Skip to main content

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors, Parts 1 and 2

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors, Parts 1 and 2

Steve Bruemmer (Editor), Peter Ford (Editor), Gary Was (Editor)

ISBN: 978-1-118-78777-9

Oct 2013

1256 pages

Select type: E-Book

Product not available for purchase

Description

This collection presents an exchange of ideas among scientists and engineers about the economic and safety concerns surrounding environmentally induced materials problems which lead to nuclear power plant outages. Scientists and engineers concerned with the environmental degradation processes (corrosion, mechanical, and radiation effects) present their latest results on such topics as life extension/relicensing and materials problems associated with spent fuel storage and radioactive waste disposal. This collection will be of interest to utility engineers, reactor vendor engineers, plant architect engineers, researchers concerned with materials degradation, and consultants involved in design, construction, and operation of water reactors.

PWR Primary-1: Mechanisms

An Overview of Internal Oxidation as a Possible Explanation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWRs 3
P.M. Scott

Methodology to Understand the Mechanisms of PWSCC 15
T. Yonezawa

Hydrogen Effects on PWR SCC Mechanisms in Monocrystalline and Polycrystalline Alloy 600 27
T. Magnin, F Foct, and O. de Bouvier

Insights into Environmental Degradation Mechanisms from Analytical Transmission Electron Microscopy of SCC Cracks 41
L.E. Thomas and S.M. Bruemmer

Measurement of the Fundamental Parameters for the Film-Rupture/Oxidation Mechanism—The Effect of Chromium 49
S.A. Attanasio, J.S. Fish, W.W. Wilkening, P.M. Rosecrans, D.S. Morton, G.S. Was, and Y Yi

Comparison of Hydrogen Effects on Alloy 600 and 690 59
S. Smuk, H. Hänninen, Y Jagodzinski, O. Tarasenko, and P. Aaltonen

Comments on a Proposed Mechanism of Internal Oxidation for Alloy 600 as Applied to Low Potential SCC 69
R. W. Staehle and Z. Fang

Internal Oxidation and Embrittlement of Alloy 600 79
R.C. Newman, T.S. Gendron, and P.M. Scott

PWR Primary-2: Chemistry and Failure Analysis

The Effect of Primary Coolant Zinc Additions on the SCC Behaviour of Alloy 600 and 690 97
M.G. Angelí, S.J. Allan, and G.P. Airey

PWSCC of Alloy 600: A Parametric Study of Surface Film Effects 105
C. Soustelle, M. Foucault, P. Combrade, K. Wolski, and T. Magnin

Modelling of Stress Corrosion Crack Initiation on Alloy 600 in Primary Water of PWRs 115
S. LeHong, C. Amzallag, and A. Gelpi

Effect of Water Chemistry on Environmentally Assisted Cracking in Alloy 600 in Simulated PWR Environments 125
P. Lidar, M. König, J. Engström, and K. Gott

Unique Primary Side Initiated Degradation in the Vicinity of the Upper Roll Transition in Once Through Steam Generators from Oconee Unit 1 133
J.P Molkenthin, T.P. Magee, J.F. Hall, G.C. Fink, D. Rochester, and A. Mcllree

PWR Primary-3: Hydrogen Effects & Microstructure

On the Possibility of Forming Ordered Ni2Cr in Alloy 690 143
T. Larsson, J.-O. Nilsson, and J. Frodigh

Hydrogen Embrittlement of PH 13-08 Mo Stainless Steel in PWR Environment Effect of Microstructure 149
J.M. Cloué, M. Foucault and E. Andrieu

The Effect of Special Grain Boundaries on IGSCC of Ni-16Cr-9Fe-xC 157
B. Alexandreanu, B.M. Capell, and G.S. Was

Fracture Behavior of Nickel-Based Alloys in Water 167
W.J. Mills and CM. Brown

Hydrogen-Assisted Failure of Alloys X-750 and 625 under Slow Strain-Rate Conditions 179
R.S. Daum, A.T. Motta, D.A. Koss, and D.D. Macdonald

An Experimental Study of the Hydrogen Embrittlement of Alloy 718 in PWR Primary Water 189
J.G. Spilmont, J.M. Cloué, M. Foucault, B. Viguier, and E. Andrieu

A Study of Corrosion Mechanisms and Kinetics of Alloy 718 in PWR Primary Water 197
O. Brucelle, J.G. Spilmont, J.M. Cloué, M. Foucault, B. Viguier, and E. Andrieu

Stress Corrosion Crack Propagation Rate of Alloy 600 in the Primary Water of PWR: Influence of a Cold Worked Layer 207
O. Raquet and G. Santarini

PWR Primary-4: Crack Growth & Creep

Stress Corrosion Crack Growth Rate Measurements in Alloys 600 and 182 in Primary Water Loops Under Constant Load 217
T. Cassagne, D. Caron, J. Daret, and Y. Lefèvre

Initial Results on the Stress Corrosion Cracking Monitoring of Alloy 600 in High Temperature Water Using Acoustic Emission 225
T. Cassagne, D. Caron, J. Daret, A. Proust, H. Mazille, G. Turluer, and D. Boulanger

Stress Corrosion Crack Propagation Rates in Reactor Vessel Head Penetrations in Alloy 600 235
C. Amzallag and F. Vaillant

Stress Corrosion Life Assessment of Alloy 600 PWR Components 243
C. Amzallag, S. LeHong, C. Pages, and A. Gelpi

Influence of Chromium Content and Microstructure on Creep and PWSCC Resistance of Nickel Base Alloys 251
F. Vaillant, J.-D. Mithieux, O. de Bouvier, D. Vançon, G. Zacharie, Y. Brechet, and F. Louchet

A Simplified Model for SCC Initiation Susceptibility in Alloy 600, with the Influence of Cold Work Layer and Strength Characteristics 261
Y.S. Garud and R.S. Pathania

Creep of Nickel Base Alloys in High Temperature Water 269
Y. Yi, G.S. Was, J. Cookson, J.S. Fish, S.A. Antanasio, H. T. Krasodomski, and W. W. Wilkening

An Investigation of Alloy 182 Stress Corrosion Cracking in Simulated PWR Environment 279
W.H. Bamford, J.P Foster, and R.S. Pathania

BWR-1: Cracking Response

Characteristics of Crack Propagation Through SCC under BWR Conditions in Stainless Steels Stabilized with Titanium or Niobium 299
J. Hickling, P.L. Andresen, R.M. Horn, and H. Hoffmann

Intergranular Stress Corrosion Cracking of Unsensitized Stainless

Steels in BWR Environments 311
T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutcliff, S. Sitzman, and R.M. Horn

Failed Components in the Ringhals 1 (BWR) Steam Separator 319
K. Norring, J. Lagerström, L. Storm, K. Norrgàrd, G. Embring, and M. Ölmeby

Stress Corrosion Cracking of Stabilized Austenitic Stainless Steels in Various Types of Nuclear Power Plants 325
M.O. Speidel and R. Magdowski

Initiation of Stress Corrosion Cracking in Alloys 600 and 182 331
A. Jenssen, M. Stigenberg, and L. Ljungberg

The Electrochemical Corrosion Potential and Stress Corrosion Cracking of 304 Stainless Steel under Low Hydrogen Peroxide Concentrations 339
Y. Wada, A. Watanabe, M. Tachibana, N. Uetake, and S. Uchida

Crack Growth of Stabilized Stainless Steels in 02-Containing High Temperature Water: Influence of Environmental and Material Conditions 347
R Kilian, U. Eberle, G. Brummer, H. Hoffmann, U. Ilg, V. Maier, and M. Widera

BWR-2: Mechanism/Life Extension

Effect of Stress Biaxiality on SCC Growth Rate 361
S. Suzuki

Prediction of Environmentally Assisted Cracking and Its Relevance to Life Management inBWRs 373
P.L. Andresen, F.P Ford, T.M. Angeliu, H.D. Solomon, and R.LCowan

Stress Corrosion Cracking Initiation in Austenitic Stainless Steel in High Temperature Water 383
K. Matocha and J. Wozniak

Effects of Acceleration Factors on the Probability Distribution of Stress-Corrosion Crack Initiation Life for Alloys 600, 182, and 82 in High-Temperature and High-Purity Water Environments 389
M. Akashi and G. Nakayama

Modeling the Accumulation and Mitigation of SCC Damage in BWRs 399
D.D. Macdonald and I. Balachov

BWR-3: SCC Data Quality & System Definition

SCC Testing and Data Quality Considerations 411
P.L. Andresen

Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel 288C Water: A Five Laboratory Round Robin 423
P.L. Andresen, K. Gott, and J.L. Nelson

First Lower Plenum ECP Measurement in an Operating BWR 435
S. Hettiarachchi, D.A. Hale, R. Burrill, I. Gorrochategui, R. Coello, S. Suzuki, and M. Sambongi

The Effect of H202 on ECP Under a Variety of Flow Rate and Temperature 443
M. Sambongi, S. Suzuki, N. Ichikawa, J. Takagi, K. Akamine, and M. Sakai

Corrosion Potential Monitoring in Swedish BWRs on Hydrogen Water Chemistry 453
A. Molander, K. Pein, A.-L. Forsgren, and G. Karlberg

ECP Suppression Mechanism and ECP Simulation for a Small-Area Noble Metal Deposition under Hydrogen Water Chemistry Conditions 461
M. Sakai

BWR-4: Mitigation / Life Extension

Electrochemical Validity of Noble Metal Technology for B WR Application 469
Y.-J. Kim

Effects of Cu and Zn on Catalytic Response of Noble Metal Doped 304 SS in 288°C Water 477
Y.-J. Kim

Full Cycle Performance of a Noblechem™ Treated BWR 485
S. Hettiarachchi, R.L. Cowan, R.J. Law, W.D. Miller, and T.P Diaz

Effect of Corrosion Potential on the SCC Initiation Lifetime of Alloy 182 Weld Metal 493
N. Saito, S. Tanaka, and H. Sakamoto

Effects of Mixed Metal Addition on Surface Film and Corrosion Prevention of Stainless Steel in BWR Water 501
Y Saitoh, H. Midorikawa, T. Kikuchi, and T. Sakai

Intergranular Stress Corrosion Cracking of Platinum Coated Type 304 Stainless Steels in High Temperature Water 511
T.-K. Yeh, Y.-C. Lin, and C.-H. Tsai

Low Temperature Aging Embrittlement of CF-8 Stainless Steel 517
L.M. Lietzan, M.D. Mathew, K.L. Murty and V.N. Shah

Closed-Loop Sidestreams for Investigating Corrosion Control using Regenerative Biofilms (CCURB) in Service Water Systems 527
K. Trandem, K. Ismail, P.J. Arps, and J.C. Earthman

The Predicted Effectiveness of Noble Metal Treatment at the Chinshan Boiling Water Reactor
T.-K. Yeh, C. Chang, F. Chu and C.-S. Huang

[Though this paper is topically relevant to BWR-4: Mitigation/Life Extension, it begins on page 1,211.]

PWR Secondary-1 : System Definition

Experimental Simulation of Boiling Crevice Chemistry 537
C.B. Bahn, I. S. Hwang, I.H. Rhee, U.C. Kim, and J.W. Na

Effects of the Feedwater Sodium/Chloride Ratio and Hydrazine on Crevice Corrosion 545
J.B. Lumsden, G.A. Pollock, P.J. Millett, N. Torigoe, and H. Takamatsu

Secondary Side Corrosion of French PWR Steam Generator Tubing: Contribution of Surface Analyses to the Understanding of the Degradation Process 555
J.M. Boursier, M. Dupin, P. Gösset, and Y Rouillon

Evidence for the Reduction of Sulfates Under Representative SG Secondary Side Conditions, and for the Role of Reduced Sulfates on Alloy 600 Tubing Degradation 567
J. Daret, T. Cassagne, Y Lefèvre, T.Q. Tran, R. Benoit, and R. Erre

Study of Deposits and Corrosion Products in Secondary Side of Steam Generators by Fourier Transform Infra Red Spectroscopy: Laboratory Study 577
S. Chevalier, M. Organista, B. Sala, A.Gelpi, and R. Erre

Electrochemical Study of the Corrosion Processes of the Secondary Side of Steam Generators 587
B. Sala, S. Chevalier, A. Gelpi, H. Takenouti, and M. Keddam

PWR Secondary-2: Cracking Response

Role of Grain Boundary Characteristics in Caustic IGA/SCC Resistance of Thermally Treated Alloy 690 and Shot-Peened Alloy 800 601
H. Kawamura, H. Hirano, S. Shirai, H. Takamatsu, T. Matsunaga, K. Yamaoka, K. Oshinden, and H. Takiguchi

Relationships Between Stress Corrosion Cracking Tests and Utility Operating Experience 611
A. Baum

A Review of the Effects of Silica on Stress Corrosion Cracking of Steam Generator Tubes 619
P.J. Prabhu

Top of Tubesheet Cracking in Bruce NGS Steam Generator Tubing: An Assessment of Material and Environmental Factors 629
M. Clark, O. Lepik, A. Brennenstuhl, M. Minai, and I. Thompson

Laboratory Examination Results from Oconee Nuclear Station Once Through Steam Generator Tubes 639
D. P. Rochester and R.W. Eaker

Corrosion Control and Lay-up of the Crystal River-3 Steam Generators and Secondary Plant during an Extended Outage 649
R.H. Thompson and W.R. Kassen

Lead-Induced SCC Propagation Rates in Alloy 600 657
M.D. Wright and M. Mirzai

Characterization of Stabilized Stainless Steels Welds of PWR Piping Systems 667
M. Widera, R. Kilian, R. Bartsch, H. Hoffmann, G. König, and O. Wächter

PWR Secondary-3: Mechanisms

Modeling the Secondary Side Corrosion of Tubings: A Help to the Maintenance Policy of PWR Steam Generators 679
F Vaillant, E.-M. Pavageau, M. Bouchacourt, J.-M. Boursier, and P. Lemaire

Development and Application of the SCC Parameter for Predicting SCC in the Secondary Side of Steam Generators 689
Z. Fang and R.W. Staehle

Nickel Alloy Stress Corrosion Cracking in Neutral and Lightly Alkaline Sulfate Environments 695
O. de Bouvier, B. Prieux, F. Vaillant, M. Bouchacourt, and P. Lemaire

Lead Assisted Stress Corrosion Cracking of Alloy 690 703
M.J. Psaila-Dombrowski, FH. Hua, and P.E. Doherty

Regulation Aspects

EPRI R&D for Safe and Economic Long-Term Nuclear Plant Operation 713
R.L. Jones, J. Carey, and C. Wood

The History of Cracking in the Reactor Coolant Pressure Boundary of Swedish BWR Plants 725
K. Gott

Plant Life Management Programme Preparation for WWER-440/V-213C Units in Czech Republic 733
M. Brumovsky, M. Ruscák, and J. Zdárek

Regulatory Perspective on Industry's Response to Generic Letter 97-06, "Degradation of Steam Generator Internals" 741
S. Coffin, M. Subudhi, and J. Higgins

Status of Review of Applications and Issues of License Renewal by Materials and Chemical Engineering Staff at the U.S. Nuclear Regulatory Commission 747
M. Banic

Welding/Processing

Development of Compressive Residual Stresses in Underwater PTA Welds 757
Z. Feng, R. A. White, E. Willis, and H.D. Solomon

Development of Repair-Welding Technology for Irradiated 'Materials of LWR 767
K. Nakata, S. Kasahara, H. Takeda, and M. Oishi

Using an Abrasive Waterjet to Machine and Remediate Nuclear Components 775
J.B Hall, K.B. Stuckey, and S. Fyfitch

Surface Modification for PWSCC Prevention of Alloy 600 by a Laser Cladding Technique 783
S. Kasahara, M. Sato, T. Ohya, M. Kanikawa, and H. Kanasaki

Welding as a Repair Option for BWR In-Vessel Components 793
W.E. Norris, A.L. Lund, CE. Carpenter, Jr., LE. Willertz, R.C. Thomas, and R.L. Dyle

Low Alloy Steel—Embrittlement

Observations on Sensitivity of RPV Integrity Probabilistic Fracture Mechanics Evaluations to Input Parameters 803
A.L. Hiser, Jr., S.C.F. Sheng, and S.N. Malik

Irradiation Behavior of Electricité De France PWR Vessel Steel 813
C. Pichón, Y. Grandjean, S. Saillet, G. Bezdikian, and J.-M. Frund

Effects of Copper, Phosphorus and Nickel on Radiation Damage in ASTM A533-B Steel 821
M. Brumovsky

Understanding the Role of Defect Production in Radiation Embrittlement of Reactor Pressure Vessels 827
D.E. Alexander, LE. Rehn, G.R. Odette, G.E. Lucas, D. Klingensmith, and D. Gragg

Effects of Neutron Irradiation on Positron Lifetime and Micro-Vicker Hardness of Fe-Cu Model Alloys and Reactor Pressure Vessel Steel 835
A. Hempel, M. Hasegawa, G. Brauer, F Plazaola, M. Saneyasu, and Z. Tang

An Evaluation of Temper Embrittlement in A508 Grade 4N Steel 845
D.B. Knorr

Low Alloy Steel—EAC & Deformation

Stress Corrosion Cracking of Low Alloy Steels under BWR Conditions; Assessment of Crack Growth Rate Algorithms 855
F P. Ford, RM. Horn, J. Hickling, R. Pathania, and G. Bruemmer

LCF Crack Initiation in WB36 in High Temperature Water 865
H.D. Solomon, R.E. DeLair, and E. Tolksdorf

Stress Corrosion Cracking Tests of RPV Steels under Simultaneous BWR Coolant and Irradiation Conditions 875
M. Ruscák, J. Kysela, A. Brozová, O. Erben, M. Postler, G. Brummer, H. Hoffmann, U.llg, and W. Rühle

Determination of EAC Threshold in Ferritic RPV Steel by Constant Load and Rising Displacement Methods 885
A. Brozová, M. Ruscák, and W. Dietzel

Evaluation of Crack Tip Solution Chemistry of Low Alloy Steel in Oxygenated High Temperature Water 893
Y Lee, T. Shoji, and K.S. Raja

Stress Corrosion Cracking of Reactor Pressure Vessel Steels Under Boiling Water Reactor Conditions 901
J. Heldt and H.P Seifert

European Round Robin on Constant Load EAC Tests of Low Alloy Steel under BWR Conditions 911
D. Blind, F. Hüttner, A. Wünsche, K. Küster, H.-P. Seifert, J. Heldt, A. Roth, P. Karjalainen-Roikonen, and U. Ehrnstén

Radiation Effects on Stress Corrosion Cracking

Effect of Pre-Irradiation Grain Boundary Chemistry on IASCC 923
M. Kodama, Y Ishiyama, S. Namatame, S. Suzuki, K. Fukuya, H. Sakamoto, K. Nakata, and T. Kato

Irradiation-Assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels 931
H.M. Chung, W.E. Rüther, R.V. Strain, W.J. Shack, and T.M. Karlsen

Intergranular Cracking of an Irradiated Ti-Stabilized Austenitic Stainless Steel Spacer Grid Sleeve from a VVER-440 Reactor 941
U. Ehrnstén, P. Nenonen, P. Aaltonen, R. Teräsvirta, and O. Hietanen

Qualification and Application of Instrumented Specimens for In-Core Studies on Cracking Behaviour of Austenitic Stainless Steels 951
T.M. Karlsen and E. Hauso

Neutron Irradiation Induced Changes in Percent Intergranular Stress Corrosion Cracking of Thermally-Sensitized Type 304 Stainless Steels 963
T. Onchi, K. Hide, M. Mayuzumi, and T. Hoshiya

Cracking Mechanisms of Type 304L Stainless Steel Core Shroud Welds 973
H.M. Chung, J.-H. Park, W.E. Rüther, R.V. Strain, J.E. Sanecki, N.J. Zaluzec, M.S. Yu, and T.T. Yang

Development of a Comprehensive Material Performance Database (JMPD) and Analyses of Irradiation Assisted Stress Corrosion Cracking Data 987
Y Kaji, T. Tsukada, H. Tsuji, and H. Nakajima

Assessment of WWER Reactor Pressure Vessel Internals and Program of Lifetime Management 997
M. Ruscák, M. Zamboch, and O. Erben
Radiation Effects on Deformation and Swelling

Radiation Hardening in Austenitic Stainless Steels Irradiated in LWRs 1007
D.J. Edwards, E.P. Simonen, and S.M. Bruemmer

Optimized Chemical Composition and Heat Treatment Conditions of 316 CW and High-Chromium Austenitic Stainless Steels for PWR Baffle Former Bolts 1015
T. Yonezawa, T. Iwamura, K. Fujimoto, and K. Ajiki

Irradiation Creep Behavior of High-Purity Stainless Steels and Ni-Base-Alloys 1027
F. Garzarolli, P. Dewes, S. Trapp-Pritsching, and J.L. Nelson

The Effect of Low Dose Rate Irradiation on the Swelling of 12% Cold-Worked 316 Stainless Steel 1035
T.R. Allen, J.I. Cole, H. Tsai, S. Ukai, S. Mizuta, and T. Yoshitake

Void Swelling of Annealed 304 Stainless Steel at ~370-385°C and PWR-Relevant Displacement Rates 1045
G.M. Bond, B.H. Sencer, FA. Garner, M.L. Hamilton, T.R. Allen, and D.L. Porter

Void Swelling at Low Displacement Rates in Annealed X18H10T Stainless Steel at 30-56 DPA and 280-332°C 1051
F Garner, S.I. Porollo, A.N. Vorobjev, Y.V. Konobeev, and A.M. Dvoriashin

Neutron-Induced Swelling and Embrittlement Behavior of Two Russian Stainless Steels at PWR-Relevant Temperatures and 65-85 DPA 1061
S.I. Porollo, A.M. Dvorianshin, A.N. Vorobjev, V.M. Krigan, Y.V. Konobeev, F Garner, N.I. Budylkin, and E. Mironova

Effects of Neutron Irradiation on Deformation Behavior of Nickel-Base Fastener Alloys 1069
R. Bajaj, W.J. Mills, B.F Kammenzind, and M.G. Burke

Radiation Effects on Microstructure and Microchemistry

Microstructural, Microchemical and Hardening Evolution in LWR-Irradiated Austenitic Stainless Steels 1079
S.M. Bruemmer, D.J. Edwards, B.W. Arey, and LA. Chariot

Microchemistry and Microstructure Evolution in Proton-Irradiated Austenitic Stainless Steels 1089
J.T. Busby, J. G an, M. Daniels, G.S. Was, S.M. Bruemmer, D.J. Edwards, and E.A. Kenik

Comparison of Radiation Induced Degradation in Several Austenitic Stainless Steels Used for Core Internals in LWR 1099
T. Aoki, T. Fukuda, Y Isobe, A. Hasegawa, M. Sato, K. Abe, K. Matsueda, and Y. Nishida

Local Evolution of Microstructure and Microchemistry Near Grain Boundaries in Irradiated Austenitic Stainless Steels 1107
E.P. Simonen, D.J. Edwards, and S.M. Bruemmer

Effects of Minor Elements and Thermal Treatment on EAC of Austenitic Simulating Steels in PWR Primary Water and Implication to IASCC 1115
G. Li, H. Kaneshima, and T. Shoji

Studies on Surface Oxide Films of Stainless Steels Having Simulated Post-Irradiated Grain Boundary Chemistries 1125
K.S. Raja, T. Masuda, T. Shoji, and Y Lee

Zircaloy

The Use of Impedance Spectroscopy to Follow the Effect of Lithium on
Zirconium Oxide Behavior 1137
B. Albinet, B. Sala, M. Organista, and A. Frichet

AC Impedance Characteristics of Oxide Film on Zirconium 1145
J.Y Lim, B.C. Han, and I. S. Hwang

Amorphization of Laves-Phase Precipitates in Zircaloy-4 by Neutron Irradiation 1153
D.F Taylor, H.R. Peters, and W.J.S. Yang

A Simple Kinetic Model of Zircaloy Zr(Fe,Cr)2 Precipitate Amorphization during Neutron Irradiation 1161
D.F. Taylor, H.R. Peters, and W.J.S. Yang

Characteristics of Axial Splits in Failed BWR Fuel Rods 1169
G. Lysell and V. Grigoriev

On the Indications of Shear Fracture at the Tip of an Axial Notch in Zircaloy Cladding 1177
V. Grigoriev and K. Pettersson

The Fracture of Zircaloy-2 Plate and Fuel Cladding Tubing in Hydrogen Gas 1183
R.G. Rowe, S.T. Mahmood, S.B. Wisner, and R.B. Adamson

On the Mechanism of Axial Splits in Failed BWR Fuel Rods 1191
K. Edsinger, S. Vaidyanathan, and R.B. Adamson

Studies on Delayed Hydride Cracking of Zircaloy Cladding 1201
K.R. Pettersson, K. Kese, and P. Efsing

The Predicted Effectiveness of Noble Metal Treatment at the Chinshan Boiling Water Reactor 1211
T.-K. Yeh, C. Chang, F. Chu and C.-S. Huang

Author Index 1225