Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

2460 Pages·2019·107.715 MB·English

by  John H. Jackson, Denise Paraventi, Michael Wright

PROCEEDINGS OF THE
August 13–17, 2017
Marriott Portland Downtown Waterfront
Portland, Oregon, USA
EDITED BY:
John H. Jackson · Denise Paraventi · Michael Wright
The Minerals, Metals & Materials Series
John H. Jackson Denise Paraventi
(cid:129)
Michael Wright
Editors
Proceedings of the 18th
International Conference
on Environmental
Degradation of Materials
in Nuclear Power
–
Systems Water Reactors
123
Editors
JohnH.Jackson Michael Wright
IdahoNational Laboratory ChalkRiver Laboratories
IdahoFalls,ID, USA Canadian Nuclear Laboratories
ChalkRiver, ON, Canada
Denise Paraventi
Naval NuclearLaboratory
Pittsburgh, PA, USA
ISSN 2367-1181 ISSN 2367-1696 (electronic)
TheMinerals, Metals& Materials Series
ISBN978-3-030-04638-5 ISBN978-3-030-04639-2 (eBook)
https://doi.org/10.1007/978-3-030-04639-2
LibraryofCongressControlNumber:2018962127
©TheMinerals,Metals&MaterialsSociety2019
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Preface
Theproductionofelectricityfromnuclearpowerreactorsoccupiesacentralrolein
meeting worldwideenergy requirements. As of January2017, there are 450 power
reactorsoperatingin30countries.Theindustrycontinuestogrow,despitesetbacks.
There are 60 new construction projects underway in 15 different countries. The
great majority of the new reactors are being built in countries with emerging
economies.FortheUSA,westernEurope,andJapan,althoughtherearesomenew
construction projects, the emphasis is on maintaining capacity and extending the
operating lives of existing reactors. Of the worldwide fleet of 450 power reactors,
273ofthemhavebeeninserviceforover30yearsand67havebeeninservicefor
over 40 years.
Ifnuclearpowerisgoingtocontinuemakingacontributiontoworldwideenergy
demands, power plants must be operated in a safe and cost-effective manner.
Central to safety and reliability goals for these plants is effective materials degra-
dation management. Effective materials degradation management must include the
maintenance of operating plants, prolongation of the lifetime of plants, and choice
and use of materials in new plants.
Environmentally induced materials degradation represents a significant fraction
of materials-related problems in today’s nuclear power plant operation. Under
extended lifetime to 60 years or potentially longer, understanding materials
degradation will be even more important as these issues are of concern for both
economic and safety reasons. Understanding today’s materials problems is also
critical for the future in the advanced reactor sector.
The purpose of the “Environmental Degradation of Materials in Nuclear Power
Systems” conference series is to foster an exchange of ideas about such problems
and their remedies. The conference series has been running since 1983. The
meetingscovermaterialsproblemsfacingnickelbasealloys,stainlesssteels,ferritic
steels, zirconium alloys, and other alloys in water environments of relevance.
Componentscoveredincludeheattransportsystempressureboundarycomponents,
reactor vessels and internals, steam generators, fuel cladding, irradiated compo-
nents, fuel storage containers, and balance of plant components and systems. The
scopeandemphasisoftheindividualconferenceshavevariedoverthepast30years
v
vi Preface
as different challenges arose and were resolved. Reflecting the growing concerns
over materials aging in general, this, the 18th conference in the series, includes a
session dedicated to cable insulation aging and concrete aging.
Thisconferencefeaturedthepresentationof164papers,spreadover25sessions.
The conference was attended by over 200 scientists and engineers from 17 coun-
tries, representing power plant operators, reactor vendors, regulators, national
laboratories, research institutes, universities, and other organizations affiliated with
the nuclear and nuclear service industries.
However, this year’s meeting was sadly missing one of its longest serving and
most influential contributors. January 2017 saw the passing of Dr. Roger
Washburne Staehle (1934–2017). Roger was an international giant in the field of
metallurgy and corrosion. Roger made enormous scientific and engineering con-
tributions to these fields, and he contributed to every one of the Environmental
Degradation meetings and personally attended the majority. Roger studied metal-
lurgicalengineeringatTheOhioStateUniversity(OSU),graduatingin1957.After
college, he worked for Admiral Hyman Rickover, the father of the US Nuclear
Navy, something Roger was immensely proud of. A successful and influential
academic career followed, with a major focus on materials degradation in com-
mercial nuclear power. In his later career, as an international consultant, mentor,
and instigator, Roger was an aggressive advocate for the best experimental and
analytical techniques. Roger was also a champion of international information
exchange. Over his last 20 years, Roger focused considerable efforts to build col-
laborative interactions in China.
Returning to the current meeting, the organizers recognize the help of a dedi-
cated group of individuals who made this 18th edition of the conference a success
andtheseproceedingspossible.TheProgramCommitteeandSessionChairslisted
in this volume’s front matter played vital roles in organizing the sessions and
conducting paper reviews. These activities required a significant commitment
of their time, and they are greatly appreciated. The organizers are thankful to their
respective employers for making them available for participating in planning,
organizing, and serving at the conference.
Special thanks go to the Technical Program Chair, John Jackson of Idaho
NationalLaboratory,and theAssistant Technical Program Chair, Denise Paraventi
of the (Bettis) Naval Nuclear Laboratory for their tireless efforts in ensuring the
success of this conference.
Finally, we thank The Minerals, Metals & Materials Society (TMS) for their
assistance with conference planning, paper review, and publication of these
proceedings.
Michael Wright
General Conference Chair
In Memoriam
Roger Washburne Staehle (February 4, 1934–January 16, 2017)
It is with great sadness that we mark the passing of Dr. Roger W. Staehle, an
international giant in the field of metallurgy and corrosion. Roger made enormous
scientific and engineering contributions to these fields, but was best known for his
friendship, generosity, and drive to support and recognize the work of others—no
one “out-gave” Roger.
Roger became ill after a fall during his morning walk in the snow and ice. He
died several weeks later with members ofhis family athis bedside. He issurvived
by his brother, George, and his children, Elizabeth, Eric, Sara, Erin, and William.
Roger Staehle studied metallurgical engineering at The Ohio State University
(OSU),graduatingin1957asthepresidentofhisseniorclass.Aftercollege,Roger
fulfilled his Navy ROTC obligation onthe staffof AdmiralHyman Rickover,who
was the father of the US Nuclear Navy. Following this extensive education in
nuclear technology, he returned to get his Ph.D. at OSU under the distinguished
guidanceofProf.MarsFontana.Hegraduatedin1965andimmediatelyjoinedthe
vii
viii InMemoriam
metallurgical engineering faculty. Roger founded the Fontana Corrosion Center
(FCC) and built it into one of the largest and most influential academic corrosion
laboratoriesintheworld.Bytheendofthe70s,hehadagroupofover40peoplein
theFCC,withamajorfocusonmaterialsdegradationincommercialnuclearpower.
He left OSU in 1979 to become Dean of the Institute of Technology at the
University of Minnesota (College of Science and Engineering), a position he held
until1983.Rogerremainedveryactivetotheendasaconsultantspecializinginthe
degradation of materials in nuclear reactors.
Roger received many awards for his accomplishments. He was a fellow of
NACE International and The Electrochemical Society and received the W.R.
Whitney Award from NACE. He was elected to the US National Academy of
Engineeringin1978,whenhewas44yearsold,oneoftheyoungesttobeelectedto
NAEatthattime.RogerservedastheeditorforCORROSIONjournalfrom1973to
1981.
Roger devoted enormous energy to coordinating and supporting research
throughout the world. He made hundreds of trips to many countries, including
Russia, Japan, China, Korea, Europe, South Africa, South America, the Middle
East, investing consistently and heavily in promoting international collaborations.
He was sufficiently proficient in Russian at one time to be able to lecture in that
language. Among the early examples of his efforts to develop international col-
laborations was his organization of major international conferences.
Roger also promoted international collaboration by inviting and hosting innu-
merable prominent experts, as well as early-career scientists, to OSU, and it had a
dramatic impact on the thinking and progress throughout the world (including the
USA),inadditiontofosteringthecareersofmanydozensofinternationalscientists.
Roger was heavily engaged in the International Cooperative Group on
Environmentally Assisted Cracking, whose charter is to promote international
exchange of information, emerging data, and the best experimental techniques for
addressing cracking in high-temperature water environments. In the last 20 years,
Roger focused considerable efforts to build collaborative interactions in China,
aimed primarily but not exclusively on issues related to materials degradation in
commercialnuclearpowerreactors.Heinitiatedandorganizedfourmajorsymposia
inChina,thefirstofwhichwas“MaterialsProblemsinLightWaterNuclearPower
Plants: Status, Mitigation, Future Problems” in 2005. Roger was single-handedly
responsible for attracting the best of the world’s experts in each aspect of each
symposium,andeachsymposiumattractedabout200engineersandscientistsfrom
throughout China.
In 2008, Roger conceived and organized a conference on stress corrosion crack
(SCC) initiation in Beaune, France, involving about 130 scientists. The week-long
conferencewasdesignedtoexchangeideas,definecriticalexperiments,anddiscuss
experimentaltechnique.ManysimilareffortswereinstigatedbyRogerinareassuch
asleadandsulfureffectsinsteamgenerators,alloyswithimprovedSCCresistance.
In2010,Rogerundertookamassiveefforttobringtogetherworldexpertsindiverse
fieldswhocouldspeaktotheissuesoffundamentalunderstandingandmodelingof
SCC. The series of four annual meetings brought together about 40 international
InMemoriam ix
experts for a week-long workshop. Roger realized the importance of such a
meeting, defined the content, identified and invited the experts, and solicited sup-
port from about a dozen agencies and companies.
These are but a few examples of Roger’s selfless, energetic efforts to promote
international collaboration, which are in turn but a fraction of his efforts in con-
sulting,educating,lecturing,mentoring,writingawardnominationsandreferences,
etc. It is difficult to imagine a world without Roger’s presence, friendship, vision,
and energy.
Peter L. Andresen, Ron Latanision, and Gerald S. Frankel
First Published by NACE in CORROSION—Vol. 73, No. 3
Contents
Part I PWR Nickel SCC—SCC
Scoring Process for Evaluating Laboratory PWSCC Crack Growth
Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52,
152, and Variant Weld Material ... .... .... .... .... .... ..... .... 3
Amanda R. Jenks, Glenn A. White and Paul Crooker
Applicability of Alloy 690/52/152 Crack Growth Testing Conditions
to Plant Components.... .... ..... .... .... .... .... .... ..... .... 15
Warren Bamford, Steve Fyfitch, Raj Pathania and Paul Crooker
SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones
in PWR Water .... .... .... ..... .... .... .... .... .... ..... .... 27
Peter L. Andresen, Martin M. Morra and Kawaljit Ahluwalia
NRC Perspectives on Primary Water Stress Corrosion Cracking
of High-Chromium, Nickel-Based Alloys. .... .... .... .... ..... .... 55
Greg Oberson, Margaret Audrain, Jay Collins and Eric Reichelt
StressCorrosionCrackingofAlloy52/152WeldmentsNearDissimilar
Metal Weld Interfaces... .... ..... .... .... .... .... .... ..... .... 67
B. Alexandreanu, Y. Chen, W.-Y. Chen and K. Natesan
Stress Corrosion Crack Growth Rate Testing of Composite Material
Specimens .... .... .... .... ..... .... .... .... .... .... ..... .... 87
DavidS.Morton,JohnV.Mullen,EricPlesko,JohnSutliff,RobertMorris
and Nathan Lewis
Investigation of Hydrogen Behavior in Relation to the PWSCC
Mechanism in Alloy TT690 .. ..... .... .... .... .... .... ..... .... 105
Takumi Terachi, Takuyo Yamada, Nobuo Totsuka and Koji Arioka
xi