1: Plenary - International Experience and Programs
An Overview of PHWR Fuel in India
C. Ganguly (NFC, India)
Status of the Demonstration Irradiation of the CANDU New Fuel Bundle CANFLEX-NU in Korea
H.C. Suk, J.S. Jun, J.Y. Jung, M.S. Cho, (KAERI, Korea), C.S. Lee, Y.B. Kim, Y.D. Kim (KEPRI, Korea), S.D. Yi, H.B. Seo (KHNP, Korea)
Advanced Fuel Development in AECL P.G. Boczar (AECL, Canada)
Status Report About CANDU Type Fuel Activities in Argentina
L. Alvarez, J.A. Casario (CNEA, Argentina), C. Moreno (NA-SA, Argentina)
Fuel Experience in QinShan CANDU M. Chen (TQNPC, China)
2A: Fuel Performance
O/M-Ratio Measurement Techniques
R.A. Verrall, J. Mouris, Z. He (AECL, Canada)
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 (AECL, Canada)
Microchemical Analysis of the Fuel-Sheath Interface in a Power-Ramped CANDU Fuel by Imaging-XPS
W.H. Hocking, K.G. Irving, T. Do (AECL, Canada)
Theoretical and Experimental Analysis of Irradiated Thorium Bundle from KAPS-2
S. Mukherjee, S. Ganesan, P.D. Krishnani, V. Jagannathan, R. Srivenkatesan, K. Anantharaman, K.C. Sahoo, S. Gangotra, P.V. Achuthan, K. Vijayan, A. Dakshinamoorthy, U. Jambunathan, A. Ramanujam, S.K. Aggarwal, R. Govindan, P.G. Jaison, P.S. Khodade, A.R. Parab, V.L. Sant, P.M. Shah, V. Venugopal, A. Ramaswami, S.P. Dange, S.S. Rattan, S.B. Manohar (BARC, India)
Fuel Performance, Design and Development in Indian Reactors
S.A. Bhardwaj, A.N. Kumar, P.N. Prasad, M. Ravi (NPCIL, India)
The PARALLEX Project: Irradiation Testing and PIE of the First Bundle
F.C. Dimayuga (AECL, Canada)
Migration Behaviour of Fission Products in CANDU Fuel
M. Saidy, R.A. Verrall, J.F. Mouris, I.J. Muir, W.H. Hocking (AECL, Canada)
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 (AECL, Canada)
Analysis of Accidental Sequence Tests and Interpretation of Fission Product Release: Interdependence of Cs, Mo and Ba Release
G. Nicaise (IRSN, France), V. Ozrin (IBRAE, Russia)
Knudsen Cell-Mass Spectroscopic Studies of Strontium Vapour Pressures Over Strontium Oxide/Uranium Dioxide Mixtures and Solid Solutions
S. Sunder, R.F. O’Connor (AECL, Canada)
2C: Fuel Bundle Thermalhydraulics
The Thermalhydraulic Characteristics of the CANDU-6 Reactor Channel with a CANFLEX-RU Fuel Bundle
J.S. Jun, H.C. Suk (KAERI, Korea)
A New Enthalpy Mixing Measurement Technique for Fuel Element Design
N. Silin (CNEA, Argentina), L.E. Juanicó (CNA, Argentina), D.F. Delmastro (CNEA, Argentina)
Recent Developments in ASSERT-PV Code for Subchannel Thermalhydraulics
Y.F. Rao, N. Hammouda (AECL, Canada)
RIH 35% Large Break LOCA without ECC for RUPIC Core
B.W. Rhee, C.J. Jeong, H.C. Suk (KAERI, Korea)
Off-Take Experiment at T-Junction Between Header and Feeder Pipes in CANDU Reactors
M. Kim, S.H. Hwang, S.O. Yu, H.J. Kim (KINS, Korea), G.S. Hwang, J.Y. Lee (Han Dong Global University, Korea)
3A: Manufacturing & Quality Assurance - I
Dry Recycling of Off-Grade Uranium Oxide Powder for Improving Sinterability
P.B. Ojha, Meena. R., C. Radhakrishna, S.M. Rao, C. Ganguly (NFC, India)
Current Process Developments in Production of Natural UO2 Green Pellets
D. Pramanik, G.V.S. Hemantha Rao, R.N. Jayaraj, C. Ganguly (NFC, India)
Application of Medium Frequency Weld Controller for Resistance Welding Process in PHWR Fuel Manufacturing
D.S. Setty, A. Rameshwar Rao, K.Y. Narayana, R.N. Jayaraj (NFC, India)
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 (NFC, India)
Development of Innovative Inspection Tools for Higher Reliability of PHWR Fuel (Abstract Only)
B. Kamalesh Kumar, B. Viswanathan, B. Laxminarayana, C. Ganguly (NFC, India)
3B: Fuel Safety - II
Failure Prediction of Irradiated Fuel Rod in Nuclear Reactors Under Reactivity-Initiated Accidents by Means of Statistical Approach
C. Nam (KAERI, Korea), J.A. Szpunar (McGill U, Canada)
LOCA Safety Margin Improvement of CANFLEX-NU Fuel
J.H. Choi, C.J. Bae, H.R. Hwang, J.T. Seo (KOPEC, South Korea), Y.B. Kim, C.S. Lee (KEPRI, Korea)
Transient Analysis of the Wolsong Units 2/3/4 Moderator for 35% RIH Break with Loss of ECC Injection Using CFX-4.4
C. Yoon, B.W. Rhee, B.J. Min (KAERI, Korea)
3C: Defected Fuel Modelling
Modelling the Activity of 129I in the Primary Coolant of a CANDU Reactor
B.J. Lewis (RMC, Canada), A. Husain (Kinectrics Inc., Canada)
Modelling the Activity of 99Tc in the Primary Heat Transport System of a CANDU Reactor
B.J. Lewis, W.T. Thompson (RMC, Canada), A. Husain (Kinectrics Inc., Canada)
Pourbaix Diagrams for Uranium, Molybdenum and Technetium
W.T. Thompson, B.J. Lewis, C. Morrison, M. Webb, F. Akbari (RMC, Canada)
Part I: Thermodynamics of Uranium Oxidation in Support of Kinetics Model for Operating Defective Fuel Elements
D.M. Thompson, B.J. Lewis, F. Akbari, W.T. Thompson (RMC, Canada)
Part II: Fuel Oxidation Kinetics Model for Operating Defective Fuel Elements
B.J. Lewis, W.T. Thompson, F. Akbari, C. Thurgood, J. Higgs (RMC, Canada)
4A: Manufacturing & Quality Assurance - II
Developments in CANDU MOX Fuel Fabrication
F.C. Dimayuga (AECL, Canada)
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 (RMC, Canada)
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 (RMC, Canada)
4B: Fuel Model Development - I
Modelling the Mechanical Behaviour of CANDU Fuel Cladding
R.A. Holt (QU, Canada)
New Approach to Derive Linear Power / Burnup History Input for CANDU Fuel Codes
T. Lac Tang, M. Richards, G. Parent (HQ, Canada)
Application of the Finite Volume Method to the Radial Conduction Model of the CATHENA Code
H.T. Kim, B.W. Rhee, B-J. Min (KAERI, Korea)
4C: Fuel and Fuel Channel Behaviour
A Role of Texture in Controlling Oxidation and Hydrogen Ingress in Zr-Nb Pressure Tubes
H. Li, J. Lin, J. Szpunar (McGill U, Canada)
Fuel Bundle Deformation Model L.C. Walters, A.F. Williams (AECL, Canada)
Crept Pressure Tube Model for Heat Transport System Aging Analysis
N. Wahba, E. Panyan, M. Bayoumi (NSS, Canada)
5A: Fuel Management
A CANDU-6 In-Core Fuel Management Study on CANFLEX-RU Fuel
C.K. Jo, H.C. Suk (KAERI, Korea)
Bruce B Core Conversion E. Braverman (BP, Canada)
Assessment of the Lattice Characteristics for DCA using WIMS-D5
B.J. Min, W.Y. Kim, Y.A. Kim, K.J. Ryu (KAERI, Korea), S.K. Oh (Ajou University, Korea)
Assessment of the WIMS-D5 Applicability to CANDU Reactors
W-Y. Kim, B-J. Min (KAERI, Korea)
Interim Storage of CANDU Spent Fuel and Safety Performance (Abstract Only)
J.K. Mohindra (OPG, Canada)
5B: Fuel Model Development - II
Fission Gas Release from Irradiated UO2 Fuel: Development of New Mechanistic Code MFPR and Applications
R. Dubourg (IRSN, France), M.S. Veshchunov (IBRAE, Russia), G. Nicaise (IRSN, France), V.E. Shestak (IBRAE, Russia)
Fission-Product Release Modelling in the ASTEC Integral Code: The Status of the ELSA Module
W. Plumecocq, M.P. Kissane, H. Manenc, P. Giordano (IRSN, France)
Oxygen and Hydrogen Diffusion in Zirconia
B. Szpunar (AECL, Canada), M.I. Baskes (LANL, USA), P.T. Jochym (Institute of Nuclear Physics, Poland)
A New Mechanism for Fission-Product Vaporization in SOURCE IST 2.0
L.W. Dickson, R.J. Lemire (AECL, Canada)
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 (IRSN, France)
5C: Advanced Fuel Cycles
Recent Progress in the Investigation of Inert Matrix Fuel
Y-W. Lee, S.C. Lee, H.S. Kim, S.H. Na, D.S. Sohn (KAERI, Korea)
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 (KAERI, Korea)
Process Optimization of DUPIC Fuel Pellet Fabrication
W.K. Kim, Jae W. Lee, G.I. Park, S.S. Kim, J.W. Lee, M.S. Yang (KAERI, Korea)
Bruce Power New Fuel Project - Design Implementation of Bruce CANFLEX-LVRF
M. Liska, D. McArthur (BP, Canada)
ACR Fuel Design P.G. Boczar, M. Tayal, A. Manzer (AECL, Canada)
