Nuclear Materials Science

Organisational unit: Institute

  1. In-proceedings paper › Research › Peer-reviewed
  2. Application of MCNPX 2.7.D for Reactor Core Management at the Research Reactor BR2

    Kalcheva, S. & Koonen, E., 18 May 2011, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011). LaGrange Park, IL, United States

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  3. Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods

    Kalcheva, S., Koonen, E., Olson, A., Matos, J. & Beeckmans de West-Meerbeeck, A., 4 Nov 2009, 2009 International Meeting on Reduced Enrichment for Research and Test Reactors. Illinois, United States

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  4. Application of the Bi-modal Master Curve Procedure to Determine the Fracture Toughness Lower Bound Curve

    Chaouadi, R., Marie, S., Lambrecht, M., Miller, C. & Fichot, P., 16 Sep 2018, Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability: Fontevraud 9 . SFEN - Société française d’énergie nucléaire , 10 p. 000107

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  5. Application of the microinterferometric tomography setup to the reliability tests of the fiber sensors exposed to cumulated gamma radiation

    Berghmans, F., Kniazewski, P., Kujawinska, M., Fernandez Fernandez, A., Goussarov, A., Van Uffelen, M. & D'hondt, P., Jun 2005, Proceedings of SPIE - Nano- and Micro-metrology. United States, p. 42-49

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  6. Approach to Criticality in the BR2 Reactor: MCNPX vs. Point Kinetics Method

    Kalcheva, S., Koonen, E. & Beeckmans de West-Meerbeeck, A., 5 Mar 2008, Proceedings of the 12th Int. Topical Meeting on Research Reactor Fuel Management. Brussels, Belgium

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  7. Artificial intelligence applied to simulation of radiation damage in ferritic alloys

    Domingos, R., Cerchiara, G., Djurabekova, F., Malerba, L. & Ruan, D., Aug 2006, Applied Artificial Intelligence. Singapore, Singapore, Vol. 1. p. 883-890

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  8. Assessment of the French and US embrittlement trend curves applied to RPV materials irradiated in the BR2 materials test reactor

    Chaouadi, R., Gérard, R., Bogaert, A-S. & Scibetta, M., 27 Sep 2010, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs. France, p. 1-11

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  9. ATF: cladding, fuels and structures with lower hydrogen production and increased ability for fission products retention

    Lemehov, S. & SONG, K. W., 4 Mar 2016, OECD NEA NI2050 Experts Meetings. Marc Deffrennes ed.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  10. Atomic scale study of single self interstitial atom diffusivity in bcc Fe-Cr using molecular dynamics simulation

    Terentyev, D., Malerba, L. & Al Mazouzi, A., Jun 2005, Eight International Workshop on Nondestructive Testing and Computer Simulations in Science and Engineering. St. Petersburg, Russian Federation, p. 44-50

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  11. Automatic Whole Core Depletion & Criticality Calculations by MCNPX 2.7.0

    Kalcheva, S. & Koonen, E., 15 May 2012, Physor 2012. LaGrange Park, IL, United States

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  12. Bituminised Waste Re-treatment: Replacement of the Bitumen Matrix by a Glass Matrix

    Impens, N., Tennstedt, I., Lemmens, K., Gielen, B., Van Laer, J., Fonteyne, A., Vos, L., Vos, B., Leenaers, A., Van den Berghe, S., Van Bree, P., Van Oost, G. & Van Iseghem, P., Jun 2006, Scientific Basis for Nuclear Waste Management XXIX. Warrendale, PA, Belgium, Vol. 1. p. 743-750 (MRS Proceedings; no. Volume 932).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  13. Boundary conditions to water removal from defective spent fuel

    Verwerft, M., Cornelis, G., Pakarinen, J., Faber, W., Höfer, H. & Rirschl, C., 22 Sep 2019, Top Fuel 2019. 2019 ed. Seattle: Unknown, p. 94-103 10 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  14. CD’S Burnable Poison for BR2 Fuel Element

    Kalcheva, S., Koonen, E., Franck, N. & Beeckmans de West-Meerbeeck, A., 24 Mar 2009, 13th International Topical Meeting on Research Reactor Fuel Management (RRFM). Brussels, Belgium

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  15. Characterisation of Cr2O3 Doped Fuel

    Cardinaels, T., Govers, K., Vos, B., Van den Berghe, S., Verwerft, M., de Tollenaere, L., Maier, G. & Delafoy, C., Mar 2010, Proceedings of the Enlarged Halden Programme Group Meeting 2010. Halden, Norway

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  16. Characterisation of SCK-CEN fuel samples used for leach tests in FIRST-Nuclides

    Govers, K., Verwerft, M., Van Renterghem, W., Lemmens, K., Mennecart, T., Cachoir, C., Adriaensen, L., Dobney, A. & Gysemans, M., 10 Oct 2012, 1st Annual Workshop Proceedings - 7th EC - FP First-Nuclides. Budapest, Hungary, p. ST61-ST67

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  17. Characterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service

    Van Dyck, S., Al Mazouzi, A., stoenescu, R. & gavillet, D., 16 Jun 2005, Characterisation of stress corrosion cracking and microstructure of a welded light water reactor thermal shield after 25 years of service. Beijing, China, p. 10-21

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  18. Coated particle production in the SELENIUM project

    Van den Berghe, S., Leenaers, A., Detavernier, C. & Sannen, L., Mar 2011, Transactions of the European Research Reactor Fuel Management conference (RRFM-2011). Brussels, Belgium, Vol. 1.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  19. Comparative study of the mechanical properties of different tungsten materials for fusion applications

    Krimpalis, S., Mergia, K., Messoloras, S., Dubinko, A., Terentyev, D., Triantou, K., Reiser, J. & Pintsuk, G., 28 Nov 2017, PHYSICA SCRIPTA: 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC). 2017 ed. Vol. T170. p. 1-8 8 p. 014068. (Physica Scripta).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  20. Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel

    Van Dyck, S., Al Mazouzi, A., Rempel, A., stoenescu, R. & gavillet, D., 16 Jun 2005, Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel. Bejing, China, p. 10-4

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  21. Corrosion of A316L and T91 materials in liquid lead bismuth eutectic at temperatures 400-600°C

    Sapundjiev, D., Van Dyck, S. & Al Mazouzi, A., Oct 2005, Corrosion of A316L and T91 materials in liquid lead bismuth eutectic at temperatures 400-600°C. Lisbon, Portugal, p. 1-6

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  22. Corrosion-resistant ternary carbides for use in heavy liquid metal coolants

    Lambrinou, K., Lapauw, T., Jianu, A., Weisenburger, A., Ejenstam, J., Szakalos, P., Wallenius, J., Strom, E., Vanmeensel, K. & Vleugels, J., 2016, Ceramic Materials for Energy Applications V: Ceramic Engineering and Science Proceedings. Matyas, J., Katoh, Y., Lin, H-T., Vomiero, A., Wang, J. & Kirihara, S. (eds.). Wiley - John Wiley & Sons, Ltd, Vol. 36. p. 19-34 16 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  23. Cost-effective precracking of CHARPY V-NOTCH specimens for fracture toughness testing using a piezo-electric actuator

    Schuurmans, J. & Scibetta, M., Sep 2014, Hotlab website (hotlab.sckcen.be). Belgium

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  24. Crack initiation testing of highly irradiated stainless steel (thimble tube material with a dose up to 80 dpa) under PWR conditions

    Bosch, R-W., Vankeerberghen, M., Chaouadi, R., Gérard, R. & Somville, F., Sep 2010, Fontevraud 7 Symposium - Contribution of Materials Investigations to Improve the Safety and Performance of LWRs. Paris, France

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  25. Crack resistance curve measurement with miniaturized CT specimen

    Chaouadi, R., Lambrecht, M. & Gérard, R., 16 Jul 2018, Pressure Vessels and Piping Conference. 2018 ed. ASME - The American Society of Mechanical Engineers, 18 p. PVP2018-84690

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  26. Dedicated CT tests and numerical simulations to assess crack arrest by quasi-laminar flaws

    Dulieu, P., Lacroix, V., Gérard, R., Brynk, T., Uytdenhouwen, I. & Chaouadi, R., 12 Jul 2021, Proceedings of the ASME 2021 Pressure Vessels & Piping Conference: Volume 1: Codes and Standards. PVP2021 ed. ASME - The American Society of Mechanical Engineers, Vol. 1. p. 1-12 12 p. 61969

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  27. Degradation of 5 mol% Y2O3-ZrO2 used for the YSZ membrane electrode in high temperature water (300°C)

    Vandermeulen, W., Bosch, R-W. & Van Dyck, S., 15 Sep 2008, Water chemistry of nuclear reactor systems. Berlin, Germany

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  28. Design and safety studies of an EFIT core with cermet fuel

    Chen, X-N., Maschek, W., Liu, P., Rineiski, A., Wang, S., Matzerath Boccaccini, C., Sobolev, V., Rimpault, G. & De Bruyn, D., Jun 2011, Technology and components of accelerator-driven systems. Paris, France, p. 375-383

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  29. Design and safety studies on an EFIT core with CERMET fuel

    Chen, X-N., Rineiski, A., Liu, P., Maschek, W., Matzerath Boccaccini, C., Gabrielli, F., Sobolev, V. & Arien, B., Sep 2008, Proceedings of "International Conference on the Physics of Reactors -PHYSOR 2008". France, p. FP1821-FP1828

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  30. Design, development and qualification of advanced fuels for an industrial ADS prototype

    Delage, F., Fernandez Carretero, A., Matzerath Boccaccini, C., Chen, X-N., D’Agata, E., Klaassen, F., Maschek, W., Ottaviani, J-P., Rineiski, A., Sobolev, V., Hiernaut, J-P., Thetford, R., Wallenius, J. & De Bruyn, D., Feb 2010, Actinide and fission product partitioning and transmutation. Tenth Information Exchange Meeting.. France, p. 169-178

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  31. Design, safety and fuel developments for the EFIT accelerator-driven system with CERCER and CERMET cores

    Maschek, W., Artioli, C., Chen, X., Delage, F., Fernandez-Carretero, A., Flad, M., Fokau, A., Gabrielli, F., Glinatsis, G., Liu, P., Mansani, L., Matzerath Boccaccini, C., Petrovich, G., Rineiski, A., Sarotto, M., Schikorr, M., Sobolev, V., Wang, S., Zhang, Y. & De Bruyn, D., Feb 2010, Actinide and fission product partitioning and transmutation. Tenth Information Exchange Meeting.. Paris, France, p. 387-400

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  32. Development and testing of an in-core YSZ high temperature reference electrode

    Bosch, R-W., Wéber, M., Vandermeulen, W. & Van Dyck, S., 15 Sep 2008, Water chemistry in nuclear reactor systems. Berlin, Germany

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  33. Development of an in-house 188W/188Re generator

    Van de Voorde, M., Burgoyne, A., Ponsard, B., Elema, D., Cardinaels, T. & Ooms, M., 30 Oct 2020, European Journal of Nuclear Medicine and Molecular Imaging. suppl. 1 ed. Vol. 47. p. 477 478 p. (European Journal of Nuclear Medicine and Molecular Imaging ; vol. 47, no. Supplement 1).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  34. Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering

    Hózer, Z., Novotny, T., Perez-Feró, E., Horváth, M., Szabó, P., Illés, L., Schyns, M., Delville, R., Kim, D. & Sevecek, M., 4 Dec 2020, IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary. Vol. 903. p. 1-9 9 p. 012004. (IOP Conference Series: Materials Science and Engineering; vol. 903).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  35. Development of refined MCNPX paret multi channel model for transient analysis in research reactors

    Kalcheva, S. & Koonen, E., 15 Apr 2012, PHYSOR 2012: Conference on Advances in Reactor Physics: Linking Research, Industry, and Education. ANS - American Nuclear Society, p. 1-13 13 p. (Unknown).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  36. Economy of BR2 fuel cycle with gadolinium as burnable absorber

    Kalcheva, S. & Koonen, E., 16 Mar 2016, RRFM 2016-A0170. 2016 ed. ENS - European Nuclear Society, p. 1-10 10 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  37. Economy of BR2 Fuel Cycle with Gadolinium as Burnable Absorber

    Kalcheva, S. & Koonen, E., 1 May 2016, PHYSOR 2016–Unifying Theory and Experiments in the 21st Century. p. 1-8 8 p. (Unknown).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  38. Effect of cyclic loading on IASCC stress threshold of thimble tube material with a dose up to 80 dpa under PWR conditions

    Bosch, R-W., Konstantinovic, M., Vankeerberghen, M., Gérard, R. & Somville, F., 17 Sep 2018, International Symposium Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability. Unknown, p. 1-11 11 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  39. Effect of neutron irradiation on the mechanical properties of an A508 CL2 and 15KH2NMFA irradiated in the NOMAD-3 rig in the BR2 cooling water

    Uytdenhouwen, I. & Chaouadi, R., 12 Jul 2021, Proceedings of the ASME 2021 Pressure Vessels & Piping Conference. PVP2021 ed. ASME - The American Society of Mechanical Engineers, p. 1-12 12 p. 61969

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  40. Effect of transient heat loads on neutron irradiated tungsten and carbon based materials

    Pintsuk, G., Compan, J., Hirai, T., Linke, J., Rödig, M., Uytdenhouwen, I. & Chaouadi, R., Jun 2007, 2007 IEEE 22nd Symposium on Fusion Engineering, 2007. SOFE 2007.. New York, NY, United States, p. 1-4

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  41. Effects of liquid lead bismuth eutectic on the mechanical properties of A316L and T91 materials

    Sapundjiev, D., Al Mazouzi, A. & Van Dyck, S., Jul 2005, Effects of liquid lead bismuth eutectic on the mechanical properties of A316L and T91 materials. Belgium, p. 1-7

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  42. Effects of temperature on the mechanical properties of T91 material tested in liquid lead bismuth eutectic

    Sapundjiev, D., Van den Bosch, J., Al Mazouzi, A. & Van Dyck, S., Oct 2005, Effects of temperature on the mechanical properties of T91 material tested in liquid lead bismuth eutectic. Lisbon, Portugal, p. 1-5

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  43. Electrical Discharge Machining of ZrO2 Toughened WC Composites

    Malek, O., Vleugels, J., Perez, Y., De Baets, P., Liu, J., Van den Berghe, S. & Lauwers, B., May 2009, Proceedings of the International Conference on High Performance P/M Materials. Austria

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  44. Ensuring data quality for environmental fatique - INCEFA-PLUS testing procedure and data evaluation

    Vankeerberghen, M., Bruchhausen, M., Cicero, R., Doremus, L., Le Roux, J-C., Platts, N., Spätig, P., Twite, M. & Mottershead, K., 15 Jul 2018, Proceedings of the ASME pressure vessels and piping conference. PVP-2018-84081 ed. ASME - The American Society of Mechanical Engineers, Vol. 1A. p. 1-7 7 p. V01AT01A014

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  45. EPMA of ground U(Mo) fuel with and without Si added to the matrix, irradiated to high burnup

    Leenaers, A., Van den Berghe, S., Charollais, F., Lemoine, P., Jarousse, C., Rohrmoser, A., Petry, W. & Van Renterghem, W., Mar 2010, RRFM2010 Transactions. Belgium

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  46. Erosion and deposition in the JET divertor during the first ILW campaign

    Mayer, M., Krat, S., Van Renterghem, W., Baron-Wiechec, A., Brezinsek, S., Bykov, I., Coad, P., Gasparyan, Y., Heinola, K., Likonen, J., Pisarev, A., Ruset, C., de Saint-Aubin, G. & Widdowson, A., 21 Jan 2016, https://iopscience.iop.org/journal/1402-4896. Vol. T167. 9 p. (Physica Scripta).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  47. Establishing a multi-laboratory test plan for environmentally assisted fatigue

    Bruchhausen, M., Mottershead, K., Hurley, C., Métais, T., Cicero, R., Vankeerberghen, M. & Le Roux, J-C., May 2016, American Society for Testing and Materials Selected Technical Papers: Fatigue and Fracture Test Planning, Test Data Acquisitions and Analysis. TP1598-EB ed. Vol. 1598. p. 1-24 24 p. STP159820160047. (Journal of ASTM International).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  48. Estimation of uniaxial and creep properties by small punch testing in support of ECCC test programmes

    Holmström, S., Nilsson, K-F., De Bruycker, E., Anelli, E., Guery, A., Rantala, J., Simonovski, I. & Baraldi, D., 20 Oct 2021, ECCC 2021 - 5th international Creep & Fracture Conference: Abstracts handbook, virtual conference 19th, 20th Oct 2021. 2021 ed. European Creep Collaborative Committee, p. 1-13 13 p. 116

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  49. European Lead Fast Reactor

    Alemberti, A., Carlsson, J., Malambu Mbala, E., Orden, A., Cinott, L., Struwe, D., Agostini, P., Monti, S. & Sobolev, V., 9 Dec 2009, Proceedings of Int. Conf. on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities FR09. Vienna, Austria

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  50. European Lead-cooled SYstem core design: an approach towards sustainability

    Artioli, C., Grasso, G., Sarotto, M., Monti, S., Malambu Mbala, E. & Sobolev, V., 10 Dec 2009, Proceedings of Int. Conf. on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities FR09. Vienna, Austria

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  51. Evaluation of the Fatigue Crack Growth of an ABNT 4133 Modified Steel (API - 5CT)

    José Vilela, J., Pimenta Alves, M., Gonçalves Carneiro, J. R., Vilela Costa, L., Scibetta, M., Oliveira Menezes, R. M. R. & de Paula Martins, G., Jul 2009, Technical contribution to 64th International Congress of the ABM. Brazil

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

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