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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Veröffentlicht in:Проблемы прочности
Datum:2004
Hauptverfasser: Debarberis, L., Sevini, F., Acosta, B., Pirfo, S., Bieth, M., Weisshaeupl, H., Törrönen, K., Kryukov, A., Valo, M.
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Veröffentlicht: Інститут проблем міцності ім. Г.С. Писаренко НАН України 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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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.
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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
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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
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