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1.9.1 Projects

AMES-NDT, Ageing Material Evaluation and Studies by Non-Destructive Techniques, EAEC-NFS 2, 9/1/1998 to 12/31/1999.

ATHENA, Ames Thematic Network on Ageing, FP5-EAECTP C, 11/1/2001 to 10/31/2004. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/58449_en.html.

COBRA, Consolidation of Scientific Technological Expertise to Assess the Reliability of Reactor Pressure Vessel Embrittlement Prediction in Particular for the Arctic Area Plant, FP5-INCO 2, 8/1/2000 TO 7/31/2003. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/53139_en.html.

FRAME, Fracture Mechanics Based Embrittlement Modelling, FP5-EAECTP C, 01-09-00 to 31-05-04. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/52863_en.html.

GETMAT, GEn IV and Transmutation MATerials, FP7-EURATOM-FISSION, 01-02-2008 to 31-10-2013. Retrieved 6 September, 2016 from http://cordis.europa.eu/project/rcn/85745_en.html.

GRETE, Evaluation of Non Destructive Testing Techniques for Monitoring of Material Degradation, FP5-EAECTP C, 01-10-00 to 30-09-03. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/52454_en.html.

HELIMNET, Heavy Liquid Metal Network, FP7-EURATOM-FISSION, 20-01-2010 to 19-01-2012. Retrieved 6 September, 2016 from http://cordis.europa.eu/project/rcn/94437_en.html.

ITEM, Improvement of Techniques for Multiscale Modelling of Irradiated Materials, FP5-EAECTP C, 01-11-01 to 31-10-05. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/58528_en.html.

LEADER, Lead-cooled European Advanced Demonstration Reactor, FP7-EURATOM-FISSION, 02-04-2010 to 01-10-2013. Retrieved 6 September, 2016 from http://cordis.europa.eu/project/rcn/96603_en.html.

LONGLIFE, Treatment of Long Term Irradiation Embrittlement Effects in RPV Safety Assessment, FP7-EURATOM-FISSION, 01-02-10 to 31-01-14. Retrieved 18 August, 2016 from http://cordis.europa.eu/project/rcn/94662_en.html.

MADAM, Conversion Table of Material Damage Indexation for All Different European Reactor Types, EAEC-NFS 2, 01-02-97 to 31-07-98.

MATTER, MATerials Testing and Rules, FP7-EURATOM-FISSION, 01-01-2011 to 31-12-2014. Retrieved 6 September, 2016 from http://cordis.europa.eu/project/rcn/97428_en.html.

NULIFE, Nuclear Plant Life Prediction, FP6-EURATOM-NUCTECH, 01-10-06 to 30-06-12. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/80046_en.html.

PERFECT, Prediction of Irradiation Damage Effects on Reactor Components, FP6-EURATOM-NUCTECH, 01-01-04 to 31-12-07. Retrieved 18 August, 2016 from http://cordis.europa.eu/project/rcn/74106_en.html.

PERFORM60, Prediction of the Effects of Radiation for Reactor Pressure Vessel and In-Core Materials Using Multi-Scale Modelling - 60 Years Foreseen Plant Lifetime, FP7-EURATOM-FISSION, 01-03-09 to 31-12-13. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/89385_en.html.

PISA, Phosphorus Influence on Steel Ageing, FP5-EAECTP C, 01-12-00 to 31-08-04. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/53036_en.html.

PRIS, Properties of Irradiated Stainless Steels for Predicting Lifetime of Nuclear Power Plant Components, FP5-EAECTP C, 01-10-00 to 30-06-04. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/52453_en.html.

REDOS, Reactor Dosimetry: Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Reactors Pressure Vessel Monitoring, FP5-EAECTP C, 01-11-01 to 31-10-04. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/58439_en.html.

REFEREE, Relation Between Different Measures of Exposure - Induced Shifts in Ductile-Brittle Transition Temperatures, EAEC-NFS 2, 01-01-96 to 30-09-99. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/30764_en.html.

RESQUE, Reconstitution Techniques Qualification & Evaluation to Study Ageing Phenomena of Nuclear Pressure Vessel Materials, EAEC-NFS 2, 01-02-97 to 31-07-99. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/35554_en.html.

VERLIFE, Unified Procedure for Lifetime Assessment of Components and Piping in VVER NPPs, FP5-EAECTP C, 01-10-01 to 30-09-03. Retrieved 18 August, 2016 from http://cordis.europa.eu/project/rcn/58143_en.html.

1.9.2 Reports

Acosta2001, B. Acosta, L. Debarberis and J.M. Perlado, Development and Evaluation of Thermoelectric Power Measurements as a Non Destructive Technique to Evaluate Ageing of Reactor Pressure Vessel Steels, 2001. Retrieved 10 October, 2018 from https://inis.iaea.org/search/search.aspx?orig_q=RN:33015214.

AMES-NDT2000, L. Debarberis, B. Acosta, J. Bros, J.F. Coste, G. Dobmann, F. Perosanz, M. Horsten, M. Hutchings, C. Scruby, A. Rogerson, D. Kalkhof, P. Kauppinen, D. Stegemann, G. Weimann, G. Keinhorst, H. Bischoff and P. Lemaitre, Ageing Material Evaluation and Studies by Non-destructive Techniques (AMES-NDT) - FINAL REPORT, 2000. Retrieved 10 October, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/eur19675en.pdf.

Ballesteros2004, A. Ballesteros, B. Böhmer, B. Ošmera, A. Keresztúri, K. Ilieva, B. Acosta, V. Smutný, E. Polke, S. Zaritsky and P. Ortego, Reactor Dosimetry: Accurate Determination and Benchmarking of Radiaton Field Parameter, Relevant for Pressure Vessel Monitoring (REDOS), Final Report, Short Version, 2004. Retrieved 10 October, 2018 from http://cordis.europa.eu/documents/documentlibrary/78683851EN6.pdf.

Ballesteros2014, A. Ballesteros, Surveillance Guidelines for Life Extension, 2014. Retrieved 18 August, 2016 from http://projects.tecnatom.es/webaccess/LONGLIFE/index.php?option=com_docman&task=doc_download&gid=804&Itemid=19.

Brumovsky2014, M. Brumovský, Guidelines for Integrity and Lifetime Assessment of Components and Piping in WWER NPPs during Operation (VERLIFE), 2014. Retrieved 18 August, 2016 from http://doi.org/10.1016/j.proeng.2014.11.043.

Brumovsky2014b, M. Brumovský and R. Kopriva, Test Results Within LONGLIFE, 2014. Retrieved 12, October 2018 from http://projects.tecnatom.es/webaccess/LONGLIFE/index.php?option=com_docman&task=doc_download&gid=795&Itemid=19.

Debarberis1998, L. Debarberis, B. Acosta, K. Törrönen and A. Ballesteros, Conversion Table of Material Damage Indexation for all Different European Reactor Types - MADAM Final Report, 1998. Retrieved 28 September, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/eur18693ben.pdf.

Dobmann2001, G. Dobmann, L. Debarberis and J.-F. Coste, Aging Material Evaluation and Studies by Non-Destructive Techniques (AMES-NDT) — a European Network Project, 2001. Retrieved 10 October, 2018 from https://doi.org/10.1016/S0029-5493(00)00422-2.

Domain2004, C. Domain, C.S. Becquart and L. Malerba, Simulation of Radiation Damage in Fe Alloys: an Object Kinetic Monte Carlo Approach, 2004. Retrieved 10 October, 2018 from https://doi.org/10.1016/j.jnucmat.2004.07.037.

English2003, C. English, F. Sevini, J-M. Frund, R. Langer, A. Donaldson, F. Gillemot, M. Brumovský, P. Nenonen, A. Ballesteros, S. Schmauder and D. Bacon, Phosphorus Influence on Steel Ageing (PISA) - FISA Contribution, 2003. Retrieved 12 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/fisa2003_2-2_pisa_en.pdf.

EUR19961, P. Manolatos and G. van Goethem (eds), EU Co-Sponsored Research on Structural Materials Ageing - Final Summary Reports: 'AGE' Cluster Projects, 2002. Retrieved 10 October, 2018 from http://bookshop.europa.eu/en/eu-co-sponsored-research-on-structural-materials-ageing-pbKINA19961.

EUR21771, A. Ballesteros, X. Jardí, B. Böhmer, J. Konheiser, B. Ošmera, J. Kyncl, A. Keresztúri, G. Hordosy, K. Ilieva, S. Belousov, D. Kirilova, M. Mitev, B. Petrov, B. Acosta, V. Smutný, E. Polke, S. Zaritsky, C. Töre and P. Ortego, Reactor Dosimetry: Accurate Determination and Benchmarking of Radiaton Field Parameter, Relevant for Pressure Vessel Monitoring (REDOS), Final Report, 2005. Retrieved 10 October, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/redoseur_21771en-ames17.pdf.

EUR22282, M. Delnondedieu, H. Hegeman, P. Kauppinen, J. Bros, G. Dobmann, B. Acosta, A. Rogerson, F. Perosanz, P.A. Hahn, F. Gillemot, T. Komber, M. Niffenenger, J. Novak, R. Oettel and R. Zimmer, GRETE: Evaluation of Non-Destructive Techniques for Monitoring Material Degradation - "GRETE" Final Report, 2006. Retrieved 9 October, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/report_no._18_grete_evaluation_of_non-destructive_techniques_for_monitoring_material_degradation.pdf.

EUR23207, AMES Thematic Network on Ageing (ATHENA) - Final Report, 2005. Retrieved 12 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/athena_projrep_en.pdf.

EUR23742, C. Domain, Improvement of Techniques for Multiscale Modelling of Irradiated Materials (ITEM) - Final Report, 2009. Retrieved 10 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/item-final-report_en.pdf.

EUR24455, J.-P. Massoud, S. Bugat, D. Lidbury, B. Marini and S. Van Dyck, PERFECT - Final Activity Report, 2008. Retrieved 10 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp6-euratom/docs/perfect-final-report.pdf.

Gerard2003, R. Gerard, A. Ballesteros, K. Wallin, L. Debarberis, M. Brumovský, C. Bolton and F. Sevini, AMES Thematic Network on Ageing (ATHENA) - FISA Contribution, 2003. Retrieved 12 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/fisa2003_2-2_athena_en.pdf.

GRETE2004, Evaluation of Non-Destructive Techniques for Monitoring Material Degradation (GRETE) - Final Synthesis Report, 2004. Retrieved 11 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/grete_projrep_en.pdf.

Horvath2005, M. Horvath, L. Tatar and F. Gillemot, Phosphorus Influence on Steel Ageing - PISA, KFKI AEKI final report, 2005.

Jardin2006, M. Jardin, M. Lambrecht, A. Rempel, Y. Nagai, E. van Walle and A. Almazouzi, Digital Positron Lifetime Spectrometer for Measurements of Radioactive Materials, 2006. Retrieved 10 October, 2018 from https://doi.org/10.1016/j.nima.2006.08.087.

JRC24564, L. Debarberis, F. Sevini, B. Acosta, A. Kryukov, Y. Nikolaev, A.D. Amaev and M. Valo, Irradiation Embrittlement of Model Alloys and Commercial Steels: Analysis of Similitude Behaviors, 2002. Retrieved 10 October, 2018 from https://doi.org/10.1016/S0308-0161(02)00066-2.

JRC26177, B. Acosta, L. Debarberis, F. Sevini and A. Kryukov, Cu Effects on Radiation Embrittlement of Ni-Containing Complex Model Alloys and the Related Potentials of the Thermoelectric Method, 2004. Retrieved 11 October, 2018 from https://doi.org/10.1016/j.ndteint.2003.10.010.

JRC26623, R. Ahlstrand, M. Bièth and C. Rieg, Neutron Embrittlement of VVER Reactor Pressure Vessels—Recent Results, Open Issues and New Developments, 2004. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.nucengdes.2003.12.003.

JRC28685, L. Debarberis, A. Kryukov, F. Gillemot, M. Valo, A. Morozov, M. Brumovský, B. Acosta and F. Sevini, Use of a Semi-Mechanistic Analytical Model to Analyze Radiation Embrittlement of Model Alloys: Cu and P Effects, 2004. Retrieved 12 October, 2018 from https://doi.org/10.1023/B%3ASTOM.0000035760.22894.75.

JRC30141, V. Slugen, A. Zeman, M. Petriska and V. Kršjak, Positron Study of Radiation Embrittlement of Steels Used in Water Cooled, Water Moderated Energy Rreactors, 2006. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.apsusc.2005.08.076.

JRC30340, L. Debarberis, B. Acosta, F. Sevini, A. Chernobaeva and A.M. Kryukov, Fluence Rate Effect Semi-Mechanistic Modelling on WWER-Type RPV Welds, 2006. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2005.11.017.

JRC30537, L. Debarberis, A. Kryukov, F. Gillemot, B. Acosta and F. Sevini, Semi-mechanistic analytical model for radiation embrittlement and re-embrittlement data analysis, 2005. Retrieved 18 August, 2016 from http://doi.org/10.1016/j.ijpvp.2004.09.002.

JRC30546, L. Debarberis, B. Acosta, F. Sevini, A. Kryukov, F. Gillemot, M. Valo, A. Nikolaev and M. Brumovský, Role of Nickel in a Semi-Mechanistic Analytical Model for Radiation Embrittlement of Model Alloys, 2005. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2004.10.002.

JRC30550, L. Debarberis, F. Sevini, B. Acosta, A. Kryukov and D. Erak, Fluence Rate Effects on Irradiation Embrittlement of Model Alloys, 2005. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.ijpvp.2004.10.002.

JRC30552, B. Acosta, F. Sevini and L. Debarberis, A Preliminary Evaluation of Irradiation Damage in Model Alloys by Electric Properties Based Techniques, 2005. Retrieved 10 October, 2018 from https://doi.org/10.1016/j.ijpvp.2004.01.005.

JRC30613, B. Acosta, L. Debarberis, S. Pirfo, F. Sevini, A. Kryukov, A. Chernobaeva, F. Gillemot and M. Brumovský, WWER-1000 Base Metal Reference Steel and its Characterisation, 2005. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.nucengdes.2005.05.023.

JRC30648, L. Debarberis, B. Acosta, A. Zeman, F. Sevini, A. Ballesteros, A. Kryukov, F. Gillemot and M. Brumovský, Analysis of WWER-440 and PWR RPV Welds Surveillance Data to Compare Irradiation Damage Evolution, 2006. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2006.01.003.

JRC30867, F. Sevini, B. Acosta and L. Debarberis, Combined Thermo-Electric Power and Resistivity Measurements of Embrittlement Recovery in Aged JRQ Ferritic Steels, 2006. Retrieved 11 October, 2018 from https://doi.org/10.1016/j.ijpvp.2006.03.006.

JRC31142, A. Ballesteros, J. Bros, L. Debarberis, F. Sevini, D. Erak, S. Gezashchenko, A. Kryukov, Y. Shtrombakh, S. Goloschapov, Ionov, Y. Pytkin, Y. Anikeev, G. Banyuk, A. Plusch, F. Gillemot, L. Tatar and V. Petrosyan, Consolidation of Scientific and Technological Expertise to Assess the Reliability of Reactor Pressure Vessel Embrittlement Prediction in Particular for the Arctic Area Plant (COBRA), 2005. Retrieved 10 October, 2018 from https://doi.org/10.1016/j.nucengdes.2004.08.062.

JRC31151, L. Debarberis, B. Acosta, A. Zeman, F. Sevini, A. Ballesteros, A. Kryukov, F. Gillemot and M. Brumovský, Effect of Irradiation Temperature in PWR RPV Materials and its Inclusion in Semi-Mechanistic Model, 2005. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.scriptamat.2005.05.026.

JRC31980, C. Györi, Z. Hozer, E. Perez-Feró, P. Van Uffelen, A. Schubert and J. Van De Laar, Applying the TRANSURANUS Code to VVER Fuel Under Accident Conditions, 2007. Retrieved 12 October, 2018 from http://publications.jrc.ec.europa.eu/repository/handle/JRC31980.

JRC32254, M. Valo, K. Wallin, E. Lucon, M. Kytka, M. Brumovský, B. Acosta, L. Debarberis, J. Kohopää, F. Gillemot and M. Horvath, The Euratom 5th Framework Programme Project FRAME (Fracture Mechanics Based Embrittlement); Description of the Project and First Results, 2005. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.nucengdes.2004.08.059.

JRC33283, L. Debarberis and H. Hein, Evidence of Chromium Stabilisation of Irradiation Damage in RPV Weld Metals, 2006. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.ijpvp.2006.05.002.

JRC34527, F. Gillemot, M. Horváth, G. Úri, T. Fekete, E. Houndeffo, B. Acosta, L. Debarberis and H.-W. Viehrig, Radiation stability of WWER RPV cladding materials, 2007. Retrieved 18 August, 2016 from http://doi.org/10.1016/j.ijpvp.2007.04.004.

JRC46534, M. Brumovský, R. Ahlstrand, J. Brynda, L. Debarberis, J. Kohopaa, A. Kryukov and W. Server, Annealing and re-embrittlement of reactor pressure vessel materials, State of the art report ATHENA WP-4, AMES Report N. 19, 2008. Retrieved 18 August, 2016 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/eur23449_-_ames_19_-_anneal-2008.pdf.

JRC46587, C.A. English, S.R. Ortner, F. Gillemot, A. Donaldson, P. Kizler, P. Binkele, M. Brumovský, R. Langer, P. Nenonen, A. Ballesteros, F. Sevini, D. Bacon, S. Saillet, M. Horvath and M. Kytka, Phosphorus Influence on Steels Ageing (PISA) - Analysis of data from work-packages 2, 4, 5, 6, 7 and 8, AMES Report N. 20, 2005. Retrieved 12 October, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/eur23450_-_ames_20-pisa-2008.pdf.

JRC63603, A. Ballesteros, R. Ahlstrand, C. Bruynooghe, A. Chernobaeva, Y. Kevorkyan, D. Erak and D. Zurko, Irradiation temperature, flux and spectrum effects, 2011. Retrieved 28 September, 2018 from https://doi.org/10.1016/j.pnucene.2011.05.022.

JRC66610, A. Kryukov, L. Debarberis, U. von Estorff, F. Gillemot and F. Oszvald, Irradiation Embrittlement of Reactor Pressure Vessel Steel at Very High Neutron Fluence, 2012. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2011.12.026.

JRC86552, A. Kryukov, D. Blagoeva and L. Debarberis, Flux Effect Analysis in WWER-440 Reactor Pressure Vessel Steels, 2013. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2013.07.011.

Jumel2005, S. Jumel and J.C. Van-Duysen, RPV-1: A Virtual Test Reactor to Simulate Irradiation Effects in Light Water Pressure Vessel Steels, 2005. Retrieved 10 October, 2018 from https://doi.org/10.1016/j.jnucmat.2004.10.131.

Keim2012, E. Keim and D. Lidbury, Review of Assessment Methods Used in Nuclear Plant Life Management - NULIFE Final Report of Expert Groups 2 and 3, 2012. Retrieved 28 September, 2018 from http://www.vtt.fi/proj/nulife/nulife_d1_d2_report_master_11may2012.pdf.

Lambrecht2008, M. Lambrecht, L. Malerba and A. Almazouzi, Influence of Different Chemical Elements on Irradiation-Induced Hardening Embrittlement of RPV Steels, 2008. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2008.06.030.

Malerba2014, L. Malerba, Advances in Modelling Nanostructural Evolution in Iron Alloys: What Do Models Tell About Late Blooming Phases ?, 2014. Retrieved 10 October, 2018 from http://projects.tecnatom.es/webaccess/LONGLIFE/index.php?option=com_docman&task=doc_download&gid=790&Itemid=19.

Ortner2014, S. Ortner, B. Radiguet, S. Cammelli, P. Pareige, F. Bergner, A. Ulbricht, A. Wagner, E. Meslin, M. Hernández-Mayoral, M. Serrano, J.J.H. Lim, C. Grovenor, K. Wilford, F. Gillemot and J. Kocik, Summary Of Microstructural Examinations Within LONGLIFE, 2014. Retrieved 10 October, 2018 from http://projects.tecnatom.es/webaccess/LONGLIFE/index.php?option=com_docman&task=doc_download&gid=793&Itemid=19.

PERFORM2013, PERFORM 60 Report Summary, 2013. Retrieved 10 October, 2018 from http://cordis.europa.eu/result/rcn/57044_en.html.

PISA2005, Phosphorus Influence on Steels Ageing (PISA) - Final Technical Report, 2005. Retrieved 11 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/pisa_projrep_en.pdf.

PRIS2004, P. Ould, P. Scott, J. Lapena, U. Ehrnsten, M. Ludwig, S. van Dyck, A. Jenssen and H. Westermark, Properties of Irradiated Stainless Steels for Predicting Lifetime of Nuclear Power Plant Components (PRIS) - Final Report (Summary), 2004. Retrieved 28 September, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/pris_projrep_en.pdf.

Souidi2006, A. Souidi, C.S. Becquart, C. Domain, D. Terentyev, L. Malerba, A.F. Clader, D.J. Bacon, R.E. Stoller, Yu. N. Osetsky and M. Hou, Dependence of Radiation Damage Accumulation in Iron on Underlying Models of Displacement Cascades and Subsequent Defect Migration, 2006. Retrieved 11 October, 2018 from https://doi.org/10.1016/j.jnucmat.2006.04.009.

Ulbricht2006, A. Ulbricht, F. Bergner, C.D. Dewhurst and A. Heinemann, Small-angle Neutron Scattering Study of Post-Irradiation Annealed Neutron Irradiated Pressure Vessel Steels, 2006. Retrieved 18 August, 2016 from http://doi.org/10.1016/j.jnucmat.2006.02.083.

Valo2007a, M. Valo, E. Lucon, M. Brumovsky, B. Acosta, L. Debarberis, J. Kohopää, F. Gillemot, M. Horwath and U. Ehrnstén, Fracture Mechanics Based Embrittlement Modelling (FRAME) - Final Technical Report, 2007.

Valo2007b, M. Valo, E. Lucon, M. Brumovský, B. Acosta, L. Debarberis, J. Kohopää, F. Gillemot, M. Horwath and U. Ehrnstén, Fracture Mechanics Based Embrittlement Modelling (FRAME) - Final Technical Report, 2007. Retrieved 12 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/frame_projrep_en.pdf.

VERLIFE2003, M. Brumovský (ed.), Unified Procedure for Lifetime Assessment of Components and Piping in WWER Nuclear Power Plants (VERLIFE) - Final Report, 2003. Retrieved 18 August, 2016 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/verlife_projrep_en.pdf.

Verheyen2006, K. Verheyen, M. Jardin and A. Almazouzi, Coincidence Doppler Broadening Spectroscopy in Fe, Fe-C and Fe-Cu After Neutron Irradiation, 2006. Retrieved 12 October, 2018 from https://doi.org/10.1016/j.jnucmat.2006.02.011.

Walle2001, E. van Walle, M. Scibetta, M.J. Valo, H.-W. Viehrig, H. Richter, T. Atkins, M.R. Wootton, E. Keim, L. Debarberis and M. Horsten, Reconstitution Techniques Qualification and Evaluation to Study Ageing Phenomena of Nuclear Pressure Vessel Materials (RESQUE), 2001. Retrieved 11 October, 2018 from https://doi.org/10.1016/S0029-5493(01)00389-2.

1.9.3 External Resources

10CFR50G, Appendix G to Code of Federal Regulations, Part 50, “Fracture Toughness Requirements”. Retrieved 12 October, 2018 from http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-appg.html.

10CFR50H, Appendix H to Code of Federal Regulations, Part 50, “Reactor Vessel Material Surveillance Program Requirements”. Retrieved 12 October, 2018 from http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-apph.html.

IAEA05a, Assessment and management of ageing of major nuclear power plant components important to safety: BWR Pressure Vessels. IAEA-TECDOC-1470, Vienna, IAEA, 2005. Retrieved 28 September, 2018 from http://www-pub.iaea.org/books/IAEABooks/7296/Assessment-and-Management-of-Ageing-of-Major-Nuclear-Power-Plant-Components-Important-to-Safety-BWR-Pressure-Vessels.

IAEA05b, Assessment and management of ageing of major nuclear power plant components important to safety: BWR Pressure Vessel Internals. IAEA-TECDOC-1471, Vienna, IAEA, 2005. Retrieved 28 September, 2018 from http://www-pub.iaea.org/books/IAEABooks/7297/Assessment-and-Management-of-Ageing-of-Major-Nuclear-Power-Plant-Components-Important-to-Safety-BWR-Pressure-Vessel-Internals.

IAEA07a, Assessment and management of ageing of major nuclear power plant components important to safety: PWR Pressure Vessels. IAEA-TECDOC-1556. Vienna, IAEA, 2007. Retrieved 28 September, 2018 from http://www-pub.iaea.org/books/IAEABooks/7735/Assessment-and-Management-of-Ageing-of-Major-Nuclear-Power-Plant-Components-Important-to-Safety-PWR-Pressure-Vessels-2007-Update.

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