Published: 1995-10-04

Articles

Fuel Development and Manufacturing Programme in India and Advanced Fuel Designs

M. Das, S.A. Bhardwaj, A.K. Saxena, K. Anantharaman, B.P. Varma

1-1

PDF

Korea's CANDU Fuel R and D Program

Ho Chun Suk, K.S. Sim, M.S. Yang, H.S. Park, B.K. Kim

1-8

PDF

Argentine Activities on Fuels for Nuclear Generation Stations

R.L. Olezza, J. Valesi

1-18

PDF

Romanian-Canadian Joint Program for Qualification of FCN as a CANDU Fuel Supplier

Constantin A. Galeriu, Gheorghe Andrei, Ana Bailescu, Axente Pascu, Mihail-Liviu Iliescu

1-24

PDF

Canadian Fuel Development Program and Recent Operational Experience

D.S. Cox, E. Kohn, J.H.K. Lau, G.J. Dicke, N.N. Macici, R.W. Sancton

1-32

PDF

Experience in the Manufacture and Performance of CANDU Fuel for KANUPP

Muhammad Salim, Iqbal Ahmed, Parvez Butt

1-42

PDF

A Feasible Approach to Implement a Commercial Scale CANDU Fuel Manufacturing Plant in Egypt

I. El-Shehawy, M. El-Sharaky, K. Yasso, I. Selim, N. Graham, D. Newington

1-56

PDF

The Post-Irradiation Examination of CANDU Type Fuel Irradiated in the Institute for Nuclear Research TRIGA Reactor

I.L. Tuturici, M. Parvan, R. Dobrin, M.D. Popov, R. Radulescu, V. Torna

2A-1

PDF

Performance of Bruce Natural UO2 Fuel Irradiated to Extended Burnups

Y. Zhou, M.R. Floyd, M.A. Ryz

2A-12

PDF

The Post-Irradiation Examination of Fuel in Support of Bruce A Nuclear Division Fueling With Flow Program

J. Montin, S. Sagat, R. Day, J. Novak, H. Bromfield

2A-22

PDF

Post-Defect Deterioration of CANDU Fuel: What Have We Learned?

A.M. Manzer, D. Dennier

2A-34

PDF

The Performance of T-Pad Bearing Pads, as a Remedy Against Pressure Tube Crevice Corrosion, on Bundles Irradiated at Bruce and Point Lepreau

Marvin A. Ryz

2A-48

PDF

Simulation Codes and the Impact of Validation/Uncertainty Requirements

H.E. Sills

2B-1

PDF

Fuel Thermal/Mechanical Behaviour Under Loss of Coolant Accident Conditions as Predicted by the FACTAR Code

C.J. Westbye, A.C. Brito, J.C. Mackinnon, H.E. Sills, V.J. Langman

2B-11

PDF

FACTAR Validation

P.B. Middleton, S.L. Wadsworth, R.C. Rock, H.E. Sills, V.J. Langman

2B-22

PDF

Qualitative Assessment of the Fission Product Release Capability of ELOCA.Mk5

M.E. Klein, L.N. Cariucci, V.I. Arimescu

2B-32

PDF

Prediction of the Fuel Failure Following a Large LOCA Using Modified Gap Heat Transfer Model

K.M. Lee, N.H. Lee, J.Y. Huh, S.K. Seo, J.H. Choi

2B-42

PDF

Quality Evaluations of the Fuel Bundle Welds and Brazed Joints by Acoustic Microscopy

M. Soare, C. lordache, R. Ciocan, V. Revenco, V. Dragne, I. Popescu, R. Moscalu

3A-1

PDF

Pyrolytic Carbon Coating of Zircaloy-4 Clads at Relatively Low Temperatures

I.D. Abdelrazek, S.W. Sharkawy, H.A. El-Sayed

3A-20

PDF

Advances in Appendage Joining Techniques for PHWR Fuel Cladding

P.B. Desai, T.K. Ray, V.G. Date, D.S. Purushotham

3A-41

PDF

Improved Techniques for Appendage Attachment to PHWR Fuel Elements

R.N. Jaya Raj, B. Laxminarayana, P.S.A. Narayanan, U.C. Gupta, B.P. Varma, K.K. Sinha

3A-55

PDF

The Active 'Ingredient' in CANLUB

P.K. Chan, K. Franklin, D.A. Guzonas, J. Halliday, K.J.W. Kaddatz

3A -65

PDF

The Production, Characterization and Neutronic Performance of Boron Nitride Coated Uranium Dioxide Fuel

Ibrahim Uslu, Uner Colak, Mehmet Tombakoglu, Gungor Gunduz

3A-75

PDF

CANDU Fuel Qualification Testing in Coolant Pressure Pulse Conditions

E. Kohn, G.I. Hadaller, P.F. Sandig

3A-85

PDF

The BTF-104 Experiment: An In-Reactor Test of Fuel Behaviour, and Fission-Product Release and Transport Under LOCAILOECC Conditions

L.W. Dickson, J.W. DeVaal, J.D. Irish, P.H. Elder, M.G. Jonckheere, A.R. Yamazaki

3B-1

PDF

Relocation of Molten Zircaloy in a CANDU Subchannel Geometry

P.M. Mathew, D.G. Evans

3B-11

PDF

CANDU Fuel Compression Tests at Elevated Temperatures

E. Kohn, J.K. Chan, V.J. Langman, G.I. Hadaller, R.A. Fortman

3B-21

PDF

Post-Irradiation Examination of Overheated Fuel Bundles

D.F. Sears, M.F. Primeau, D.A. Leach

3B-34

PDF

Fuel Sheath Integrity for Fuel Bundles at Decay Power Levels at 600 Degrees in Steam

P.J. Reid, R.A. Gibb

3B-41

PDF

Effect of CANFLEX Bundle Design on CANDU-6 Reactor Safety

D.J. Oh, C.H. Cho, Ho Chun Suk

3B-55

PDF

Plutonium Dispositioning in CANDU

P.G. Boczar, J.R. Hopkin, H. Feinroth, John C. Luxat

4A-1

PDF

Development of Inert-Matrix Carrier Fuels for Burning Plutonium or Actinide Waste

R.A. Verrall

4A-13

PDF

Status of Irradiation Testing and PIE of MOX (Pu-Containing) Fuel

F.C. Dimayuga, Y.N. Zhou, M.A. Ryz, M.R. Floyd

4A-25

PDF

Nuclear 'Garbage' as a Source of Energy

Osvaldo Cristallini, Domingo F. Quilici

4A-40

PDF

AECL's Progress in Developing the DUPIC Fuel Fabrication Process

J.D. Sullivan, D.S. Cox

4A-49

PDF

Comparison of Refueling Schemes for DUPIC Core

Hangbok Choi, Bo-Wook Rhee, Hyunsoo Park

4A-59

PDF

DUPIC Fuel Performance From Reactor Physics Viewpoint

Hangbok Choi, Bo-Wook Rhee, Hyunsoo Park

4A-69

PDF

Transient Fission Product Release During Reactor Shutdown and Startup

C.E.L. Hunt, Brent J. Lewis

4B-1

PDF

CANDU Type Fuel Behaviour Evaluation - A Probabilistic Approach

D.R. Moscalu, G. Horhoianu, LA. Popescu, G. Olteanu

4B-15

PDF

Modelling Stable-Fission-Gas Diffusion Inside the Grain

V.I. Arimescu

4B-28

PDF

Improvements, Verifications and Validations of the BOW Code

S.D. Yu, M. Tayal, P.N. Singh

4B-38

PDF

Thermally-Induced Bowing of CANDU Fuel Elements

Ho Chun Suk, K.S. Sim, J.H. Park, G.S. Park

46-52

PDF

Effect of Radial Power Profile on Endplate Integrity

M. Tayal, B. Wong, Y. Shudoh

4B-70

PDF

Bringing the CANFLEX Fuel Bundle to Market

A.D. Lane, D.F. Sears, I.E. Oldaker, A. Celli, G.R. Dimmick, Ho Chun Suk, K.S. Sim, C.H. Chung, C.B. Choi

5A-1

PDF

The Use of Graphite for the Reduction of Void Reactivity in CANDU Reactors

B.J. Min, B.G. Kim, K.S. Sim, Ho Chun Suk

5A-10

PDF

A 61 -Element Fuel Design (HAC) for Very High Burnups

M. Tayal, J.W. Love, D. Dennier, M. Gacesa, S. Sato, J. MacQuarrie, B.A.W. Smith, S.D. Yu, M. Tanaka, G. Wong, C. Manu

5A-20

PDF

Combined Effects of Graphite Discs and Central Holes on Pellet Temperatures in CANDU Fuel

K.A. Yasso, LA. El-Osery, M. Tayal

5A-31

PDF

MOX Fuel Fabrication at AECL

F.C. Dimayuga, A.T. Jeffs

5A-47

PDF

The 'Equivalent Plutonium' Concept and its Application to Synergetic Fuel Cycles Calculation

L.L. Perez Tumini, M.M. Sbaffoni, M.J. Abbate, P.C. Florido, LA. Mai, J.R. Maiorino

5A-56

PDF

Recent Findings on the Oxidation of UO, Fuel Under Nominally Dry Storage Conditions

P. Taylor, R.J. McEachern, S. Sunder, K.M. Wasywich, N.H. Miller, D.D. Wood

5A-66

PDF

Modelling of Phenomena Associated with High Burnup Fuel Behaviour During Overpower Transients

H.E. Sills, V.J. Langman, F.C. Iglesias

5B-1

PDF

AXLOAD: A Computer Code to Model Constrained Fuel String Axial Expansion

J.K. Chan, H.E. Sills, V.J. Langman

5B-13

PDF

Fission Product Release Mechanisms and Groupings

F.C. Iglesias, A.C. Brito, Y. Liu, M.A. Petrilli, R. Hu, M.J. Richards, R.A. Gibb, P.J. Reid, P. Elder, D.S. Cox, Brent J. Lewis

5B-23

PDF

SOURCE 2.0: A Computer Program to Calculate Fission Product Release from Multiple Fuel Elements for Accident Scenarios

A.C. Brito, F.C. Iglesias, Y. Liu, M.A. Petrilli, M.J. Richards, R.A. Gibb, P.J. Reid

5B-45

PDF

A Model for Fuel Oxidation and Diffusion-Based Fission Product Release Under Severe Nuclear Reactor Accident Conditions

P.L. Purdy, Brent J. Lewis, W.S. Andrews, D.S. Cox, F.C. Iglesias

5B-57

PDF

Modelling the Release Behaviour of Cesium During Severe Fuel Degradation

Brent J. Lewis, B. Andre, B. Morel, P. Dehaudt, D. Maro, M.F. Osborne, R.A. Lorenz

5B-74

PDF

A Model for Non-Volatile Fission Product Release During Reactor Accident Conditions

Brent J. Lewis, B. Andre, G. Ducros, D. Maro

5B-100

PDF

Hydrogen in CANDU Fuel Elements

R. Sejnoha, A.M. Manzer, B.A. Surette

6A-1

PDF

Determination of the Hydrogen Content of Fuel Elements

M. Soare, F. Petriu, V. Toma, A. Calinescu, V. Dragne, I. Popescu, V. Revenco, I. Pavel, G. Tatu, M. Butnaru

6A-16

PDF

AECL Hot-Cell Facilities and Post-Irradiation Examination Services

M.H. Schankula, E.L. Plaice, L.G. Woodworth

6A-34

PDF

Fuel Performance Evaluation Through Iodine Activity Monitoring

K. Anantharaman, Rajesh Chandra

6A-46

PDF

Sensitivity of Cesium Chemistry to the 0lU Ratio in UO2x

J. McFarlane, J.C. LeBlanc, D.G. Owen

6B-1

PDF

The Stoichiometry and the Oxygen Potential Change of Urania Fuels During Irradiation

Kwangheon Park, Myung-Seung Yang, Hyun-Soo Park

6B-11

PDF

Grain-Boundary Oxidation of Used CANDU Fuel Exposed to Dry Air at 150 Degrees for a Prolonged Period

W.H. Hocking, R. Behnke, A.M. Duclos, A.F. Gerwing, K.M. Wasywich

6B-20

PDF

Development of a Fuel Thermal Diffusivity Measurement Technique Using Pulsed Electron Beams

M.S. deJong, F.P. Adams, R.M. Hutcheon, P.G. Lucuta, R.A. Verrall

6B-39

PDF

Measurement of Krypton Grain-Boundary Inventories in CANDU Fuel

P.H. Elder, D.S. Cox, Z. Liu, R.S. Dickson, Z. Bilanovic

6B-48

PDF