Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE
Radiation embrittlement and aging mechanisms for NPP reactor pressure vessels and vessel internals have been studied within NPP Plant Life Management (PLIM) for evaluation, prediction, and monitoring of the critical components’ service life. The main achievements of the SAFELIFE project, integ...
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2004
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| Zitieren: | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE / L. Debarberis, F. Sevini, B. Acosta, S. Pirfo, M. Bieth, H. Weisshaeupl, K. Törrönen, A. Kryukov, M. Valo // Проблемы прочности. — 2004. — № 1. — С. 23-29. — Бібліогр.: 5 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859919084670418944 |
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| author | Debarberis, L. Sevini, F. Acosta, B. Pirfo, S. Bieth, M. Weisshaeupl, H. Törrönen, K. Kryukov, A. Valo, M. |
| author_facet | Debarberis, L. Sevini, F. Acosta, B. Pirfo, S. Bieth, M. Weisshaeupl, H. Törrönen, K. Kryukov, A. Valo, M. |
| citation_txt | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE / L. Debarberis, F. Sevini, B. Acosta, S. Pirfo, M. Bieth, H. Weisshaeupl, K. Törrönen, A. Kryukov, M. Valo // Проблемы прочности. — 2004. — № 1. — С. 23-29. — Бібліогр.: 5 назв. — англ. |
| collection | DSpace DC |
| container_title | Проблемы прочности |
| description | Radiation embrittlement and aging mechanisms
for NPP reactor pressure vessels and vessel internals
have been studied within NPP Plant Life Management
(PLIM) for evaluation, prediction, and
monitoring of the critical components’ service life.
The main achievements of the SAFELIFE project,
integrating various networks on PLIM issues, are
given. Results of neutron embrittlement of model
alloys are presented, and surveillance and research
data on WWER reactor pressure vessel and other
steels have been analyzed. Projects for the development
of destructive and non-destructive testing of
irradiated materials have been outlined.
В рамках программы PLIM исследовано радиационное охрупчивание и механизмы старения
конструкционных сталей внутрикорпусных устройств реакторов с целью оценки, прогнозирования
и мониторинга ресурса ответственных узлов АЭС. Изложены результаты проекта
SAFELIFE, объединяющего различные подходы к контролю ресурсом АЭС. Представлены
результаты радиационного охрупчивания модельных сплавов, проанализированы данные
испытаний с использованием образцов-свидетелей, а также исследована надежность
корпусных и других типов сталей. Предложены перспективы развития разрушающих и
неразрушающих методов радиационного охрупчивания материалов.
У рамках програми PLIM досліджено радіаційне окрнхчування і механізми
старіння конструкційних сталей та реакторів із метою оцінки, прогнозування
і моніторинга ресурсу відповідальних вузлів АЕС. Підсумовуються результати
проекту SAFELIFE, що об’єднує різні підходи щодо контролю
ресурсом АЕС. Представлено результати радіаційного окрихчування модельних
сплавів, проаналізовано дані випробувань із використанням зразків-
свідків, а також досліджується надійність корпусних та інших типів сталей.
Запропоновано перспективи розвитку руйнівних і неруйнівних методів радіаційного
окрихчення матеріалів.
|
| first_indexed | 2025-12-07T16:06:50Z |
| format | Article |
| fulltext |
UDC 539.4
Radiation Embrittlement Understanding for PLIM Activities at
EC-JRC-IE
L. Debarberis,a F. Sevini,a B. Acosta,a S. Pirfo,a M. Bieth,a H. Weisshaeupl,a
K. Törrönen,a A. Kryukov,b and M. Valoc
a Joint Research Center (JRC) of the European Commission, Institute for Energy (JRC-IE
Petten), Petten, the Netherlands
b RRC-KI, Moscow, Russia
c VTT, Espoo, Finland
УДК 539.4
Радиационное охрупчивание корпусных сталей в рамках программы
управления ресурсом АЭС
Л. Дебарбериса, Ф. Севиниа, Б. Акоста3, С. Пирфоа, М. Биета, X. Вайсхепла,
К. Торронен3, А. Крюков6, М. Валов
а Объединенный исследовательский центр Европейской комиссии, Энергетический
институт, Петтен, Нидерланды
б Российский исследовательский центр, Москва, Россия
в ВТТ, Эспо, Финляндия
В рамках программы PLIM исследовано радиационное охрупчивание и механизмы старения
конструкционных сталей внутрикорпусных устройств реакторов с целью оценки, прогно
зирования и мониторинга ресурса ответственных узлов АЭС. Изложены результаты про
екта SAFELIFE, объединяющего различные подходы к контролю ресурсом АЭС. Представ
лены результаты радиационного охрупчивания модельных сплавов, проанализированы дан
ные испытаний с использованием образцов-свидетелей, а также исследована надежность
корпусных и других типов сталей. Предложены перспективы развития разрушающих и
неразрушающих методов радиационного охрупчивания материалов.
Ключевые слова : радиационное охрупчивание, старение, АЭС, корпусная
реакторная сталь, химический состав.
1. Background. Nuclear electricity accounts for more than one third of the
total EU needs, and the life distribution of the operating plants is such that in
2005 more than 70% of the plants will have passed the 20-year lifetime and
almost 30% the 30-year age limit. In total, more than 100 LWRs in the EU and
Associated States are producing more than 100 GWe.
In view of the secure and safe supply of electricity, aging of power plants is
becoming of increasing concern in the EU as well as in the rest of the world. In
fact, with increasing operational plant life approaching gradually the original
© L. DEBARBERIS, F. SEVINI, B. ACOSTA, S. PIRFO, M. BIETH, H. WEISSHAEUPL, K. TÖRRÖNEN,
A. KRYUKOV, M. VALO, 2004
ISSN 0556-I7IX. Проблемы прочности, 2004, № 1 23
L. Debarberis, F. Sevini, B. Acosta, et al.
design life, aging issues are arising. The list of issues is very long and research
and development effort is required in order to understand and tackle them
properly.
Such issues include: RPV embrittlement, core shrouds, upper and lower head
cracking, sticking control rods, cracking in the control rod drive mechanism and
upper head penetrations, reactor coolant piping issues, steam generator
degradation, electric cable aging, and concrete aging.
An integrated view of aging mechanisms and optimization of PLIM (Plant
Life Management) activities is promoted together with the prevention,
performance and risk-informed-based approach.
In order to perform the PLIM task, an integration effort in the JRC has been
undertaken and a new PLIM Action, SAFELIFE, has been launched for the 6th
Framework Program (FP6), which integrates the efforts done in the past and the
competencies of various European Networks. The effort is required in order to
solve the problems summarized hereinafter. A complete list of NPP life
management problems is not easy to draw, but anyhow a general agreement has
been reached on several major items:
□ RPV embrittlement, effect of such elements as Cu, P, Ni, Mn, etc.
□ Cracking of reactor internals shroud, cracking of bolts
□ Thermal fatigue in piping
□ Integrity of dissimilar metal welds
□ Steam generator degradation cracking
□ Aging of electric cables and concrete structures
2. The JR C Institute for Energy and the SA FELIFE Action. The JRC-IE
with the AMES, NESC, ENIQ, NET, and SENUF European Networks and the
information and competence within the TACIS Unit are playing a key role in
solving such problems as plant life management, various aspects of: irradiation
embrittlement, material degradation assessment and monitoring, surveillance,
structural integrity, fracture mechanics studies, qualification of in-service
inspection methodologies for crack detection, and recently, risk aspects. In
addition, a new network, AMALIA, is in preparation in order to tackle the issues
related to core internals and Irradiation Assisted Stress Corrosion Cracking
(IASCC) phenomena. Some aspects of managing and mitigation of accidents,
neutron beam methods for residual stress measurements, and other problems
related to directives on pressure equipment are also dealt with.
For the 6th Framework Program, the JRC-IE has started the SAFELIFE
Action. SAFELIFE is integrating various existing and designed JRC tasks and
networks on the PLIM issues. PLIM is seen as a multi-disciplinary issue, which
requires application of various involved disciplines ranging from crack detection,
residual stress evolution, integrity assessment, degradation of material properties,
IASCC, maintenance practices, etc.
The major objectives of the SAFELIFE projects are planned to be as follows:
□ Best practices: promotion, development, and dissemination:
♦ assessing neutron embrittlement (Ni, Mn, Cu, P, etc.)
♦ annealing and re-embrittlement of WWER (PRIMAVERA)
♦ assessment of primary component integrity (Master Curve, dissimilar
welds, large-scale benchmark tests, etc.)
24 ISSN 0556-171X. npo6n.eubi npounocmu, 2004, № 1
Radiation Embrittlement Understanding
♦ thermal fatigue assessment
♦ residual stress evolution
♦ inspection qualification, risk-based approach and residual life
□ Enhancing competencies/facilities in nuclear safety
♦ high-flux reactor, irradiation technology, rigs and neutron beams, JRC
laboratories, reference materials.
♦ modeling, RPV cladding, etc.
□ Creation and implementation of the Training and Mobility Action:
♦ grant holders, visiting scientists, training workshops, Eurocourses, WEB,
etc.
□ Further exploit Networking (tool for Integration and Dissemination)
♦ completion of the projects GRETE, REDOS, PISA, FRAME, ATHENA,
NURBIM, SPIQNAR, ENPOWER, INTERWELD, ADIMEW, THERFAT
♦ development of new ones coherent to SAFELIFE, using FP6 tools
♦ promotion and operation of the Network of Excellence/I.P. on PLIM
♦ IAEA co-operation
□ Direct support to other Directorate Generals
During the EC’s FP4 and FP5, JRC-IE has been co-ordinating and managing
the major European Networks, namely, AMES, NESC, ENIQ, and also NET and
their research activities in the area of nuclear plant life management.
□ AMES deals with the problems of irradiation embrittlement, material
degradation assessment and monitoring, surveillance, etc. [1-4].
□ The NESC activity is dedicated to structural integrity, with a principal
focus on fracture assessment [5-7].
□ ENIQ considers risk-informed approaches to plant life management and
the qualification of in-service inspection methodologies for defect
detection and sizing [8].
□ NET deals with the application of neutron-based testing for residual stress
analysis, detection of defects, aging and irradiation damage, repair issues,
etc.
□ Relevant expertise on the subject is also available at the Institute for
Energy at the Unit supporting the TACIS/PHARE programs (SENUF
activity).
□ AMALIA is the newest network dealing with internals issues and IASCC
phenomena.
The Networks have brought together all key partners in Europe in various
fields of aging, structural integrity, and inspection related to plant life
management.
A large number of partnership projects in the area have been designed,
promoted, and carried out in the last ten years. These European Networks have
made a substantial contribution to the total effort in the field of nuclear plant life
management through a large number of shared cost actions, thematic networks,
concerted actions, and contribution-in-kind projects in the area.
For FP6, the JRC-IE has launched the SAFELIFE Action on PLIM [5] to
integrate the efforts done in the past and the competencies of various European
Networks (AMES, NESC, ENIQ, NET, AMALIA and SENUF) complemented by
the information and competence developed within the TACIS programs.
ISSN 0556-171X. npoôëeMbi npounocmu, 2004, № 1 25
L. Debarberis, F. Sevini, B. Acosta, et al.
3. Exam ple of Results in the A rea of Radiation Em brittlem ent. In what
follows we illustrate, as an example, some results obtained by AMES in the field
of neutron-embrittlement. Figure 1 summarizes the results obtained from the
model alloy project. The results showing the influence of nickel on irradiation
embrittlement in synergy with copper and phosphorus are an important element
for improved embrittlement-prediction formulas for high-nickel steels for RPVs
like WWER-1000.
300 -------------------------------------------------------------------------------------
250
^ ;00
£
a -'so«
E—H
ffl 1 do Q
5 0
0 20 40 60 SO 100
800(P + 0.07Cu)
I *
A
X
X ,
— x — * —
♦ Very Low Nickel
A Medium Nickel
X High Nickel
X Very High Nickel
----------- Linear (Very
Low Nickel)
■ Logarithmic
(Very High Nickel)
300
- .
a
E
E-CC
O
TdP
cd<u
200
150
100
50
0
0.001
[P+ 0.07Cu][Ni - 0.1](a+b)
+15%
7 W
.^■/7
v T
R2 = 0.8841
0 100 200 300
Calculated DBTT shift (0C)
Fig. 1. Model alloys project; summary of results (DBTT is the ductile-to-brittle transition
temperature).
26 ISSN 0556-171X. npoôëeMbi npounocmu, 2004, № 1
Radiation Embrittlement Understanding
Another example of results is the understanding of the embrittlement kinetics
in high-nickel commercial steels by the evaluation of WWER-1000 surveillance
data and other relevant research data. The role of nickel for a broad fluence range
is clear and plays a major role in the embrittlement, see Fig. 2.
W E R RPV embrittlement - effect of Nickel at 1.2 and 1.7 wt%
trends from Surveillance, Tacis & other programmes data
О ТАС-3
О ТАС-4
•
SS SU-1 R-3
- - - „ Ni—1.7 wt%
□
ED-3
□
ТАС-2
■ SS NIV-5 Z2
0 0 Ф ^ Ni=1.2 wt%
CF=20
Fig. 2. Effect of nickel in high-Ni materials with low manganese.
In addition, the role of manganese in different WWER-1000 welds is
targeted for additional irradiation embrittlement. Welds with the Mn content in
excess of ~ 0.9 wt.%, in combination with Ni, exhibit an increased sensitivity to
embrittlement, see Fig. 3.
Fluence, 1018 n • cm“2 (E > 0.5 MeV)
Fig. 3. The role of Mn in the embrittlement of high-Ni welds (WWER-1000 surveillance data).
ISSN 0556-171X. Проблемы прочности, 2004, N2 1 27
L. Debarberis, F. Sevini, B. Acosta, et al.
Recently, new data, both from destructive and non-destructive tests, have
been obtained as well as important preliminary results. These are, for example,
positron annihilation data on some selected irradiated alloys; high fluence
irradiation data on model alloys, WWER-1000 reference steel data, analysis of
samples irradiation under stress, etc. The analysis is ongoing and final results will
be reported in the nearest future. These studies cover a wide range of issues
related to radiation embrittlement, including the role of chemical composition (P,
Cu, Ni, Mn) of steels and welds, the effect of irradiation dose and dose rate,
irradiation temperature, annealing and re-embrittlement of pressure vessels of
both western and Russian design. They are carried out within the framework of
the SAFELIFE Action of JRC of the 6th Framework Program.
Conclusions. In FP6, the JRC-IE has launched the SAFELIFE Action on
PLIM, which integrates the efforts done in the past and the competencies of
various European Networks (AMES, NESC, ENIQ, NET, AMALIA and SENUF)
complemented by the information and competence developed within the TACIS
programs.
With SAFELIFE, the JRC plays a key role in the investigation of the
problems of plant life management such as irradiation embrittlement, material
degradation assessment and monitoring, surveillance, structural integrity, fracture
mechanics studies, qualification of in-service inspection methodologies for crack
detection and risk aspects.
Important results have already been obtained and additional results will
become available from the large number of projects still carried out at present.
Р е з ю м е
У рамках програми PLIM досліджено радіаційне окрнхчування і механізми
старіння конструкційних сталей та реакторів із метою оцінки, прогнозуван
ня і моніторинга ресурсу відповідальних вузлів АЕС. Підсумовуються ре
зультати проекту SAFELIFE, що об’єднує різні підходи щодо контролю
ресурсом АЕС. Представлено результати радіаційного окрихчування мо
дельних сплавів, проаналізовано дані випробувань із використанням зразків-
свідків, а також досліджується надійність корпусних та інших типів сталей.
Запропоновано перспективи розвитку руйнівних і неруйнівних методів раді
аційного окрихчення матеріалів.
1. F. Sevini, L. Debarberis, and M. Davies, “The European Network AMES,”
in: Proc. 6th Int. Conf. on Materials Issues in Design, Manufacturing, and
Operation o f NPP Equipment, St. Petersburg, Russia (2000).
2. A. K ryukov and L. D ebarberis, “A chievem ents, open issues and
developments on WWER RPV irradiation embrittlement assessment and
AMES European Network strategy,” in: IAEA Specialist Meeting on
Irradiation Embrittlement, Madrid, PLIM+PLEX (1999).
3. L. Debarberis, F. Sevini, B. Acosta, et al., “Results of embrittlement studies
on model alloys, reference steels, and RPV materials at JRC-IAM,” in: Proc.
7th Int. Conf. on Materials Issues in Design, Manufacturing, and Operation
o f NPP Equipment, St. Petersburg, Russia (2002).
28 ISSN 0556-171X. Проблеми прочности, 2004, № 1
Radiation Embrittlement Understanding
4. L. Debarberis, “The effect of nickel, phosphorus, and copper in irradiation
embrittlement of RPV steel model alloys,” in: NATO Int. Workshop on RPV
Embrittlement, Varna, Bulgaria (2000).
5. L. Debarberis, N. Taylor, A. Eriksson, et al., “An integrated view on plant
life management; EC-JRC-IE projects and programs,” in: Proc. IAEA PLIM
Int. Conf. (Nov. 2002), Budapest (2002).
Received 26. 05. 2003
ISSN 0556-171X. npo6neMU npouHocmu, 2004, № 1 29
|
| id | nasplib_isofts_kiev_ua-123456789-47057 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 0556-171X |
| language | English |
| last_indexed | 2025-12-07T16:06:50Z |
| publishDate | 2004 |
| publisher | Інститут проблем міцності ім. Г.С. Писаренко НАН України |
| record_format | dspace |
| spelling | Debarberis, L. Sevini, F. Acosta, B. Pirfo, S. Bieth, M. Weisshaeupl, H. Törrönen, K. Kryukov, A. Valo, M. 2013-07-09T13:20:58Z 2013-07-09T13:20:58Z 2004 Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE / L. Debarberis, F. Sevini, B. Acosta, S. Pirfo, M. Bieth, H. Weisshaeupl, K. Törrönen, A. Kryukov, M. Valo // Проблемы прочности. — 2004. — № 1. — С. 23-29. — Бібліогр.: 5 назв. — англ. 0556-171X https://nasplib.isofts.kiev.ua/handle/123456789/47057 539.4 Radiation embrittlement and aging mechanisms for NPP reactor pressure vessels and vessel internals have been studied within NPP Plant Life Management (PLIM) for evaluation, prediction, and monitoring of the critical components’ service life. The main achievements of the SAFELIFE project, integrating various networks on PLIM issues, are given. Results of neutron embrittlement of model alloys are presented, and surveillance and research data on WWER reactor pressure vessel and other steels have been analyzed. Projects for the development of destructive and non-destructive testing of irradiated materials have been outlined. В рамках программы PLIM исследовано радиационное охрупчивание и механизмы старения конструкционных сталей внутрикорпусных устройств реакторов с целью оценки, прогнозирования и мониторинга ресурса ответственных узлов АЭС. Изложены результаты проекта SAFELIFE, объединяющего различные подходы к контролю ресурсом АЭС. Представлены результаты радиационного охрупчивания модельных сплавов, проанализированы данные испытаний с использованием образцов-свидетелей, а также исследована надежность корпусных и других типов сталей. Предложены перспективы развития разрушающих и неразрушающих методов радиационного охрупчивания материалов. У рамках програми PLIM досліджено радіаційне окрнхчування і механізми старіння конструкційних сталей та реакторів із метою оцінки, прогнозування і моніторинга ресурсу відповідальних вузлів АЕС. Підсумовуються результати проекту SAFELIFE, що об’єднує різні підходи щодо контролю ресурсом АЕС. Представлено результати радіаційного окрихчування модельних сплавів, проаналізовано дані випробувань із використанням зразків- свідків, а також досліджується надійність корпусних та інших типів сталей. Запропоновано перспективи розвитку руйнівних і неруйнівних методів радіаційного окрихчення матеріалів. en Інститут проблем міцності ім. Г.С. Писаренко НАН України Проблемы прочности Научно-технический раздел Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE Радиационное охрупчивание корпусных сталей в рамках программы управления ресурсом АЭС Article published earlier |
| spellingShingle | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE Debarberis, L. Sevini, F. Acosta, B. Pirfo, S. Bieth, M. Weisshaeupl, H. Törrönen, K. Kryukov, A. Valo, M. Научно-технический раздел |
| title | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE |
| title_alt | Радиационное охрупчивание корпусных сталей в рамках программы управления ресурсом АЭС |
| title_full | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE |
| title_fullStr | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE |
| title_full_unstemmed | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE |
| title_short | Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE |
| title_sort | radiation embrittlement understanding for plim activities at ec-jrc-ie |
| topic | Научно-технический раздел |
| topic_facet | Научно-технический раздел |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/47057 |
| work_keys_str_mv | AT debarberisl radiationembrittlementunderstandingforplimactivitiesatecjrcie AT sevinif radiationembrittlementunderstandingforplimactivitiesatecjrcie AT acostab radiationembrittlementunderstandingforplimactivitiesatecjrcie AT pirfos radiationembrittlementunderstandingforplimactivitiesatecjrcie AT biethm radiationembrittlementunderstandingforplimactivitiesatecjrcie AT weisshaeuplh radiationembrittlementunderstandingforplimactivitiesatecjrcie AT torronenk radiationembrittlementunderstandingforplimactivitiesatecjrcie AT kryukova radiationembrittlementunderstandingforplimactivitiesatecjrcie AT valom radiationembrittlementunderstandingforplimactivitiesatecjrcie AT debarberisl radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT sevinif radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT acostab radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT pirfos radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT biethm radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT weisshaeuplh radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT torronenk radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT kryukova radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés AT valom radiacionnoeohrupčivaniekorpusnyhstaleivramkahprogrammyupravleniâresursomaés |