KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors

References

1 Chanaron, B.; Ahnert, C.; Crouzet, N.; Sanchez, V.; Kolev, N.; Marchand, O.; Kliem, S.; Papukchiev, A.: Advanced Multi-physics Simulation for Reactor Safety in the framework of the NURESAFE Project. Annals of Nuclear Energy (2015) 166–17710.1016/j.anucene.2014.12.013Search in Google Scholar

2 Gaston, D.; Newman, G. H. C.; Lebrun-Grandie, D.: MOOSE; A parallel computational framework for coupled code systems of non-linear equations. Nuclear Engineering and Design239 (2009) 1768–177810.1016/j.nucengdes.2009.05.021Search in Google Scholar

3 Palmtag, S.; Clarno, K.; Davidson, G.; Evans, T.; Turner, J.; Belcourt, K.; HooperR.; SchmidtR.: Coupled Neutronics and Thermal Hydraulic solution of a Full-core PWR using VERA-CS. PHYSOR-2014, Kyoto, Japan, 2014Search in Google Scholar

4 Sánchez, V.; Imke, U.; Gomez, R.: SUBCHANFLOW: A Thermal-Hydraulic Sub-Channel Program to Analyse Fuel Rod Bundles and Reactor Cores. 17th Pacific Basin Nuclear Conference., Cancún, México, October 24–30, 2010Search in Google Scholar

5 Imke, U.: Porous media simplified simulation of singleand two-phase heat trasnfer in micro-channel heat exchangers. Chemical Engineering Journal101 (2004) 295–30210.1016/j.cej.2003.10.012Search in Google Scholar

6 Trost, N.; Jimenez, J.; Imke, U.; Sánchez, V.: TwoporFlow – A Porous media Two Phase Flow code. Kalsruhe Institute of Technology, Karlsruhe, Germany, 201Search in Google Scholar

7 Trost, N.; Jimenez, J.; Sánchez, V.; Imke, U.: Parallelization of TWOPORFLOW, a Cartesian grid based two-phase porous media code for transient thermo-hydraulic simulations. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013. SNA+ MC2013, Paris, France, 201310.1051/snamc/201405402Search in Google Scholar

8 Imke, U.; Sánchez, V.: Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT). Science and Technology of Nuclear Installations (2012) Article ID 46505910.1155/2012/465059Search in Google Scholar

9 Calleja, M.; Sánchez, V.; Jimenez, J.; Imke, U.; Stieglitz, R.; Macián-Juan, R.: Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks. Annals of Nuclear Energy66 (2014) 145–15810.1016/j.anucene.2014.03.036Search in Google Scholar

10 Jimenez, J.: Coupling of SUBCHANFLOW with different core simualtors inside SALOME. KIT Internal Report, Karlsruhe, Germany, 2015Search in Google Scholar

11 Daeubler, M.; Trost, N.; Jimenez, J.; Sánchez, V.; Stieglitz, R.; Macián-Juan, R.: Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB. Annals of Nuclear Energy84 (2015) 31–4410.1016/j.anucene.2014.09.057Search in Google Scholar

12 Basualdo, J.; Sánchez, V.: PARCS/Subchanflow: Nodal Internal Coupling. International CAMP Spring Meeting, Prague, Czech, 2015Search in Google Scholar

13 Calleja, M.: Improvements in Multi-physics and Multi-scale Methodologies for Safety-related Investigations of Pressurized Water Reactors within the NURESIM Platform. KIT Doctoral Thesis, Karlsruhe, Germany, 2013Search in Google Scholar

14 Gomez, A.; Kliem, S.; Gommlich, A.: Implementation of a fast running full core pin power reconstruction method in DYN3D. Nuclear Engineering and Design274 (2014) 44–5510.1016/j.nucengdes.2014.04.028Search in Google Scholar

15 Gomez, A. M.; Sánchez, V.; Ivanov, K.; Macián-Juan, R.: DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part I: Development, implementation and verification. Annals of Nuclear Energy48 (2012) 108–12210.1016/j.anucene.2012.05.011Search in Google Scholar

16 Ivanov, A.; Sánchez, V.; Stieglitz, R., Ivanov, K.: Internal multi-scale multi-physics coupled system for high fidelity simulation of light water reactors. Annals of Nuclear Energy66 (2014) 104–11210.1016/j.anucene.2013.12.003Search in Google Scholar

17 Daeubler, M.; Ivanov, A.; Sjenitzer, B.; Sánchez, V.; Stieglitz, Macián-Juan, R.: High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW. Annals of Nuclear Energy83 (2015) 352–37510.1016/j.anucene.2015.03.040Search in Google Scholar

18 Sánchez, V. H.; van Dorseleare, J.-P.; Klein-Heßling, W.; Miassoedov, A.: European View on Severe Accidents R&D Needs for Beyond Design Basis Accidents: Important Severe Accident R & D Issues after Fukushima. ICONE-23, Chiba, Japan, May 27-21. 2015Search in Google Scholar

19 van Dorseleare, J.-P.; Chatelard, P.; Chevalier-Jabet, K.; Nowack, H.; Herranz, L. E.; Pasal, G.; Sánchez-Espinoza, V. H.: ASTEC code development, validation and applications for severe accident management within the CESAM European project. ICAPP, P15392, Nice, 2015Search in Google Scholar

20 Steinbrück, M.; Große, M.; Sepold, L.; Stuckert, J.: Synopsis and outcome of the QUENCH experimental program. Nuclear Engineering and Design240 (2010) 1714–172710.1016/j.nucengdes.2010.03.021Search in Google Scholar

21 Miassoedov, A.; Cron, T.; Gaus-Liu, Y.; Palagin, A.; Schmidt-Stiefel, S.; Wenz, T.: LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head. Heat Transfer Engineering201 (2015) 1226–1236Search in Google Scholar

22 Miassoedov, A.; Albrecht, J. F. G.; Jordan, T.; Steinbrück, M.; StuckertJ.; Tromm, W.: Overview of LWR Severe Accident Research Activities at the Karlsruhe Institute of Technology. 14th Brazilian COngress of Thermal Sciences and Engineering, Rio de Janeiro, Brazil, 2012Search in Google Scholar

23 Miassoedov, A.; Jordan, T.; Steinbrück, M.; Tromm, W.: LWR severe accident research at the Karlsruhe Institute of Technology. 22nd International Congress of Mechanical Engineering (COBEM), Sau Paulo, Brazil, 2013Search in Google Scholar

24 Miassoedov, A.; Journeau, C.; Bechta, S.; Hozer, Z.; Manara, D.; Bottomley, D.; Kisclova, M.; Langrock, G.: Severe Accident Facilities for European Safety Targets. The SAFEST Project. 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, USA, 2015Search in Google Scholar

25 Zhang, S.; Miassoedov, A.; Liao, Y.; Ruggieri, J.-M.; ShenF.; Gaus-Liu, X.: ALISA Project. Access to Large Infrastructures for Severe Accidents in Europe and in China. 5th European Review Meeting on Severe Accident Research (ERMSAR-2012), Cologne, Germany, 2012, March 21–23Search in Google Scholar

26 Szabó, T.: Verbesserte Berechnung der Wasserstoffverteilung im Sicherheitsbehälter bei der Analyse schwerer Störfälle in Kernkraftwerken durch Kopplung von MELCOR und GASFLOW. KIT-SR 7658, Karlsruhe, 2014Search in Google Scholar

27 García-Toraño, I. G.; V.Sanchez und R.Stieglitz, ASTEC Validation based on the KIT Re-flooding Experiment QUENCH-08. Annual Meeting on Nuclear Technology., in Annual Meeting of Nuclear Technology, Frankfurt, Germany, May 6–8 2014Search in Google Scholar

28 DiMarcello, V.; Belousov, A.; Imke, U.; Sánchez-Espinoza, V. H.: ATHLET-CD post-test calculations of CORA-17 bundle experiment. Annual Meeting on Nuclear Technology, Frankfurt, Germany, 2014, May 6–8Search in Google Scholar

29 García-Toraño, I. G.; SánchezV.; Stieglitz, R.: Simulation of large break LOCA sequence in a German PWR Konvoi with ASTEC. Annual Meeting on Nuclear Technology, Berlin, German, 2015, May 5–7Search in Google Scholar

30 DiMarcello, V.; SánchezV.; Imke, U.: WASA-BOSS: Investigation of the coolability of partly-damaged BWR core by water injection into the RPV. Annual Meeting on Nuclear Technology, Berlin, Germany, 2015, May 5–7Search in Google Scholar