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4.9.1 Projects

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, 01-03-2009 to 31-12-2013. Retrieved 10 October, 2018 from http://cordis.europa.eu/project/rcn/89385_en.html.

STYLE, Structural Integrity for Lifetime Management – Non-RPV Components, FP7-EURATOM-FISSION, 01-01-2010 to 31-12-2013. Retrieved 6 December, 2018 from https://cordis.europa.eu/project/rcn/94435_en.html.

4.9.2 Reports

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 9 October, 2018 from http://capture.jrc.ec.europa.eu/sites/capture/files/files/documents/eur19675en.pdf.

Bosch2008, R.W. Bosch, G. Nagy, D. Feron, M. Navas, W. Bogaerts, D. Kárník, T. Dorsch, A. Molander and T. Saario, Development of Light Water Reactor Reference Electrodes (LIRES) - Final Report (Summary), 2008. Retrieved 9 October, 2018 from https://cordis.europa.eu/pub/fp5-euratom/docs/projrep_lires_en.pdf.

Bugat2006, S. Bugat, SIRENA (Final Report), 2006. Retrieved 9 October, 2018 from http://cordis.europa.eu/docs/publications/1039/103938461-6_en.pdf.

Cameron2004, N.B. Cameron and W. Daniels, Signal Processing and Improved Qualification for Non-Destructive Testing of Ageing Reactors (SPIQNAR) - Final Report (Summary), 2004. Retrieved 9 October, 2018 from https://cordis.europa.eu/pub/fp5-euratom/docs/spiqnar_projrep_en.pdf.

CASTOC2004, J. Föhl, T. Weissenberg, D. Gómez-Briceño, J. Lapeña, M. Ernestová, M. Žamboch, H.-P. Seifert, S. Ritter, A. Roth, B. Devrient and U. Ehrnstén, 2004. Retrieved 9 October, 2018 from http://cordis.europa.eu/pub/fp5-euratom/docs/castoc_projrep_en.pdf.

Dobmann2001, G. Dobmann, L. Debarberis and J.-F. Coste, Ageing Material Evaluation and Studies by Non-Destructive Techniques (AMES-NDT) — A European Network Project, 2001. Retrieved 9 October, 2018 from https://doi.org/10.1016/S0029-5493(00)00422-2.

EUR19961, P. Manolatos and G. van Goethem (eds.), EU Co-Sponsored Research on Structural Materials Ageing - Final Summary Reports: 'AGE' Cluster Projects, 2002. Retrieved 9 October, 2018 from http://bookshop.europa.eu/en/eu-co-sponsored-research-on-structural-materials-ageing-pbKINA19961.

EUR22469, R. Miteva and N.G. Taylor, General Review of Dissimilar Metal Welds in Piping Systems of Pressurised Water Reactors, Including WWER Designs, 2006. Retrieved 9 October, 2018 from http://bookshop.europa.eu/en/general-review-of-dissimilar-metal-welds-in-piping-systems-of-pressurised-water-reactors-including-wwer-designs-pbLDNA22469/downloads/LD-NA-22469-EN-N/LDNA22469ENN_002.pdf;pgid=GSPefJMEtXBSR0dT6jbGakZD0000pORmO9mf;sid=oh4kqIY6n30kotHMnHu6D-Qfpc0ieyT53k4=?FileName=LDNA22469ENN_002.pdf&SKU=LDNA22469ENN_PDF&CatalogueNumber=LD-NA-22469-EN-N.

EUR22510, N. Taylor, C. Faidy and P. Gilles, Assessment of Dissimilar Weld Integrity: Final Report of the NESC-III Project, 2006. Retrieved 9 October, 2018 from http://bookshop.europa.eu/en/general-review-of-dissimilar-metal-welds-in-piping-systems-of-pressurised-water-reactors-including-wwer-designs-pbLDNA22469/downloads/LD-NA-22469-EN-N/LDNA22469ENN_002.pdf;pgid=GSPefJMEtXBSR0dT6jbGakZD0000pORmO9mf;sid=oh4kqIY6n30kotHMnHu6D-Qfpc0ieyT53k4=?FileName=LDNA22469ENN_002.pdf&SKU=LDNA22469ENN_PDF&CatalogueNumber=LD-NA-22469-EN-N.

Faidy2001, C. Faidy, BIMET - Final Report, 2001.

JRC33994, J.-J. Janosch, M. Huther, N. Taylor, S. Maddox and M. Koçak, Proceedings of the 24th International Conference on Offshore Mechanics and Arctic Engineering, 2005. Retrieved 9 October, 2018 from http://proceedings.asmedigitalcollection.asme.org/proceeding.aspx?articleid=1575749.

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 9 October, 2018 from http://www.vtt.fi/proj/nulife/nulife_d1_d2_report_master_11may2012.pdf .

Kocak2006, M. Koçak, FITNET - European Fitness-for-Service Network - Final Technical Report, 2006. Retrieved 9 October, 2018 from http://www.eurofitnet.org/FITNETFinalTechnRepwithProjManagement30Jan07.pdf.

Michel2004, F. Michel et al., Compilation of Current Active or Potential Damage Mechanisms in European Light-Water Reactor Power Plant Components (WP1), 2004.

Schulz2004a, H. Schulz, T. Schimpfke, B. Brickstad, V. Chapman, B. Shepherd, S. Kelly, S. Olsson, J. Wintle, A. Muhammed and K. Simola, Nuclear-Risk-Based Inspection Methodology for Passive Components (NURBIM) - Final Report (Short Version), 2004. Retrieved 9 October, 2018 from https://cordis.europa.eu/pub/fp5-euratom/docs/nurbim_projrep_en.pdf.

Schulz2004b, H. Schulz, T. Schimpfke, B. Brickstad, V. Chapman, B. Shepherd, S. Kelly, S. Olsson, J. Wintle, A. Muhammed and K. Simola, Nuclear-Risk-Based Inspection Methodology for Passive Components (NURBIM) - Final Report, 2004.

Simonovski2012, I. Simonovski and L. Cizelj, Towards Modeling Intergranular Stress Corrosion Cracks on Grain Size Scales, 2012. Retrieved 9 October, 2018 from https://doi.org/10.1016/j.nucengdes.2011.08.032.

Simonovski2013a, I. Simonovski, L. Cizelj, G. Machina and M.I. Uplaznik, Modeling Intergranular Cracking in Polycrystalline Aggregates: Explicit Account for Grain Boundaries With Cohesive Zone Approach, 2013. Retrieved 9 October, 2018 from http://www.iasmirt.org/transactions/22/Pap_677_ver_1.pdf.

Starflinger2010, J. Starflinger, T. Schulenberg, P. Marsault, D. Bittermann, E. Laurien, C. Maraczy, H. Anglart, J.-A. Lycklama, M. Andreani, M. Ruzickova, T. Vanttola, A. Kiss, M. Rohde and R. Novotny, High Performance Light Water Reactor Phase 2 - Public Final Report, 2010.

STYLE2014, Structural Integrity for Lifetime Management – Non-RPV Components (STYLE) - Final Report, 2014. Retrieved 9 October, 2018 from http://cordis.europa.eu/pub/fp7/euratom-fission/docs/style-final-report_en.pdf.

Tice1998, D. R. Tice, J. Atkinson, W. Dietzel, J. Lapeña, S. McAllister, B. Rosborg, D. Swan and A. Toivonen, Evaluation of Techniques for Assessing Corrosion Cracking of Dissimilar Metal Welds (DISWEC) - Final Report (Long Version), 1998.

VERLIFE2003, M. Brumovský (ed.), Unified Procedure for Lifetime Assessment of Components and Piping in WWER Nuclear Power Plants (VERLIFE) - Final Report, 2003. Retrieved 9 October, 2018 from ftp://ftp.cordis.europa.eu/pub/fp5-euratom/docs/verlife_projrep_en.pdf.

4.9.3 External Resources

IAEA00, Iodine Induced Stress Corrosion Cracking of Zircaloy Fuel Cladding Materials, IAEA-TECDOC-1185, 2000. Retrieved 9 October, 2018 from http://www-pub.iaea.org/MTCD/Publications/PDF/te_1185_prn.pdf.

IAEA03, Assessment and Mangement of Ageing of Major Nuclear Power Plant Components Important to Safety: Primary Piping in PWRs, IAEA-TECDOC-1361, 2003. Retrieved 9 October, 2018 from http://www-pub.iaea.org/MTCD/publications/PDF/te_1361_web.pdf.

IAEA05a, Assessment and Mangement of Ageing of Major Nuclear Power Plant Components Important to Safety: BWR Pressure Vessels, IAEA-TECDOC-1470, 2005. Retrieved 9 October, 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.

IDENTIFIER, Assessment and Mangement of Ageing of Major Nuclear Power Plant Components Important to Safety: BWR Pressure Vessel Internals, IAEA-TECDOC-1471, 2005. Retrieved 9 October, 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.

IAEA07, Assessment and Mangement of Ageing of Major Nuclear Power Plant Components Important to Safety: PWR Pressure Vessels, IAEA-TECDOC-1556, 2007. Retrieved 9 October, 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.

IAEA98, Assessment and Mangement of Ageing of Major Nuclear Power Plant Components Important to Safety: CANDU Pressure Tubes, IAEA-TECDOC-1037, 1998. Retrieved 9 October, 2018 from http://www-pub.iaea.org/books/IAEABooks/5334/Assessment-and-Management-of-Ageing-of-Major-Nuclear-Power-Plant-Components-Important-to-Safety-CANDU-Pressure-Tubes.

NUREG-2188, K.J. Karwoski, U.S. Operating Experience with Thermally Treated Alloy 600 Steam Generator Tubes Through December 2013, NUREG-2188, 2016. Retrieved 9 October, 2018 from http://www.nrc.gov/docs/ML1606/ML16061A159.pdf.

NUREG-CR-7187, E.J. Sullivan and M.T. Anderson, Managing PWSCC in Butt Welds by Mitigation and Inspection, NUREG/CR-7187, 2014. Retrieved 9 October, 2018 from http://www.nrc.gov/docs/ML1432/ML14329A085.pdf.

PMMD07, P.L. Andresen, F.P. Ford, K. Gott, R.L. Jones, P.M. Scott, T. Shoji, R.W. Staehle and R.L. Tapping, Expert Panel Report on Proactive Materials Degradation Assessment, NUREG/CR-6923, 2007. Retrieved 9 October, 2018 from http://pmmd.pnl.gov/default.aspx.