Published: 1989-06-07

Articles

Future Prospects for CANDU Advanced Fuel Cycles

J.B. Slater

1-1

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Use of Advanced Fuel Cycles in CANDU Power Plant Optimization

J.R. Hardman, A.C. Mao, A.R. Dastur

1-6

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The R and D Program in Support of Advanced Fuel Cycles for CANDU

E.O. Moeck, F.N. McDonnell, A.D. Lane, J. Griffiths

1-10

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The Role of the New CANFLEX Fuel Bundle in Advanced Fuel Cycles for CANDU Reactors

A.D. Lane, J. Griffiths, I.J. Hastings

1-16

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Reactor Physics Measurements in Support of Advanced Fuel Cycles in CANDU Reactors

R.T. Jones, J. Griffiths, A. Okazaki, A. Celli

1-23

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Equilibrium Fuel Management Simulations for 1.2% SEU in a CANDU 6

M.H. Younis, P.G. Boczar

1-33

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The Small Pressurized Light-Yater Reactor - A Yell-Optimized Marine-Propulsion Power Source

P. Gumley, F.N. McDonnell

2-1

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The AMPS-1000 - An Advanced Reactor Design for Marine Propulsion

A.F. Oliva

2-8

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The Nuclear Battery Program: Progress and Future Possibilities

K.S. Kozier, James V. Donnelly, W.G. Mathers

2-18

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Recent Initiatives at the IAEA and Within Canada to Develop Small Reactor Safety Criteria

P.M. French, P.C. Ernst, D.J. Axford, V.G. Snell

2-24

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SPORTS-M Prediction of the Transient Behaviour in a MAPLE Heat Transfer Test Facility

P.J. Mills, S.Y. Shim, J.E. Kowalski, K.O. Spitz

2-33

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Oxygen Addition to the Annulus Gas Systems of Pickering NGS A, Units 3 and 4

J.M. Kenchington, M. Ng, D.G. Meranda

3-1

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Some Aspects of Darlington Status Schedule and Complexity

H.L. Austman

3-6

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CANDID - Integrated Design System

T.H. Prescott, C.D. Sayles, E.D. Wessman

3-8

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New Approaches to Alarm Annunciation for CANDU Power Plants

R.A. Olmstead, J. Pauksens, W. Goddyn

3-15

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CANDU 3 - Single-Ended Refuelling

R.K. Nakagawa, R.A. Mansfield, W.H. Buchan

3-22

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Circumferential Cracking of the End Cap Welds - Case Analysis

R. Sejnoha, M. Tayal, P.N. Singh, B.A. Surette, C.K. Chow

3-29

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Irradiation-Induced Deformation in CANDU Fuel Channels

Roger Dutton, C.H. Woo

4-1

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Pickering NGS A: Assessment of Calandria Tube Integrity Following a Sudden Pressure Tube Failure

P.S. Kundurpi, A.P. Muzumdar, F.B.P. Tran

4-10

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Design Features of the Fuel Channel to be Used in the Retubing of Pickering 3 and 4

R. DeGregorio

4-19

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The Evolution of Pressure Tube Sampling Tools for Life Assessment

R. Joynes, C.A. Kittmer

4-24

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Remotely Operated Inspection Systems for the CANDU Fuel Channels

K.S. Mahil, G.N. Jarvis, D.W. Donnelly

4-29

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Comparison of Measured and Calculated Dose Rates and Activities During Pressure Tube Replacement in Pickering Units 1 and 2

K.M. Aydogdu, C.R. Boss, D.W. McKean

4-36

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Public Communication

Terry Young

5-2

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Government Information Needs

Brian Finlay

5-3

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Media Perspectives

Derek Nelson

5-4

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Public Attitudes Toward the Environment

Margaret Buhlman

5-5

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The Role of Public Consultation

Michael Scott

5-6

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TUF Verification Against Selected RD-14 Experiments

J. Pascoe, A. Tornasone, M. Williams, W.W. Yousef, W.S. Liu, J.C. Luxat

6-1

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Verification of CHAN-II (MOD6) Against Experiments

M. Bayoumi, F.B.P. Tran, K.E. Locke, A.P. Muzumdar

6-10

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FIDAS: A Three-Fluid Subchannel Code for Dryout Prediction in Rod Bundles

Takaaki Sakai, Helena E.C. Rummens, Satoru Sugawara

6-19

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Status of Physical and Numerical Modelling of CANDU Moderator Circulation

R.G. Huget, J.K. Szymanski, W.I. Midvidy

6-25

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Determination of Blowdown Heat Transfer Based on Experimental Investigation of RD14 Experiments. Analysis with the Code SLLOH

Jean-Claude Amrouni, J.C. Luxat

6-35

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CATHENA Simulation of Thermosiphoning in a Multiple-Channel Pressurized-Vater Test Facility

J.P. Mallory, P.J. Ingham

6-39

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Simulation of 'Standing Start' Behaviour by the CATHENA Thermalhydraulics Code

B.N. Hanna, J.P. Mallory

6-46

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Repair of End Shield of Pressurized Heavy Water Reactor

S.L. Kati, K.S.N. Murthy, A. Krishnan

7-1

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Remote Inspection and Repair of CANDU Reactor Vault Components

A.B. Powell

7-8

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Turbine Trip Due to Inadvertent Operation of ECI Injection Valves During Routine Testing at Pickering NGS-B

N.G. Blair-Johns

7-14

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Operating Experience With Mercury-Vetted Relays at Ontario Hydro's Nuclear Generating Stations

P.V. Castaldo, B.A. Rolfe

7-18

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Ten Year Performance of Bruce NGS 'A' On-Power Fuelling System

S. Jayabarathan

7-23

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Un Simulateur Pleine Echelle De Centrale Nucleaire: Un Outil Complexe Conduisant A Une Meilleure Formation

Claude Drouin, Denis Delorme

7-33

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Reactor Physics Recommissioning of Pickering NGS Units 1 and 2

J. Judah, N. Roy, M. Gold, G. Costa

7-43

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Coupled Neutronics - Thermohydraulics Simulations of Fast Transients in CANDU

B. Rouben, P. Soedijono, P.D. Thompson, A. Baudouin

8-1

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TRAWA-FEE Simulation of Reactivity Transients in PWRCores

D. Pevec, D. Grgic

8-9

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Evaluation of Neutron Resonance Data and Analysis Techniques for CANDU Type Fuel Bundles

Francisco Leszczynski

8-17

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The Sudbury Neutrino Observatory (SNO)

H.C. Evans

8-21

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On Factors Contributing to Quality of Nuclear Control Computer Software

S. Rannem, E. Hung

8-26

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Gestion Du Combustible Integree

Denis Aubin

8-34

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A Study of the Effectiveness for Response to Loss of Class IV Power of One Standby Class III Generator Operating in a Continuous or Test Cycle Mode

A.A. Chowdhury, A.T. McGregor, J.H. McIntosh, M.G. Frauley

9-1

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Emittance of Zircaloy-4 Sheath at High Temperatures in Argon and Stearn Atmospheres

P.M. Mathew, M.H. Schankula

9-12

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The Experimental Measurement of Circumferential Temperature Distributions Developed on Pressure Tubes Under Stratified Two-Phase Flow Conditions: Tests 1 to 5

P.S. Yuen, K.A. Haugen, D.G. Litke, R.G. Moyer, H.E. Rosinger

9-18

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Experiments to Determine the Thermal-Mechanical Response when Molten Zircaloy-4 Flows onto a Ballooned Pressure Tube

D.B. Sanderson, K.W. Demoline, K.E. Locke, A.P. Muzumdar

9-26

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Overpressures and Time Scales Associated with Hydrogen Combustion

G.W. Koroll, R.K. Kumar, C.K. Chan, K.N. Tennankore

9-31

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