The LIVE program - Results of test L1 and joint analyses on transient molten pool thermal hydraulics. In Bal Raj Sehgal, Jean-Pierre Van Dorsselaere, Thierry Albiol, Didier Jacquemain, and Christophe Journeau (Eds.), Major achievements after 4,5 years of SARNET Severe Accident Research Network of Excellence, 52, 1, special issue:46-60, Elsevier, Amsterdam, 2010. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Influence of weld-seams on the fluid-structure-interactions in pipe flows. Fatigue design 2011 : Recueil de conférences : Conference proceedings, Cetim, Senlis, 2011. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Numerical study of nuclear coupled two-phase flow instability in natural circulation system under low pressure and low quality. In Liangzhi Cao, Guanghui Su, and Yassin Hassan (Eds.), The 18th International Conference on Nuclear Engineering (ICONE-18), 241, 12:4972-4977, Elsevier, Amsterdam, 2011. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40072 unibibliografie]
Experimental setup for the investigation of fluid-structure interactions in a T-junction. In Jovica R. Riznic (Eds.), NURETH-14 : The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, CNS, Toronto, 2011. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Quenching experiments : coolability of DEBRIS bed. NURETH-14 : the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics : September 25 - 30, 2011, Toronto Hilton Hotel, Toronto, Ontario, Canada, CNS, Toronto, 2011. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Coolability of particulate beds in severe accidents: Status and remaining uncertainties. In Bal Raj Sehgal, Jean-Pierre Van Dorsselaere, Thierry Albiol, Didier Jacquemain, and Christophe Journeau (Eds.), Major achievements after 4,5 years of SARNET Severe Accident Research Network of Excellence, 52, 1, special issue:61-75, Elsevier Science, Amsterdam, 2010. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Experimental results on the coolability of a debris bed with multidimensional cooling effects. In Hisashi Ninokata, and Yassin Hassan (Eds.), 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 241, 11, special issue:4537-4543, Elsevier, Amsterdam, 2011. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Experimental investigation of vapor bubbles nucleating in bulk liquid. In Josua P. Meyer (Eds.), Proceedings of the Seventh International Conference on Heat Transfer, Fluid Mechanics & Thermodynamics, HEFAT 2010, HEFAT, Antalya, 2010. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Experimental results on the coolability of a debris bed with down comer configurations. Proceedings of the 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), Jiao Tong University, Shanghai, 2010. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Concept of a pressurized water reactor cooled with supercritical water in the primary loop. In Michael A. Fütterer, Yassin Hassan, and Finis H. Southworth (Eds.), 4th International Topical Meeting on High Temperature Reactor Technology (HTR 2008), with regular papers, 240, 10, special issue:2789-2799, Elsevier Science, Amsterdam, 2010. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
Modelling and simulation of the radioactive release during the Fukushima accident. 2011. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 unibibliografie] URL
Steady state operation of a copper-water LHP with a flat-oval evaporator. In John Lewis, and Tassos G. Karayiannis (Eds.), MNF 2009 Special Issue, 31, 5:686-695, Elsevier, Amsterdam, 2011. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40072 unibibliografie]
Evaluation of medium 1000MWth sodium-cooled fast reactor neutronic OECD benchmarks. In Kenya Suyama (Eds.), Proceedings of the International Conference on the Physics of Reactors (PHYSOR2014), 2014, 3JAEA, Tōkaimura, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 unibibliografie]
Feasibility study on the thermal management of inductive distance sensors by a heat pipe cooling system. In Sameer Khandekar (Eds.), Science and technology of heat pipes : Historical perspective to contemporary development : Proceedings of the 17th International Heat Pipe Conference, 5, 1-4:647-654, Begell House, Redding, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Investigations on cooling possibilities of a degraded core in a MBLOCA scenario for a German PWR with ATHLET-CD. 19th Pacific Basin Nuclear Conference (PBNC 2014), (3):1899-1911, Curran, Red Hook, NY, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Monte Carlo neutronics analysis of sodium-cooled fast reactor benchmark with OTF temperature and burn-up treatment. In Kenya Suyama (Eds.), Proceedings of the International Conference on the Physics of Reactors (PHYSOR2014), 2014, 3JAEA, Tōkaimura, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Physical separation and disposal of secondary waste from the decommissioning of nuclear facilities. FILTECH 2015 : International Conference & Exhibition for Filtration and Separation Technology, FILTECH Exhibitions Germany, Meerbusch, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Recent experiments and numerical simulations on coolability of degraded cores in the late phase of severe accidents of light water reactors. 19th Pacific Basin Nuclear Conference (PBNC 2014), (2):1604-1611, Curran, Red Hook, NY, 2015. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Power cycle calculations and preliminary design of a compact heat exchanger of a scaled down sCO2-HeRo-system for a PWR glass model at KSG/GfS. 2016. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Development of passive spent fuel pool cooling by heat pipes. 47th Annual Meeting on Nuclear Technology : The International Expert Conference on Nuclear Technology : Proceedings, INFORUM Verlags- und Verwaltungsgesellschaft mbH, Berlin, 2016. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]