Published: 1999-11-30

Articles

PHWR Advanced Fuel R&D for the 21st Century in Korea

Ho Chun Suk

1-10

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CANFLEX-NU Fuel Licensing Status and Issues in Korea

Geun-Sun Auh, Jun-Sang Park, Sweng-Woong Woo, Yung-Ho Ryu

11-17

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Critical Heat Flux and Pressure Drop for a CANFLEX Bundle String Inside an Axially Non-Uniform Flow Channel

L.K. Leung, D.C. Groeneveld, G.R. Dimmick, D.E. Bullock, W.W. Inch

18-29

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Static Strength Analysis of CANFLEX Fuel Bundle for CANDU 6 Reactor

Moon-Sung Cho, Ki-Seob Sim, Ho Chun Suk, Seok-Kyu Chang

30-39

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Validation of WIMS-AECL with ENDF/B-V Against Phase B Reactor Physics Tests at Wolsong Units 2 and 3

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

40-51

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Analysis of Xenon Spatial Oscillation in a CANDU 6 Reactor with DUPIC Fuel

Chang-Joon Jeong, Hangbok Choi

52-60

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Advanced CANDU Reactors Fuel Analysis Through Optimal Fuel Management at Approach to Refuelling Equilibrium

C.P. Tingle, H.W. Bonin

61-71

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New Fuel Bundle Packaging

J.W. Spencley, D.J. Semple

72-81

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High Polymer-Based Composites for Spent Nuclear Fuel Disposal Containers

H.W. Bonin, V.T. Bui

82-95

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Corrosion Resistance of (Th,U)O2 Fuel in Water

S. Sunder

96-105

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Assessment of the Core Flow Pattern and Pressure Tube Creep at Cernavoda Unit#l

Nastase Mazalu

106-116

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Post-Irradiation Examination of Two Gentilly-2 Bundles to Investigate the Effect of Pressure Tube Diametral Creep on Fuel Performance

Z. He, M.R. Floyd

117-126

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Measurement of the Composition of Noble-Metal Particles in High-Burnup CANDU Fuel by Wavelength Dispersive X-Ray Microanalysis

W.R. Hocking, F.J. Szostak

127-142

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Microacoustic Techniques to Assess the Local Characteristics of Irradiated Fuel Materials

B. Cros, Daniel Baron, V. Roque

143-152

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Source Term Analysis for a Nuclear Submarine Accident

Brent J. Lewis, J.J. Hugron

153-168

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Power Coefficient Calculation of a CANDU Reactor

H.B. Choi, J.W. Park

169-177

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Verification and Uncertainty Analysis of Fuel Codes Using Distributed Computing

D. Evens, R. Rock

178-186

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Verification of Fuel Performance Simulation Codes: Application of Distributed Computing

Y. Liu, C.J. Westbye

187-196

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Five Years of Successful CANDU-6 Fuel Manufacturing in Romania

A.C. Galeriu, A. Pascu, Gheorghe Andrei, Ana Bailescu

197-204

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Trends in Joining Technology Development for PHWR Fuel Assemblies in India

Pankaj B. Desai, P.G. Kulkarni

205-214

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A Study on the Core Characteristics for a CANDU 6 Reactor Fuelled with Recovered-Uranium CANFLEX Bundles

B.J. Min, C.J. Jeong, Ho Chun Suk

215-225

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The Use of Stainless Steel in CANDU Fuel with Recovered Uranium

B.J. Min, Ho Chun Suk

226-234

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A Reactor Physics Study of the Economic Penalty Associated with L VRF and Increased Pressure Tube Thickness

Daniel Rozon, Wei Shen

235-250

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Proliferation Hardening of Thorium Fusion Breeders with CANDO Spent Fuel

Sumer Sahin, Huseyin Yapici, Haci Mehmet Sahin, Veysel Ozceyhan

251-260

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Status of SOPHAEROS Fission-Product Transport Code Validation

S. Gingras, R.S. Dickson, L.W. Dickson

261-270

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Release of Fission Products from CANDU Fuel in Air, Steam and Argon Atmospheres at 1500 1900 C: The HCE3 Experiment

R.D. Barrand, R.S. Dickson, RS. Liu, D.D. Semeniuk

271-280

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Post-Irradiation Examination Results from the BTF-105A LOCA/LOECC Test

P.J. Valliant, J.D. Irish, S.T. Craig

281-290

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Preliminary Fission-Product and Post-Irradiation Examination Results from BTF-105B LOCA/LOECC Test

J.D. Irish, S.T. Craig, P.J. Valliant

291-300

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The Development of 3-D Tomography Method Based on Gamma-Scanning of Irradiated Fuel Rods

R. Dobrin, T. Craciunescu

301-305

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Looking Back at Fuel Thirty Nine to Forty Years Ago

R. Page

306-324

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CANDU Fuel: Design/1\fanufacturing Interaction

N.A. Graham

325-337

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Oxidation and Hydriding of Zircaloy Fuel Cladding- The Inside (and Outside) Story

B. Cox

338-347

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Load-Following Performance and Assessment of CANDO Fuel

M. Tayal, M.R. Floyd, D. Rattan, Z. Xu, A.M. Manzer, J.H. Lau, E. Kohn

348-364

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Fuel Performance at Cernavoda Unit #1

Dan Stanila

365-373

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Gentilly 2 NGS Recent Fuel Experience

Nicolas Macici

374-383

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Performance of Two CANDU-6 Fuel Bundles Containing Elements with Pellet Density and Clearance Variances

M.R. Floyd, Z. He, E. Kohn, J. Montin

384-392

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SOURCE 1ST 2.0: Development and Beta Testing

Duncan H. Barber, Fernando C. Iglesias, Yung Hoang, Lawrence W. Dickson, Raymond S. Dickson, Michael J. Richards, Robert A. Gibb

393-402

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An Overview of Defective Fuel Analysis in CANDU and Light Water Reactors

Brent J. Lewis

403-427

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Oxygen Potential in the Gap of Defective CANDU Fuel Rods During Severe Accident Conditions

Brent J. Lewis, C. Cole

428-443

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Technical Aspects and Benefits of the use of RU in CANDU Reactors

Ho Chun Suk, J.H. Park, B.J. Min, K.S. Sim, W.W. Inch, T.G. Rice

444-459

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Irradiation Plan of DUPIC Fuel at HANARO

Kikwang Bae, Kweonho Kang, Myung-Seung Yang, Hyunsoo Park

460-469

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A Comparative Study of Uranium and Thorium Based Fuel Pins using Code FAIR-TFC

B.K. Dutta

470-478

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Assessment of Fuel Manufacturing Safe Operating Envelope

R.A. Gibb, T.J. Chapman

479-491

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Analysis of Thermomechanical Behaviors of a Fuel Element using Three Dimensional Isoparametric Finite Elements

S.D. Yu, S. Xu

492-503

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Validations and Applications of the FEAST Code

Z. Xu, M. Tayal, J.H. Lau, D. Evinou, J.S. Jun

504-522

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