Foto: Programm Nukleare Entsorgung und Sicherheit ©Copyright: BengsSafety Research for Nuclear Reactors

Energy > Nuclear Waste Management and Safety as well as Radiation Research - All Topics

Foto: Flows in a nuclear reactor ©Copyright: HZDR/Oliver KilligAlthough Germany decided to shut down all nuclear reactors for energy production until 2022, own reactor safety research is needed in future. The preservation of competence in nuclear engineering is essential for the safety assessment of nuclear power plants and nuclear projects in Germany and abroad. Only in that way Germany is able to influence international safety standards and to participate in international research projects.

Based on this background the work within the topic “Reactor Safety” is concentrated on the research on safety aspects of currently operating nuclear reactors and new reactor types being under development in the neighboring countries. It covers the development of methods for analyses of transients and postulated accidents, the investigation of ageing phenomena in materials and integrity of components, and the safety related aspects connected with the thermal fluid dynamics of cooling water or liquid metal flows. Especially after the Fukushima accident in 2011, the efforts on the investigation of accident management measures in nuclear reactors have been increased.

Objectives

  • Development and validation of neutron kinetic and thermal hydraulic methods for the analysis of design basis and severe accidents for nuclear reactors.
  • Development and qualification of predictive Computational Fluid Dynamics (CFD) models for two-phase flows
  • Conduction of industry-grade experiments for code validation using innovative measuring techniques (TOPFLOW facility)
  • Exploration of the mechanisms of irradiation effects in reactor pressure vessel steels and Gen-IV candidate materials by means of nanostructural characterization, atomistic modelling and mechanical testing

Press Releases

Involved HZDR institutes

Collaborations

Contacts

Publications

  • Pukenas, A.; Chekhonin, P.; Scharnweber, J. et al.
    TiAl-based semi-finished material produced by reaction annealing of Ti/Al layered composite sheets
    Materials Today Communications 30(2022), 103083 (10.1016/j.mtcomm.2021.103083)
  • Das, A.; Altstadt, E.; Kaden, C. et al.
    Nanoindentation response of ion-irradiated Fe, Fe-Cr alloys and ferritic-martensitic steel Eurofer 97: The effect of ion energy
    Frontiers in Materials 8(2022), 630 (10.3389/fmats.2021.811851)
  • Zhang, T.; Huang, G.; Yin, J. et al.
    Investigation on swirl instability in a vane-type separator with tomographic PIV
    Journal of Fluids Engineering - Transactions of the ASME (2021), FE-21-1202 (10.1115/1.4052547)
  • Kapoor, G.; Chekhonin, P.; Kaden, C. et al.
    Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy
    Nuclear Materials and Energy 30(2022), 101105 (10.1016/j.nme.2021.101105)
  • Sanchez-Espinoza, V. H.; Gabriel, S.; Suikkanen, H. et al.
    The H2020 McSAFER project: Main goals, technical work program, and status
    Energies 14(2021), 6348 (10.3390/en14196348)
  • Viebach, M.; Lange, C.; Kliem, S. et al.
    Verification of the code DYN3D for calculations of neutron flux fluctuations
    Annals of Nuclear Energy 166(2022), 108735 (10.1016/j.anucene.2021.108735)
  • Davies, S.; Litskevich, D.; Rohde, U. et al.
    DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)
    Energies 14(2021), 5060 (10.3390/en14165060)
  • Malerba, L.; Caturla, M. J.; Gaganidze, E. et al.
    Multiscale modelling for fusion and fission materials: the M4F project
    Nuclear Materials and Energy 29(2021), 101051 (10.1016/j.nme.2021.101051)
  • Windisch, D.; Knodel, O.; Juckeland, G. et al.
    FPGA-based Real-Time Data Acquisition for Ultrafast X-Ray Computed Tomography
    IEEE Transactions on Nuclear Science 68(2021)12, 2779-2786 (10.1109/TNS.2021.3123837)
  • Gu, B.; Chekhonin, P.; Xin, S. W. et al.
    Microstructure and texture development during hot-compression of Ti5321
    Materials Characterization 179(2021), 111297 (10.1016/j.matchar.2021.111297)
  • Sornin, D.; Ehrnsten, U.; Mozzani, N. et al.
    Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure
    Metallurgical and Materials Transactions A 52(2021), 3541-3552 (10.1007/s11661-021-06327-0)
  • Garcia, M.; Vocka, R.; Tuominen, R. et al.
    Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
    Nuclear Engineering and Technology 53(2021), 3133-3150 (10.1016/j.net.2021.04.023)
  • Di Nora, V. A.; Fridman, E.; Nikitin, E. et al.
    Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part II: methodology application
    Annals of Nuclear Energy 163(2021), 108541 (10.1016/j.anucene.2021.108541)
  • Gu, B.; Chekhonin, P.; Xin, S. W. et al.
    Effect of temperature and strain rate on the deformation behavior of Ti5321 during hot-compression
    Journal of Alloys and Compounds 876(2021), 159938 (10.1016/j.jallcom.2021.159938)
  • Nikitin, E.; Fridman, E.; Mikityuk, K. et al.
    Neutronic Modelling of the FFTF Control Rod Worth Measurements with Diffusion Codes
    European Physical Journal Web of Conferences 247(2021), 10017 (10.1051/epjconf/202124710017)
  • Baker, U.; Margulis, M.; Shwageraus, E. et al.
    Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients
    Journal of Nuclear Engineering and Radiation Science 8(2021)1, 011316 (10.1115/1.4052121)
  • Ponomarev, A.; Mikityuk, K.; Fridman, E. et al.
    Superphénix Benchmark Part II: Transient Results
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011321 (10.1115/1.4051877)
  • Jiménez-Carrascosa, A.; García-Herranz, N.; Krepel, J. et al.
    Decay heat characterization for the European Sodium Fast Reactor
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011319 (10.1115/1.4051798)
  • Ponomarev, A.; Mikityuk, K.; Zhang, L. et al.
    Superphénix Benchmark Part I: Results of Static neutronics
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011320 (10.1115/1.4051449)
  • Viebach, M.; Lange, C.; Seidl, M. et al.
    Neutron noise patterns from coupled fuel-assembly vibrations
    European Physical Journal Web of Conferences 247(2021), 02015 (10.1051/epjconf/202124702015)
  • Bilodid, Y.; Leppänen, J.
    Effect of the Uniform Fission Source method on local power variance in full core Serpent calculation
    European Physical Journal Web of Conferences 247(2021), 04024 (10.1051/epjconf/202124704024)
  • Ferraro, D.; García, M.; Imke, U. et al.
    SERPENT/SUBCHANFLOW coupled calculations for a VVER core at hot full power
    European Physical Journal Web of Conferences 247(2021), 04006 (10.1051/epjconf/202124704006)
  • Garcia, M.; Tuominen, R.; Gommlich, A. et al.
    SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly
    European Physical Journal Web of Conferences 247(2021), 06016 (10.1051/epjconf/202124706016)
  • Davies, S.; Rohde, U.; Litskevich, D. et al.
    CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development
    Energies 14(2021), 1220 (10.3390/en14051220)
  • Rzehak, R.; Liao, Y.; Meller, R. et al.
    Radial pressure forces in Euler-Euler simulations of turbulent bubbly pipe flows
    Nuclear Engineering and Design 374(2021), 111079 (10.1016/j.nucengdes.2021.111079)
  • Vogel, K.; Chekhonin, P.; Kaden, C. et al.
    Depth distribution of irradiation-induced dislocation loops in an Fe-9Cr model alloy irradiated with Fe ions: The effect of ion energy
    Nuclear Materials and Energy 27(2021), 101007 (10.1016/j.nme.2021.101007)
  • Tekavčič, M.; Meller, R.; Schlegel, F.
    Validation of a morphology adaptive multi-field two-fluid model considering counter-current stratified flow with interfacial turbulence damping
    Nuclear Engineering and Design 379(2021), 111223 (10.1016/j.nucengdes.2021.111223)
  • Garcia, M.; Bilodid, Y.; Basualdo Perello, J. et al.
    Validation of Serpent-SCF-TU full-core pin-by-pin burnup calculations using Pre-Konvoi PWR experimental data
    Nuclear Engineering and Design 379(2021), 111173 (10.1016/j.nucengdes.2021.111173)
  • Prasser, H.-M.; Hampel, U.; Schütz, P.
    TOPFLOW Pressure Chamber – versatile techniques to simplify design and instrumentation of thermal fluid dynamic experiments at high pressure
    Nuclear Engineering and Design 372(2021), 110971 (10.1016/j.nucengdes.2020.110971)
  • Colombo, M.; Rzehak, R.; Fairweather, M. et al.
    Benchmarking of computational fluid dynamic models for bubbly flows
    Nuclear Engineering and Design 375(2021), 111075 (10.1016/j.nucengdes.2021.111075)
  • Zhao, X.; Liao, Y.; Wang, M. et al.
    Numerical simulation of micro-crack leakage on steam generator heat transfer tube
    Nuclear Engineering and Design 382(2021), 111385 (10.1016/j.nucengdes.2021.111385)
  • Di Nora, V. A.; Fridman, E.; Nikitin, E. et al.
    Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: methodology demonstration
    Annals of Nuclear Energy 155(2021), 108183 (10.1016/j.anucene.2021.108183)
  • Krauter, N.; Galindo, V.; Wondrak, T. et al.
    Eddy Current Flow Meter performance in liquid metal flows inclined to the sensor axis
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011303 (10.1115/1.4050420)
  • Altstadt, E.; Bergner, F.; Houska, M.
    Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels
    Nuclear Materials and Energy 26(2021), 100918 (10.1016/j.nme.2021.100918)
  • Buchholz, S.; Bonfigli, G.; Schäfer, F. et al.
    Safety Cases for Design-Basis Accidents in LWRs Featuring Passive Systems Part 2 - Numerical Investigations
    Nuclear Engineering and Design 372(2021), 110996 (10.1016/j.nucengdes.2020.110996)
  • Mull, T.; Wagner, T.; Bonfigli, G. et al.
    Safety Cases for Design-Basis Accidents in LWRs Featuring Passive Systems Part 1 - Experimental Investigations
    Nuclear Engineering and Design (2021), 111095 (10.1016/j.nucengdes.2021.111095)
  • Liao, Y.; Lucas, D.
    A review on numerical modelling of flashing flow with application to nuclear safety analysis
    Applied Thermal Engineering 182(2021), 116002 (10.1016/j.applthermaleng.2020.116002)
  • Fridman, E.; Álvarez-Velarde, F.; Romojaro-Otero, P. et al.
    Neutronic analysis of the European Sodium Fast Reactor: Part II - burnup results
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011302 (10.1115/1.4048765)
  • Fridman, E.; Álvarez-Velarde, F.; Romojaro-Otero, P. et al.
    Neutronic analysis of the European Sodium Fast Reactor: Part I - fresh core results
    Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011301 (10.1115/1.4048905)
  • Grahn, A.; Diaz Pescador, E.; Kliem, S. et al.
    Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2.3 experiment
    Nuclear Engineering and Design 372(2021), 110938 (10.1016/j.nucengdes.2020.110938)
  • Rydlewicz, W.; Fridman, E.; Shwageraus, E.
    Modelling ASTRID-Like Sodium-Cooled Fast Reactor with Serpent DYN3D Code Sequence
    European Physical Journal Web of Conferences 247(2021), 02028 (10.1051/epjconf/202124702028)
  • Davies, U.; Margulis, M.; Shwageraus, E. et al.
    Evaluation of the ESFR End of Cycle State and Detailed Spatial Distributions of Reactivity Coefficients
    European Physical Journal Web of Conferences 247(2021), 02001 (10.1051/epjconf/202124702001)
  • Diaz Pescador, E.; Schäfer, F.; Kliem, S.
    Modelling of multidimensional effects in thermal-hydraulic system codes under asymmetric flow conditions – Simulation of ROCOM Tests 1.1 and 2.1 with ATHLET 3D-Module
    Nuclear Engineering and Technology 53(2021)10, 3182-3195 (10.1016/j.net.2021.04.015)
  • Unger, S.; Arlit, M.; Beyer, M. et al.
    Experimental study on the advective heat flux of a heat exchanger for passive cooling of spent fuel pools by temperature anemometry grid sensor
    Nuclear Engineering and Design 379(2021), 111237 (10.1016/j.nucengdes.2021.111237)
  • Das, A.; Viehrig, H. W.; Bergner, F. et al.
    Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel – the role of primary and secondary cracking
    Journal of Nuclear Materials 491(2017), 83-93 (10.1016/j.jnucmat.2017.04.059)
  • Liao, Y.; Lucas, D.
    Computational modelling of flashing flows: a literature survey
    International Journal of Heat and Mass Transfer 111(2017), 246-265 (10.1016/j.ijheatmasstransfer.2017.03.121)
  • Grahn, A.; Gommlich, A.; Kliem, S. et al.
    Simulation of an MSLB scenario using the 3D neutron kinetic core model Dyn3D coupled with the CFD software Trio U
    Nuclear Engineering and Design 315(2017), 117-127 (10.1016/j.nucengdes.2017.02.002)
  • Höhne, T.; Gasiunas, S.; Šeporaitis, M.
    Numerical Modelling of a Direct Contact Condensation Experiment using the AIAD Framework
    International Journal of Heat and Mass Transfer 111(2017), 211-222 (10.1016/j.ijheatmasstransfer.2017.03.104)