Published: 1985-06-04

Articles

Recent Use of the Finite Element Method In Deslgn/Analysis of CANDU Fuel

M. Tayal, O. Lim

1.1

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Fuel Development In CANOEV - Recent Achievements

I.E. Oldaker, R. Sejnoha

1.11

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Low Enriched Fuels tor NRU - Developments In Fabrication and Irradiation

J.D. Schaefer, J.C. Wood, D.F. Sears, L.C. Berthiaume, L.N. Herbert

1.15

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The Fluorination of UF4

R.C. Burk

1.2

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Modelling of Blast Wave Propagation Through the Darlington NGS Powerhouse In the Event of a Nearby Accidental Explosion

R.C. Wong, R. Monteforte, J. Skears, J.J. Gottlieb

2.1

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Modelling of Full-Scale Pressure Tube Rupture Experiments

A.P. Muzumdar, M. Kwee, J.K. Presley

2.9

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Measuring Moderator Temperatures In a CANDU Reactor

G. Austman, J. Szymanski, M. Garceau, W.I. Midvidy

2.19

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An Experimental Investigation Into the Development of Pressure Tube/Calandrla Tube Contact and Associated Heat Transfer under LOCA Conditions

G.E. Gillespie, R.G. Moyer, G.I. Hadaller, J.G. Hildebrandt

2.24

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A Probabilistic Risk Assessment of Loss of Fuel Rod Cooling In the NRU 135 MW Research Reactor

D.J. Winfield

2.31

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Proposed On-Line Automatic Vibration Monitoring and Diagnostic System in Nuclear Generating Stations

Sanjit K. Bose

3.1

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Determination of the Alpha Flux from Dental Prostheses

J.J.G. Durocher, W.S. Love, A. Lockshln, A.M. Sourkes

3.5

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A Computerized Gamma Camera for Prompt Location of Radiological Sources

T.J. Jamieson, J.S. Hewitt, D. Litchinsky

3.12

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A Waste Characterization Monitor tor Low-Level Radioactive Waste Management

E.C. Davey, G.W. Csullog, S. Kupca, K.B. Hlppola

3.18

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Identification of Iodine Species Released from Fuel Using a Commercial Volatile Radioiodine Species Sampler

D.R. McCracken

3.24

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The Economics of Coal Versus Nuclear Power Generation In Alberta when Social Costs are Included

B.W. Simms, B.W.K. Ng, B.H. McDonald, S.Y. Ahmad

4.1

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Canadian Churches Show Interest in Nuclear Energy - The IPPANI Hearings

A. Wyatt

4.11

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Socio-Economic Impact Analysis of New AECB Regulatfons

Ellen H. Rochman

4.21

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Public Opinion and Nuclear Issues

S.D. Guindon

4.26

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International Collaboration in Fusion

T.S. Brown

5.1

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The Muon-Catalyzed Nuclear Energy System

A.A. Harms

5.5

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Optimization of the Neutron Multiplier of Experimental Ayman Hybrid Blankets with ThO2

Sumer Sahin, Tawfik A. AI-Kusayer, Muhammed Abdul Raoof

5.1

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CFFTP - A Canadian Program on Fusion Technology

D.P. Dautovlch

5.19

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CANDU Reactor Experience: Fuel Performance

P.T. Truant, I.J. Hastings

6.1

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GENTILLY-2 Fuel Performance

R.H. Hu, L. Cloutier, N. Macici, D. Aubin

6.7

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Defective Fuel Detection in CANDU-600's

A.M. Manzer

6.12

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Fission Product Release to the Primary Coolant of a Reactor

B.J. Lewis

6.22

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Canadian High Burnup Fuel Experience

I.J. Hastings, T.J. Carter, G.M. MacGillivray, R.D. MacDonald, J. Judah

6.26

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In-Reactor Measurement of Operating Temperature in ThO2-UO2 Fuel: Effect of Pellet Microstructure

A.D. Smith, J.A. Walsworth, R.E. Donders, P.J. Fehrenbach

6.33

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Operating Experience with Nuclear Steam Generator Tubes

O.S. Tatone

7.1

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Vacuum Drying of the Pickering A Units 1 and 2 Primary Heat Transport Systems

P.J. Ellis, T. Lau, D.G. Meranda

7.7

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The Effect of the CAN-OECON Decontamination Process on the Surface Oxides on Pickering Units 1 and 2 Feeder Pipes

V.S. Chew, F.R. Greening

7.12

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Annulus Gas System Flow Tests: Experiment and Analysis

P.J. Ellis, D.G. Meranda, J.M. Kenchlngton, C.H. Cheh, V.P. Singh

7.16

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Crud Tolerant Fuel Channel Closure for Bruce GS A

P.T. Henry

7.21

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Automated Fuel Scheduling Experience at Gentilly-2

Guy Hotte

7.25

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Erosion Experiments of Stalnless Steel Under Water-Vapour Two-Phase Flow Conditions

M. Koike, T. Kltahara

8.1

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Neutron Irradiation Induced Effects In Zircaloy-2

R.A. Herring, M.H. Loretto

8.9

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Solute Interactions with Point Detects In HVEM Irradiated Zirconium Alloys

R.A. Herring, M.H. Loretto

8.18

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Measurement of Hydrogen and Deuterium In CANDU Pressure Tubes

Iain H. Crocker, John P. Mlslan

8.28

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Resistance/Diffusion Bonding of Titanium Nuclear Fuel Waste Disposal Containers

P.Y.Y. Maak, M. Cooper

8.31

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Recent Developments In Canadian Nuclear Power Plant Licensing Practices

P. Marchlldon

9.1

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Cost and Benefits of Nuclear Reactor Regulation In Canada

J.D. Harvie

9.10

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A Proposal tor Evolution of Safety and Licensing Criteria

D.A. Meneley

9.15

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Upfront Licensing - A New Approach

A. Natalizio

9.21

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Source Terms for Emergency Planning In Ontario

R.A. Brown, R.J. Fluke

9.27

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Fusion Reactor Configurations

S.B. Nickerson

10.1

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Tokamak de Varennes: The Design of Its Internal Poloidal Field Cells

P.B. Cumyn

10.8

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Electromagnetic Flelds and Forces in the Tokamak de Varennes

G. Clair, H. Van Andel, H.D. Pachar, G.W. Pachar

10.12

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Remote Maintenance of TFTR Poloidal Limiter

J. Stringer, H. Conrads, C. Holloway, T. Szlrtes

10.19

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Development of a Laser Based Detritiation System at Ontario Hydro

J.A. ONeill, K.B. Woodall, J.R. Robins, F.E. Bartoszek, H.D. Morrison

10.22

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Research Into Fuel Behaviour in Accidents

M.J. Notley

11.1

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Failure Criteria for Zircaloy-Sheathed Fuel Elements Under LOCA Conditions

J.A. Walsworth, H.E. Sills, S. Sagat

11.7

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In-Reactor LOCA Tests of Zircaloy Sheathed UO2 Fuel at Chalk River

P.J. Fehrenbach, J.A. Walsworth, R.C. Spencer, W.R. Chase, R.D. Delaney

11.14

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A LOCA Blowdown Test of CANDU Fuel Elements

E. Kohn, P.J. Fehrenbach, D.G. Hardy, J.H.K. Lau, G.H. Archinoff

11.2

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Comparisons Between ELOCA Code Calculations and CANDU Fuel Behaviour Under LOCA Conditions

J.A. Walsworth, P.J. Fehrenbach, R.C. Spencer

11.28

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Current Status of Fuel Channel Examinations Following the P2 G16 Failure in August 1983

G.J. Field

12.1

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Garter Spring Repositioning In Pickering and Bruce Reactors

M.A. Liska, B.R. Churchill, I.E. Lauchlan

12.9

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Pickering Large Scale Fuel Channel Replacement Program: Process, Organization and Status Overview

B.J. Murdoch, K.H. Talbot

12.13

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Large Scale Fuel Channel Replacement Program: Unit Preparations for P1/P2 LSFCRP

D.G. Austin

12.19

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Pickering NGS Decontaminations

C.S. Lacy, B. Montford

12.26

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Pickering Large Scale Fuel Channel Replacement: Site Facilities for Tool Proving and Training

R.J. Jessop, T.R. Moore

12.3

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Scaling Requirements for an Experimental Facility to Study the Thermosyphoning Behaviour of a CANDU Reactor

J.C. Amrouni, S. Nljhawan, A.M.M. Aly, R.L. Ferch, A.M. Omar

13.1

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Conceptual Design of an Experimental Facility to Study the Thermosyphoning Behaviour of CANDU Reactors

J.C. Amrouni, S. Nljhawan, A.M.M. Aly, A.M. Omar, Q.S. Truong

13.6

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A Study of Natural Circulation Cooling Using a Flow Visualization Rig

W.C. Bowman, R.L. Ferch, A.M. Omar

13.12

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Enhancement at Critical Heat Flux In CANDU 37-Element Bundles

I.P.L. Macdonald

13.16

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A Parametric Investigation ot Critical Heat Flux In a Vertical Forced Convective Channel

S.T. Yin, T.-J. Liu

13.24

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A Facility for Determining the Heat Transfer Characteristics at Present and Novel CANDU Fuels

C.F. Forrest, R.A. Fortman

13.33

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Critical Channel Power Evaluation Methodologies at Atomic Energy ot Canada Limited

A. Leung, E.E. Merlo, M. Gacesa, D.C. Groeneveld

13.36

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Prediction at Moderator Temperature Distribution Inside CANDU Calandrla and Its Effect on Criticality and Safety

Mohsen Abou Mandour, Hassan E.S. Fath, Makarem A.I. Hussein

14.1

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Progress In the Development of WIMS at Chalk River

James V. Donnelly

14.1

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Longer Life Cores for SLOWPOKE -2 Reactors

J.D. Irish, J.W. Hilborn

14.15

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A Calculational Model tor the NRU Reactor

S.R. Douglas

14.19

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Physics Characteristics of a CANDU-600 with Repositioned Adjuster Rods Fuel led with MOX or Natural Uranium

P.G. Boczar

14.24

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Checkerboard Fuelling - The Key to Advanced Fuel Cycles in Existing CANDU Reactors

P.S.W. Chan, A.R. Dastur

14.27

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A New Generatron of Intense Radiation Sources

J. McKeown

15.1

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Modelling Transient Fission Product Release from UO2 Fuel

J.H.K. Lau, F. Rance

16.1

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Behaviour of Short-Lived Fission Products Under Fuel Accident Conditions: Chalk River Studies

I.J. Hastings, C.E.L. Hunt, J.J. Lipsett, R.D. Delaney, P.J. Fehrenbach, L.L. Larson, R.C. Spencer

16.7

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Oxidation of UO₂ and Fission Product Release at 400-1000 °C in Air

D.R. McCracken

16.15

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Fuel Temperature Escalatfon in Severe Accidents

O. Akalin, C. Blahnfk, B. Phan, F. Rance

16.26

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The lnteraction and Dissolutlon of Solid UO2 by Molten Zircaloy-4 Cladding in an Inert Atmosphere or Steam

H.E. Rosinger, R.K. Rondeau, K. Demollne, K.J. Ross

16.33

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CANDU Fuel Deformation During Degraded Cooling (Experimental Results)

E. Kohn, G.I. Hadaller, R.M. Sawaia, G.H. Archinoff, S.L. Wadsworth

16.39

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Pickering Large Scale Fuel Channel Replacement: Separatron of Pressure Tube Rolled Joints by Rapid Induction Heating

D.F. Pritchard, M.B. Cenanovlc

17.1

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Radiation Shielding Equipment tor In-Vault Use During the Retubing of Pickering Units 1 & 2

W.J. Knowles, J.A.M. Vissers, W.J. Bethune

17.6

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Pickering NGS-A Large Scale Fuel Channel Replacement Program: Retubing Tool Carrier (RTC)

E.J. Bennett

17.12

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Management of Irradiated Components from the Pickering Units 1/2 Retube

I.E. Wall, Z.S. Beallor

17.19

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Pickering NGS Units 1 and 2 LSFCRP: Fuel Channel Reinstallation Process

A. Mehmi

17.26

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Nuclear Plant Care and Maintenance During the Retube Outage

K.H. Talbot, J.T. Wieckowski

17.3

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Calculation of Two-Phase Critical Flow from a Long Pipe

C.R. Slongo, C.S. Kim, J.Y. Stambolich

18.1

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Computation of Two Phase Flow Distribution and CHF In Horizontal Bundles Using the ASSERT Subchannel Code

M.B. Carver, A. Tahir, R.A. Judd, J.C. Klteley

18.8

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Fuel Cooling under Channel Steam Venting Conditions

E. Hussein, John C. Luxat

18.17

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SMARTT - A Computer Code to Predict Fuel and Pressure Tube Temperature Gradients Under Asymmetric Coolant Conditions

K.E. Locke, Glenn H. Archinoff, A.P. Muzumdar

18.23

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Models tor Analysing the Radial Heat Transfer In CANDU Reactor Fuel Channels During High-Temperature Loss -of-Coolant Accidents

James Hildebrandt

18.3

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Effect of Axially Non-Uniform Pressure Tube Diametral Creep on Mass and Enthalpy Imbalance for a 37-Element Bundle

A.M.M. Aly, Q.S. Truong, T. Malaty

18.37

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Status of the Canadian Nuclear Fuel Waste Management Program

R.B. Lyon

19.1

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Social and Political Aspects of Nuclear Fuel Waste Management

E.R. Frech

19.11

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Safety Assessment of Uranium Mill Tailings: The National Uranium Tailings Program

W.C. Harrison, Bruce E. Halbert, Douglas Chambers

19.15

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Leaching Studies of Low-Level Radioactive Waste Forms

Ramesh Dayal, Harpal Arora, Lawrence Milian, James Clinton

19.23

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Leaching Performance of Simulated Decontamination Wastes Solidified with Water Extendible Polyester Resin

M. Adam Habayeb

19.28

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An Atmospheric Dispersion Modelling System for Nuclear Emergency Response

G.L. Ogram, S.C. Wright, S. Daggupaty, P.K. Misra

19.33

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Restart of the U.S. Space Nuclear Reactor Power Program

Vincent C. Truscello

20.1

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The CANDU 300: An Overview with Emphasis on Constructability

R.S. Hart

20.6

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The SECURE Reactor Concepts

Cristen Pind

20.12

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The MAPLE-X Concept Dedicated to the Production of Radio-Isotopes

W. Heeds

20.18

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The Slowpoke-2 Reactor with LEU Oxide Fuel

B.M. Townes, J.W. Hilborn

20.25

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SAGA-N: A Nuclear-Powered Submarine Vehicle For Commercial Operation

J.S. Hewitt, P. Wilkins, G.A. Kastner

20.32

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