2016: International Conference on CANDU Fuel | Proceedings of the Canadian Nuclear Society

Canadian Nuclear Laboratories Fuel Science & Technology

Mark Floyd, R. Ham-Su, T. Nitheanandan

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Fuel Recycling in CANDU - the Global Benefits

Jerry Hopwood

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CANDU Fuel Safety Criteria: a CNSC Perspective

Michel Couture

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Development of Advanced CANDU Fuel Bundles in Korea

J.H. Park, Y.M. Song

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Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents

Lembit Sihver, N. Yasuda

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Resistance Welding – Preferred Technique for Appendage Welding in PHWR Fuel Manufacturing

N.V. Satish Kumar, Tanumay Bhattacharya, S.K. Pathak, D.S. Setty, G. Kalyanakrsihnan, N. Saibaba

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Microscopic Examination of Unirradiated CANDU Fuel From Darlington Nuclear GS

Keith Ellison, J. Judah, R. VanLochem, Constantin Banica

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Post-Irradiation Examination of Bruce Nuclear Generating Station Elements at Chalk River Laboratories (CNL)

J. Armstrong, K. Chakraborty, R. Lewis, R. Scrannage

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Application of the WANO Fuel Reliability Indicator for PHWRS

Brent J. Lewis, Constantin Banica, Paul K. Chan

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How to Minimise Fuel Failures (and Other Surprises) Following Either Reactor New Build or Refurbishment

John G. Roberts

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CANDU Advanced Fuel Technology Development in China – Perspective, Roadmap, and Status

S. Fan, Z. Meng, T. Wu, G. Qiao

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Establishing and Sustaining a Technical Program to Achieve Zero Fuel Failures

J. Deshon, K. Pigler, R. Burnham, S. Goodchild

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Analysis of Pressure Tube Measured Data for CANDU Reactors

Jong Yeob Jung, W.J. Hartmann

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Spark Plasma Sintering of Uranium Nitride Fuels

Janne Wallenius, Kyle Johnson, Mark Zimny

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Romanian Experimental Research on Fuel Performance

Gheorghe Olteanu, Dragos Victor Ionescu, Roxana Roman, Silviu Florea

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Progress in the Development of Thoria Fuel Science & Technology

Mark Floyd, A. Quastel, S.J. Livingstone, K. Leeder, R.S. Dixon, G. Cota-Sanchez, E. Bulumela, A. Bergeron, John S. Bell, R. Beier, M. Saoudi

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Thorium Based Fuel Performance Modelling and the Development of the Multi-pellet Material Fuel and Sheath Modelling Tool (MPM-FAST)

John S. Bell, Paul K. Chan

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First Principles Study of Thermal Conductivity of Nuclear Fuel Materials

Barbara Szpunar, Linu Malakkal, Ericmoore Jossou, Dotun Oladimeji, Jayangani Ranasinghe, Ingunn Rossland, Jerzy A. Szpunar

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Neutronic Analysis of an In-Core co-60 Production in CANDU6 Reactor

J. Lyu, M.A. Motalab, Yonghee Kim

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Optimal Neutron Absorber Location to Mitigate End Flux Peaking in CANDU Fuel Bundles

Dylan Pierce, Paul K. Chan, Wei Shen

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The Modification of Fuelling Frequency and the Use of Burnable Absorbers in CANDU Reactors

Christy L. Bruce, Paul K. Chan, H.W. Bonin, Jae Song, Stephane Paquette

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Erbia-loaded CANDU Fuel for Minimization of the Coolant Void Reactivity

W. Kim, M.A. Motalab, Yonghee Kim

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Modelling of Fuel Bundle Deformation Under High-Temperature Transient Conditions

Zhen Xu, Shouze George Xu, Hazen Fan, Masoud Shams

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Campus: A Fully Coupled Multiphysics Modeling Approach for Light Water Fuel Performance

R. Liu, Wen Zhou, Andrew Prudil, Paul K. Chan

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3d Modelling Capability for CANDU Fuel Performance

Girma G. Chassie, Masoud Shams

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Applicability of Evaluation Models in the PWR Fuel Performance Code, Roper for CANDU-6 Fuel

Joon Suk Ji, Young Ho Heo, Kang Moon Lee, Eun Ki Lee

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The Other Metallic Phase in Spent Nuclear Fuel ~ A Complete Thermodynamic Evaluation of the U-Pd-Rh-Ru System ~

Lian Wang, Matthew H. Kaye

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A Method for Predicting the Evolution of Crack Growth in Complex Structures – A Potential Application in Simulating Stress Corrosion Cracking

Diane Wowk, L. Alousis, Paul K. Chan

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The Unique Contribution of CANDU Technology in the Battle Against Climate Change

Fabricia Pineiro, J. Hannah, C. Cottrell, S. Kuran

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Performance of High Burnup MOX Fuel

Mark Floyd, S. Corbett, A. Barry

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Preliminary Modelling of U-Pu MOX Fuel in CANDU Geometries Using BISON

Andrew Prudil, M. Welland, W. Richmond, S. Yatabe

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MOX Fuel Performance Modelling of CANDU Fuel

Girma G. Chassie, Alan Jiang, Akash Gill, Masoud Shams

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Qualification and Implementation of 37M Fuel Into CANDU Reactors: A Regulatory Perspective

Kelly T. Conlon

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Repeatability of Full Scale 37M Critical Heat Flux Experiments Performed at Stern Laboratories Inc.

R.A. Fortman, R.C. Hayes, Gordon I. Hadaller

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Mechanical Behaviour of High Burnup PHWR Clads

Priti Kotak Shah, J.S. Dubey, Ashwini Kumar, R.S. Shriwastaw, B.N. Rath, Prerna Mishra, V.D. Alur, Sunil Kumar

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Waste Management Policies for CANDU Spent Fuel in Nigeria

Nnodi Akelachi Chinweikpe

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Predicting the Behaviour of Defected CANDU Fuel Oxidation in Air With the USA DOE Semi-Empirical Model for the Oxidation of Defected LWR Fuel

Jose Freire-Canosa

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CANDU Fuel Defect Bundle Transfer Platform

Robert Kozeluh

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Modelling of CANDU Pressure Tube Diameter Expansion

Jong Yeob Jung, W.J. Hartmann

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Analyzing Fuel Bundle Deformation Using the Finite Element Method

Rabia Soni, Paul K. Chan, A.F. Williams, Diane Wowk

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Finite Element Simulations of a Fuel Element Simulator Sagging Experiment

A.F. Williams, S. Yatabe, A. Belov

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Automated Inspection Systems for PHWR Fuel at Nuclear Fuel Complex

C. Phani Babu, K.S. Subramaniam, B. Kamalesh Kumar, M.K. Yadav, Y.S. Rao, N. Saibaba

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Vision Based Smart Systems for Reliable Nuclear Fuel Pin Manufacturing

N.V. Satish Kumar, S.K. Pathak, D.S. Setty, G. Kalyanakrsihnan, N. Saibaba

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Characterization of Zr - 2.5%Nb - 0.5%Cu Garter Spring With Rectangular Wire for 700 MWE PHWRS

R.K. Chaube, Y. Subba Rao, C. PhaniBabu, A. Maruthi Ram, K.S. Lakshmi, S.K. Reddy, S. Singh, Chaitanya Reddy, S. Acharya, N. Saibaba

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Multiphysical Unsteady Simulations of Ballooning Pt and Ct Contact in the Benchmark Model of IAEA/ISCP

S.M. Chang, H.T. Kim

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Determination of the Threshold Conditions for Delayed Hydride Cracking in Zircaloy-4 CANDU Fuel Cladding – AECL’s Contribution to IAEA Coordinated Research Programme

Z. He, C.E. Coleman, D. McDonald

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Failed Fuel Location by Xe-133 Trend in CANDU6

Wei Hu

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Fuel Defect Detection and Location Methods at Pickering Nuclear Generating Station

K. Vizmuller

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Fuel Behaviour After a LOCA Followed by a Site Design Earthquake at 24 Hours After the Initial Event

E.R. Istrate

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High - Temperature Bundle Deformation Experiments Under Conditions Applicable to LBLOCA With ECI Available

Farzin Abbasian, Gordon I. Hadaller, R.A. Fortman, R.C. Hayes

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The Effect of the Molten Corium Temperature on the Predicted Melt Penetration Distance

V.Q. Tang, J. Spencer, J. Tang

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Assessment of Fuel and Fuel Channel Behaviour at High Temperature During a Postulated LOCA/LOECC Event

Hazen H. Fan, Augustina Ranger, L. Flatt, Fred Huang, T. Laurie, H. Zhao, W. Zhu, Zhen Xu

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A Cross-Platform Multi-physics Reactor Transient Simulations Through a Salome-Backbone Joint Platform

Yu Liu, Tao Xu, Marat Seydaliev, Boone Tensuda

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Optimization of Process Parameters of UO₂ Powder Production for Higher Pellet Recovery

D.S. Setty, R.A.L.V. Kumar, J Venkataswamy, S.K. Tiwari, D.M. Reddy, M. Misra, G. Kalyanakrsihnan, N. Saibaba

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An Integral Approach for Handling and Minimizing Effluent Generation During Production of Sinterable Grade UO₂ Powder for PHWR Fuels

D.S. Setty, R.A.L.V. Kumar, J Venkataswamy, S.K. Tiwari, D.M. Reddy, M. Misra, G. Kalyanakrsihnan, N. Saibaba

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Effect of Particle Size Distribution of UO₂ Powder on Sinterability

Sameer Nautiyal, Baidurjya Nath, R.S. Ambhorkar, P.V. Rama Rama, D.S. Setty, G. Kalyanakrsihnan, N. Saibaba

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