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Subtopic 2.1: Design Basis Accidents and Materials Research

B. Chanaron, C. Ahnert, N. Crouzet, V. Sanchez, […], S. Kliem, et al., Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project, Ann. Nucl. Energy  84, 166 (2015) doi.org/10.1016/j.anucene.2014.12.013

A. Das, H.-W. Viehrig, F. Bergner, C. Heintze, E. Altstadt, J. Hoffmann, Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel - the role of primary and secondary cracking, J. Nucl. Mater. 491, 83 (2017) DOI: 10.1016/j.jnucmat.2017.04.059

W. Ding, T. Geißler, E. Krepper, U. Hampel, Critical heat flux as a mass flux dependent local or global phenomenon: Theoretical analysis and experimental confirmation, Int. J.Therm. Sci. 130, 200 (2018) 10.1016/j.ijthermalsci.2018.04.040

C. Heintze, I. Hilger, F. Bergner, T. Weissgärber, B. Kieback, Nanoindentation of single- (Fe) and dual-beam (Fe and He) ion-irradiated ODS Fe-14Cr-based alloys: effect of the initial microstructure on irradiation-induced hardening, J. Nucl. Mater. 518, 1 (2019) 10.1016/j.jnucmat.2019.02.037

T. Höhne, S. Gabriel, Simulation of a counter-current horizontal gas-liquid flow experiment at the WENKA channel using a droplet entrainment model, Ann. Nucl. Energy 121, 414 (2018) doi.org/10.1016/j.anucene.2018.07.047

V. Jauregui Chavez, U. Imke, V. Sanchez-Espinoza, TWOPORFLOW: A two-phase flow porous media code, main features and validation with BWR-relevant bundle experiments, Nucl. Eng. Des. 338, 181 (2018) doi.org/10.1016/j.nucengdes.2018.08.009

E. Nikitin, E. Fridman, Extension of the reactor dynamics code DYN3D to SFR applications – Part I: Thermal expansion models, Ann. Nucl. Energy 119, 382 (2018)  10.1016/j.anucene.2018.05.015

M. Knebel, L. Mercatali, V. Sanchez, R. Stieglitz, R. Macian-Juan, Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III) Ann. Nucl. Energy  91, 79 (2016) doi.org/10.1016/j.anucene.2016.01.005

E. Krepper, R. Rzehak, D. Lucas, Validation of a closure model framework for turbulent bubbly two-phase flow in different flow situations, Nucl. Eng. Des. 340, 388 (2018) 10.1016/j.nucengdes.2018.09.042

Y. Liao, D. Lucas, Poly-disperse simulation of flash evaporation of water inside a large vertical pipe using class method of population balance, Int. J. Heat Fluid Fl. 77, 299 (2019) 10.1016/j.ijheatfluidflow.2019.05.005

J. Pacio, M. Daubner, F. Fellmoser, K. Litfin, T. Wetzel, Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE, Nucl. Eng. Des. 330, 225 (2018) doi.org/10.1016/j.nucengdes.2018.01.034

J. Pacio, T. Wetzel, H. Doolaard, F. Roelofs, K. Van Tichelen, Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations, Nucl. Eng. Des. 312, 327 (2016) doi.org/10.1016/j.nucengdes.2016.08.023

V. Tsisar, C. Schroer, O. Wedemeyer, A. Skrypnik, J. Konys, Effect of Structural State and Surface Finishing on Corrosion Behavior of 1.4970 Austenitic Steel at 400 and 500 °C in Flowing Pb-Bi Eutectic With Dissolved Oxygen, ASME J. of Nuclear Rad. Sci. 1(4), 047001 (2015) nuclearengineering.asmedigitalcollection.asme.org/article.aspx?articleid=2422759&resultClick=3

V. Tsisar, C. Schroer, O. Wedemeyer, A. Skrypnik, J. Konys, Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550 °C to flowing Pb-Bi eutectic with 10⁻⁷  mass% dissolved oxygen, J. Nucl. Mater. 494, 422 (2017) doi.org/10.1016/j.jnucmat.2017.07.031

F. Röder, C. Heintze, […], F. Bergner, A. Ulbricht, E. Altstadt, Nanoindentation of ion-irradiated reactor pressure vessel steels – model-based interpretation and comparison with neutron irradiation, Philos. Mag. 89, 911 (2018) 10.1080/14786435.2018.1425007

Subtopic 2.2: Beyond Design Basis Accidents and Emergency Management

X. Gaus-Liu, A. Miassoedov, Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head. ASME J. of Nuclear Rad. Sci. 3(3), 031003 (2017) DOI: 10.1115/1.4035853

I. Gómez-García-Toraño, V. Sánchez-Espinoza, R. Stieglitz, J. Stuckert, L. Laborde, et al., Validation of ASTECV2.1 based on the QUENCH-08 experiment, Nucl. Eng. Des. 314, 29 (2017) doi.org/10.1016/j.nucengdes.2016.12.039

I. Gómez-García-Toraño, V. Sánchez-Espinoza, R. Stieglitz, C. Queral, M. Rebollo, Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0, Ann. Nucl. Energy 113, 476 32.02.11 doi.org/10.1016/j.anucene.2017.11.053

M. Grosse, S. Pulvermacher, M. Steinbrück, B. Schillinger, In-situ neutron radiography investigations of the reaction of Zircaloy-4 in steam, nitrogen/steam and air/steam atmospheres, Physica B  Condens. Matter. 551, 244 (2018) doi.org/10.1016/j.physb.2018.03.030

S. Kelm, W. Jahn, J. Lehmkuhl, H.-J. Allelein,  A comparative assessment of different experiments on buoyancy driven mixing processes by means of CFD, Ann. Nucl. Energy 93, 50 (2016) doi.org/10.1016/j.anucene.2015.12.032

S. Kelm, R. Kapulla, H.-J. Allelein, Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI Benchmark, Nucl. Eng. Des. 312, 228 (2017) doi.org/10.1016/j.nucengdes.2016.09.014

M. Kurata, M. Barrachin, T. Haste, M. Steinbrück, Phenomenology of BWR fuel assembly degradation, J. Nucl. Mater 500, 119 (2018).doi.org/10.1016/j.jnucmat.2017.12.004

J. Lehmkuhl, S. Kelm, M. Bucci, H.-J. Allelein, Improvement of wall condensation modeling with suction wall functions for containment application, Nucl. Eng. Des. 299, 105 (2016) doi.org/10.1016/j.nucengdes.2015.08.002

S. Moehrle, W. Raskob, Structuring and reusing knowledge from historical events for supporting nuclear emergency and remediation management Eng. Appl. Artif. Intel. 46(Part B) 303 (2015) doi.org/10.1016/j.engappai.2015.07.010

H. Nowack, P. Chatelard, L. Chailan, S. Hermsmeyer, V. Sanchez, et al., CESAM – Code for European severe accident management, EURATOM project on ASTEC improvement, Ann. Nucl. Energy 116, 128 (2018) doi.org/10.1016/j.anucene.2018.02.021

W. Raskob, T. Almahayni, N. Beresford, Radioecology in CONFIDENCE: Dealing with uncertainties relevant for decision making, J. Environ. Radioact .192, 399 (2018) doi.org/10.1016/j.jenvrad.2018.07.017

E.-A. Reinecke, S. Kelm, P.-M. Steffen, M. Klauck, H.-J. Allelein, Validation and application of the REKO-DIREKT code for the simulation of passive auto-catalytic recombiners (PARs) operational behavior, Nucl. Technol .196(2), 355 (2016) doi.org/10.13182/NT16-7

E.-A. Reinecke, A. Bentaïb, J. Dornseiffer, D. Heidelberg, F. Morfin, P. Zavaleta, H.-J. Allelein, A first orienting investigation of the interaction of cable fire products with passive auto-catalytic recombiners (PARs), Nucl. Technol. 196(2), 367 (2016) doi.org/10.13182/NT16-4

T. Schneider, F. Gering, S. Charron, M. Zhelezniak, […], W. Raskob, Nuclear and Radiological Preparedness: The Achievements of the European Research Project PREPARE, Radiat. Prot. Dosim. 173(1-3), 151(2017) doi.org/10.1093/rpd/ncw318

T. Schneider, S. Lafage, J. Bardelay, T. Duranova, […], W. Raskob, NERIS: European platform on preparedness for nuclear and radiological emergency response and recovery - Activities and perspectives, Radioprotection 51(HS1), S5 (2016) doi.org/10.1051/radiopro/2016003