Published: 1987-06-17

Articles

Virginia Power's Nuclear Unit Life Extension Program

P.R. Beament, D.R. Hostetler

3-7

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EPRI Overview and Generic Aspects of PWR and BWR Studies

M.E. Lapides, C. Bergeron, T.L. Bailey

8-10

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CANDU-300 Features for Plant Life Extension

R.S. Hart

11-17

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Assessment of Plant Life Extension (FLEX) and Long-Term Reliability Assurance (LTRA) Issues for Ontario Hydro's Nuclear Generating Stations

J.A. Chadha, R.J. Strickert

18-26

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Modifications to the Shutdown Systems to Augment Reactor 27 Trip Coverage to Cater to a Single Pump Trip in a CANDU 600 Reactor

P.D. Thompson, A. Baudouin, L.J. Watt, G. Delorme

27-30

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Consequences of Pressure/Calandria Tube Failure in a 31 CANDU Reactor Core During Full-Power Operation

A.P. Muzumdar, G.M. Frescura

31-39

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Gentilly-2 Safety Analysis for Higher Containment Leakage

R.H. Hu, M.S. Quraishi

40-48

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UO2 Oxidation in Air or Steam-Release or Retention of the 49 Fission Products Ru, Ba, Ce, Eu, Sb and Nb

C.E.L. Hunt, F.C. Iglesias, D.S. Cox, N.A. Keller, R.D. Barrand, J.R. Mitchell, R.F. O'Connor

49-57

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Fission Product Release from UO2 in Air During 58 Temperature Ramps

D.S. Cox, F.C. Iglesias, C.E.L. Hunt, N.A. Keller, R.D. Barrand, R.F. O'Connor, J.R. Mitchell

58-64

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Experience on Environmental Qualification of Safety 65 Related Components for Darlington Nuclear Generating Station

A.S. Yu, B.M. Kukreti

65-72

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An Investigation into the Relationship Between Local and 73 Global Power Excursions in CANDU

M.H. Younis, S.D. Grant, B. Rouben

73-76

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Expected Reactivity Effect of Fuel Channel Coolant 77 Boiling in the Darlington NGS A Reactor Core

M. Gold, E. Carruthers

77-80

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Fuel Management Simulations for a Part-Core Loading of 81 Slightly Enriched Uranium in a CANDU-600

P.G. Boczar, H.G. Blundell, M.T. Van Dyk

81-90

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Shut-off Rod Performance Study for the Point Lepreau 91 Reactor

R.C. Robinson

91-95

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Simulating the Power Rundown Transient from Poison 96 Injection System for a CANDU Reactor

M.Z. Farooqui, N. Roy, S.G. Lie, H.G. Austman, A.L. Wight

96-102

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In-Situ Calibration of Flux Mapping Detectors in an 103 Operating CANDO Reactor

T.C. Leung, D.S. Hall, N.H. Drewell, A.M. Lopez

103-110

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Development of the LOCA Analysis Code System of the ATR

Y. Hayamizu, H. Mochizuki, H. Midorikawa

111-115

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Thermal Power Uprating of CANDU Reactor

N. Spinks, D. Groeneveld

116-119

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Experimental Investigation of Core-Jet Confinement in a MAPLE-type Flow Test Facility

P.T. Wan, S.Y. Shim, V.S. Krishnan

120-124

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Regime-4 Code for Prediction of Flow Regime Transition in a Horizontal Pipe, Annulus and Bundle Flow Under Gas-Liquid Two-Phase Flow

S.I. Osamusali, Jen-Shih Chang

125-134

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Subchannel Analysis of CANDU 37-Element Fuel Bundles

A.M.M. Aly, K. Amrud

135-141

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Assessment of the Code CHAN3 for the Prediction of the Thermal Response of a CANDU Fuel Channel During a Loss-of-Coolant Accident with Impaired Emergency Cooling Against Experimental Results

M. Rizk, G.A. Maclean, K.W. Demaline, D.G. Litke, R.J. Norek

142-150

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The Darlington Probabilistic Safety Evaluation -A CANDU Risk Assessment

F.K. King, V.M. Raina, K.S. Dinnie

151-178

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The Use of Probabilistic Safety Assessment in the Operation of Point Lepreau Generating Station

S. Alikhan, D.J. Edgar

179-186

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The SLAR System -An Overview

D.J. Benton

187

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An Automated Inspection and Analysis System for SLAR

M. DeVerno, H. Licht, W. Mayo

188-193

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Ultrasonic Fast-Scan Blister Detection System

M.D.C. Moles, D.W. Donnelly

194-198

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The AC Device for Repositioning of Garter Springs in CANDU Reactors

M. Cenanovic, H. Maureira

199-202

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Optimization of SLAR Tool Bearings

H. Wong

203-208

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Development of a Telescopic Ram and its Control System

D. Grossman, J.L. Roberts

209-214

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An Adaptable Distributed Computer Control System

R.J. Cairns, R.J. Hohendorf, J. Greenhalgh

215-222

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CATHENA Simulation of a Critical Inlet Header Break Test with Emergency Coolant Injection in RD-14

D.J. Richards, F.W. Barclay, P.J. Ingham

223-235

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Experimental Investigation of the Refill Behaviour in a CANDO-type Header/Feeder System

J.E. Kowalski, V.S. Krishnan

236-240

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The Experimental Determination of Circumferential Temperature Distributions Developed in Pressure Tubes During Slow Coolant Boildown

C.B. So, G.E. Gillespie, R.G. Moyer, D.G. Litke

241-248

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Verification of a Thermal-Hydraulic Model of Channel Cooling Degradation During a IDCA/LOECI Event

J.C. Luxat, F.D. Rance, C.B. So, R.G. Moyer, D. Litke

249-254

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Progress on SMARTT Simulation of Pressure Tube Circumferential Temperature Distribution Experiments ­- Test 1 to 4

K.E. Locke, John C. Luxat, A.P. Muzumdar, C.B. So, R.G. Moyer, D. Litke

255-264

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Point Lepreau Generating Station: Four Years of Reliable Production

A.C.F. Hadfield

265-271

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Fuel Defect Detection by Radioiodine Monitoring

A.M. Manzer, N. Macici

272-278

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The Role of Enriched Fuel in CANDU Power Uprating

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

279-286

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Waterlancing for CANDU Steam Generators

W.G. Schneider

287-291

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On-Site Contingency Planning at Pt. Lepreau NGS

D.F. Weeks

292-295

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Off-Site Nuclear Contingencies in a Multi-Hazard Planning Group

James O. Stith, Gary E. Stairs

296-304

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Safety Research and Development -Post Chernobyl

R.A. Brown

305-306

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Fuel Behaviour During Simulated Reactivity Initiated Accidents in the NSRR Experiments and its Application

T. Fujishiro, T. Inabe, M. Sobajima

307-316

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The Relevance of Chernobyl to LWR and PHWR Source Term Experimental Programs

F.C. Iglesias, C.E.L. Hunt, D.S. Cox, M.F. Osborne, R.A. Lorenz, J.L. Collins

317-326

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Aerosol Behavior Research Implications of Chernobyl

T.S. Kress

327-329

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Hydrogen in Water-Cooled Nuclear Reactors

M.W. Jankowski, J.C. Cummings, D.F. Torgerson

330-340

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Atmospheric Dispersions Modelling in Nuclear Safety

P.J. Cooper, W. Nixon, B.Y. Underwood

341-356

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Confidence in Fuel Channel Components

B.A. Cheadle

357-360

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Pressure Tube Procurement for CANDU Reactors

E.G. Price, S. Venkatapathi

361-367

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Corrosion Performance of ZR-2.5 wt% NB Pressure Tubes in Ontario Hydro's Operating CANDU Nuclear Reactors

B.D. Warr, P.C. Lichtenberger

368-374

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Progress on an Experimental Program to Determine the Consequences of Pressure Tube Rupture in CANDU Reactors

G.I. Hadaller, A.P. Muzumdar

375-381

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The Behaviour of the CANDU Calandria Tubes

C.E. Ells, C.E. Coleman, V. Fidleris, E.T.C. Ho, A.R. Causey

382-389

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The Failure of the Pressure Tube in Fuel Channel Bruce NGS-A Unit 2 in March 1986

G.J. Field, M.W. Shanahan

390-398

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Operational Safety Management at Point Lepreau Generating Station

D.F. Weeks, D.J. Wilson

399-403

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Suitability of On-Line Leak Tests for CANDU Single-Unit Containment Buildings

J.F. Lafortune, C.A. McDevitt, S. Poolpol

404-408

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Development of a CANDU Fuel Channel Replacement Program

E.J. Bennett, R.A. Eager

409-417

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Emergency Operating Procedures Based on Thermodynamic State

R. Colquhoun, A.R. Johnson, J.F. Mccallum, D.F. Weeks

418-424

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An Overview of the Development of Leak Detection Monitoring for Ontario Hydro Nuclear Stations

J.M. Kenchington, P.J. Ellis, D.G. Meranda

425-432

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Vibration Analysis of the PHT Piping System of Point Lepreau NGS

M. Mikasinovic

433-440

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CANDU 600 Reactor Output Optimization

P.J. Allen, M.R. Soulard, V.C. Orpen, P.D. Thompson

441-448

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Principles and Techniques to Accelerate the 'Realization' of Nuclear Plant

P.D. Stevens-Guille, I.E.B. Lauchlan

449-453

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Improved CANDU 600 Designability

N.G. Craik

454-457

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Optimization of Darlington Tritium Removal Facility Performance Effects of Key Process Variables

A. Busigin, S.K. Sood

458-461

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The Development of Industrial Linacs with the Capacity to Open New Horizons for Electron Processing

A.J. Stirling

462-466

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The Slowpoke-2 Facility at the Royal Military College: Improved Performance and Versatility

P.A. Beeley, L.G.I. Bennett, H.W. Bonin, L.S. Fisher, L.S. Wright

467-472

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