuel Assembly Fabrication

P.K. Banerjee, V.S. Sastry, G.N. Ganesha, A Singh, C. Ganguly

151-162

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Microchemical Studies of Irradiated Fuel by Imaging-XPS

W.H. Hocking, K.G. Irving

163-176

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Mechanical Characterization of Irradiated Fuel Materials with Local Utrasonic Methods

Didier Laux, G. Despaux, Daniel Baron, J. Spino

177-190

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Two-phase Pressure-drops for CANDU Fuel Bundles in Uncrept and Crept Channels

S.C. Sutradhar

191-204

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Optimization of Powder/Pellet Fabrication for DUPIC Fuel

J.-H. Kim, K.H. Kang, B.G. Kim, Jae Lee, J.W. Lee, M.S. Yang

205-216

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The Precise X-Ray Inspection for DUPIC Fuel Elements Weldded by Nd:YAG Laser

W.K. Kim, S.S. Kim, J.W. Lee, M.S. Yang

217-226

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DUPIC Fuel Fabrication in Shielded Facilities in Korea

J.W. Lee, W.K. Kim, S.S. Kim, M.S. Yang, H.S. Park

227-236

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Analysis of the Thermal Behavior of DUPIC Fuel

Hee Seoung Park, Kee Chan Song, Myung Seung Yang

237-248

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Romanian Program for SEU/RU Fuel Manfacturing at Nuclear Site Pitesi

Dumitru Ohai, Gheorghe Andrei

249-260

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Exporting Technology for CANDU Fuel Manufacturing to the People's Republic of China-A Stimulating Experience for the Romanian Nuclear Fuel Plant

V. Bailescu, G. Burcea, V. Turcanu, C. Stanciu

261-268

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A Dark Side Of The Fuel Cycle: Some Military Uses Of Depleted Uranium And Potential Consequences

W.S. Andrews, Brent J. Lewis, L.G.I. Bennett, E. Ough

269-286

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Gentilly 2 NGS Recent fuel Experience

Nicolas Macici

287-298

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FISM: A New Optimized Fuel Modeling Computer Code

M.Y. Khalil, W.A. Omar, K.A. Yasso

299-310

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Fuel Oxidation and Thermal Conductivity Model for Operating Defective Fuel Rods

Brent J. Lewis, B. Szpunar, Fernando C. Iglesias

311-328

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Multi-Component Gas Transport in CANDU Fuel Rods During Severe Accidents

B. Szpunar, Brent J. Lewis, V.I. Arimescu, R.S. Dickson, L.W. Dickson, M.I. Baskes

329-354

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Knudsen Cell-Mass Spectroscopic Studies on the Relationship between Molybdenum Oxidation and Iodine Volatility in CANDU Fueld

S. Sunder, R.F. O'Connor

355-364

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