Published: 2003-11-24

Articles

An Overview of PHWR Fuel in India

C. Ganguly

1-19

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

Ho Chun Suk, J.S. Jun, Jong Yeob Jung, M.S. Cho, C.S. Lee, Y.B. Kim, Y.D. Kim, S.D. Yi, H.S. Seo

20-35

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Advanced Fuel Development in AECL

Peter G. Boczar

36-48

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Status Report About CANDU Type Fuel Activities in Argentina

L. Alvarez, J.A. Casario, C. Moreno

49-57

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Fuel Experience in QinShan CANDU

Mingjun Chen

58-64

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O/M-Ratio Measurement Techniques

R.A. Verrall, J. Mouris, Z. He

65-73

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Characterization of Fuel Pellet Oxidation in Defected Fuel Elements Using O/M Ratio Measurements and Optical Microscopy

Z. He, R.A. Verrall, J.F. Mouris, C.A. Buchanan

74

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Microchemical Analysis of the Fuel-Sheath Interface in a Power-Ramped CANDU Fuel by Imaging-XPS

W.H. Hocking, K.G. Irving, Than Do

75-87

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Theoretical and Experimental Analysis of Irradiated Thorium bundle from KAPS-2

Sadhana Mukherjee, R. Govindan, P.G. Jaison, P.S. Kohdade, A.R. Parab, V.L. Sant, P.M Shah, V. Venugopal, A. Ramaswami, S.P. Dange, S.S. Rattan, S.K. Aggarwal, A. Ramanujam, U. Jambunathan, S. Ganesan, P.D. Krishnani, V. Jagannathan, R. Srivenkatesan, K. Anantharaman, K.C. Sahoo, S. Gangotra, P.V. Achuthan, K. Vijayan, A. Dakshinamoorthy, S.B. Manohar

88-97

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Fuel Performance, Design and Development in Indian Reactors

S.A. Bhardwaj, A.N. Kumar, P.N. Prasad, M. Ravi

98-107

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Gamma-ray Tomography of Irradiated CANDU Reactor Fuel

Barbara D. Sawicka

108-125

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The PARALLEX Project: Irradiation Testing and PIE of the First Bundle

F.C. Dimayuga

126-136

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Migration Behaviour of Fission Products in CANDU Fuel

M. Saidy, R.A. Verrall, J.F. Mouris, I.J. Muir, W.H. Hocking

137-148

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The Effect of Heating Rate on Fission-Product Release: The HRE1 Experiment

R.S. Dickson, Z. Liu, G.W. Wood, R.F. O'Connor, L.W. Dickson

149-159

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Analysis of Accidental Sequence Tests and Interpretation of Fission Product Release: Interdependence of Cs, Mo and Ba Release

Gregory Nicase, V. Ozrin

160-172

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Knudsen Cell-Mass Spectroscopic Studies of Strontium Vapour Pressures Over Strontium Oxide/Uranium Dioxide Mixtures and Solid Solutions

S. Sunder, R.F. O'Connor

173-182

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The Thermalhydraulic Characteristics of the CANDU-6 Reactor Channel with a CANFLEX-RU Fuel Bundle

J.S. Jun, Ho Chun Suk

183-201

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A New Enthalpy Mixing Measurement Technique for Fuel Element Design

Nicolas Silin, Luis E. Juanico, Dario F. Delmastro

202-210

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Mathematical Modeling of CANDU-PHWR

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

211-219

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Recent Developments in ASSERT-PV Code for Subchannel Thermalhydraulics

Y.F. Rao, N. Hammouda

220-229

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RIH 35% Large Break LOCA without ECC for RUPIC Core

Bo-Wook Rhee, C.J. Jeong, Ho Chun Suk

230-244

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Off-Take Experiment at T-Junction Between Header and Feeder Pipes in CANDU Reactors

Manwoong Kim, Su Hyun Hwang, Seon Oh Yu, Hho Jung Kim, Gi Suk Hwang, Jae Young Lee

245-253

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Dry Recycling of Off-Grade Uranium Oxide Powder for Improving Sinterability

P.B. Ojha, R. Meena, C. Radhakirshna, S.M. Rao, C. Ganguly

254-261

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Current Process Developments in Production of Natural UO2 Green Pellets

D. Pramanik, G.V.S. Rao, R.N. Jayaraj, C. Ganguly

262-271

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Application of Medium Frequency Weld Controller for Resistance Welding Process in PHWR Fuel Manfacturing

D.S. Setty, A. Rao, K.Y. Narayana, R.N. Jayaraj

272-281

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Manufacturing of 37-Element Fuel Bundles for PHWR 540 - New Approach

U.K. Arora, V.S. Sastry, P.K. Banerjee, G.V.S.H. Rao, R.J. Jayaraj

282-289

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Development of Innovative Inspection Tools for Higher Reliability of PHWR Fuel

B. Kumar, B. Viswanathan, B. Laxminarayana, C. Ganguly

290

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Failure Prediction of Irradiated Fuel Rod in Nuclear Reactors Under Reactivity-Initiated Accidents by Means of Statistical Approach

C. Nam, J.A. Szpunar

291-302

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LOCA Safety Margin Improvement of CANFLEX-NU Fuel

J.-H. Choi, C.J. Bae, H.R. Hwang, J.T. Seo, Y.B. Kim, C.S. Lee

303-311

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Transient Analysis of the Wolsong Units 2/3/4 Moderator for 35% RIH Break with Loss of ECC Injection Using CFX-4.4

Churl Yoon, Bo-Wook Rhee, Byung-Joo Min

312-322

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Modelling the Activity of the 129I in the Primary Coolant of a CANDU Reactor

Brent J. Lewis, A. Husain

323-333

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Modelling the Activity of 99Tc in the Primary Heat Transport System of a CANDU Reactor

Brent J. Lewis, W.T. Thompson, A. Husain

334-343

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Pourbaix Diagrams for Uranium, Molybdenum and Technetium

W.T. Thompson, Brent J. Lewis, C. Morrison, M. Webb, F. Akbari

344-355

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Part I: Thermodynamics of Uranium Oxidation in Support of Kinetics Model for Operating Defective Fuel Elements

D.M. Thompson, Brent J. Lewis, F. Akbari, W.T. Thompson

356-366

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Part II: Fuel Oxidation Kinetics Model for Operating Defective Fuel Elements

Brent J. Lewis, W.T. Thompson, F. Akbari, C. Thurgood, J. Higgs

367-377

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Developments in CANDU MOX Fuel Fabrication

F.C. Dimayuga

378-394

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Cold War Legacy: Surface Investigation of Unsaturated Prairie Soil Radiologically Contaminated in 1951

D.J. Sims, W.S. Andrews, G. Hounsell, K.A.M. Creber

395-403

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Cold War Legacy: Sub-surface Investigation of Unsaturated Prairie Soil Radiologically Contaminated in 1951

D.J. Sims, W.S. Andrews, Z. Wang, K.A.M. Creber

404-413

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Modelling the Mechanical Behaviour of CANDU Fuel Cladding

R.A. Holt

414-422

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New Approach to Derive Linear Power/Burnup History Input for CANDU Fuel Codes

T. Lac Tang, Michael Richards, Gilbert Parent

423-431

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Application of the Finite Volume Method to the Radial Conduction Model of the CATHENA Code

Hyoung Tae Kim, Bo-Wook Rhee, Byung-Joo Min

432-441

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A Role of Texture in Controlling Oxidation and Hydrogen Ingress in Zr-Nb Pressure Tubes

Hyalong Li, Jianlong Lin, Jerzy Szpunar

442-451

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Fuel Bundle Deformation Model

L.C. Walters, A.F. Williams

452-463

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Crept Pressure Tube Model for Heat Transport System Aging Analysis

Nabil Wahba, Edward Panyan, Mohamed Bayoumi

464-480

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A CANDU-6 In-Core Fuel Management Study on CANFLEX-RU Fuel

Chang Keun Jo, Ho Chun Suk

481-490

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Bruce "B" Core Conversion

Evgeny Braverman

491-500

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Assessment of the Lattice Characteristics for DCA using WIMS-D5

B.J. Min, W-Y. Kim, Y.A. Kim, K.J. Ryu, S.K. Oh

501-511

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Assessment of the WIMS-D5 Applicability to CANDU Reactors

Won-Young Kim, Byung-Joo Min

512-521

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Interim Storage of CANDU Spent Fuel and Safety Performance

Jag K. Mohindra

522

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Fission Gas Release from Irradiated UO2 Fuel: Development of New Mechanistic Code MFPR and Applications

Roland Dubourg, M.S. Veshchunov, G. Nicaise, V.E. Shestak

523-539

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Fission-Product Release Modelling in the ASTEC Integral Code: The Status of the ELSA Module

W. Plumecocq, M.P. Kissane, H. Manenc, P. Giordano

540-550

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Oxygen and Hydrogen Diffusion in Zirconia

B. Szpunar, M.I. Baskes, P.T. Jochym

551-561

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A New Mechanism for Fission-Product Vaporization in SOURCE IST 2.0

L.W. Dickson, R.J. Lemire

562-572

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Fission-Product Transport Modelling in the ASTEC Integral Code: The Status of the SOPHAEROS Module

N. Alpy, M.P. Kissane, I. Drosik, C. Fiche, M.H. Kaye

573-583

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Recent Progress in the Investigation of Inert Matrix Fuel

Young-Woo Lee, Sang Chul Lee, Han Soo Kim, Sang Ho Na, Dong Seong Sohn

584-593

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Improvement of DUPIC Pellet Fabrication Processes by Using Simulated Fuel

Jae W. Lee, J.W. Lee, W.K. Kim, G.I. Park, K.C. Song, M.S. Yang

594-604

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Process Optimization of DUPIC Fuel Pellet Fabrication

W.K. Kim, Jae Lee, G.I. Park, S.S. Kim, J.W. Lee, M.S. Yang

605-612

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Bruce Power New Fuel Project - Design Implementation of Bruce CANFLEX-LVRF

M. Liska, D. McArthur

613-622

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ACR Fuel Design

Peter G. Boczar, Mukesh Tayal, Al Manzer

623-628

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