Contact

Dr. Sören Kliem

Head
Reactor Safety
s.kliemAthzdr.de
Phone: +49 351 260 2318

Department of Reactor Safety


Research

Neutron physics and reactor dynamics


  • Validation and application to light water reactors and innovative reactor concepts of the Monte Carlo code SERPENT2
  • Application of the deterministic lattice code HELIOS-2
  • Development, verification and application of the in-house reactor dynamics code DYN3D
  • Extension of the DYN3D code to innovative reactor concepts
  • Coupling of DYN3D to the system code ATHLET
  • Coupling of DYN3D to the Computational Fluid Dynamics codes ANSYS CFX and TRIO_U

Plant dynamics and severe accident analysis

  • Accident analysis and analysis of plant dynamics using the ATHLET system code
  • Assessment of the impact of severe accident management measures on the progression of severe accidents in PWRs and VVERs

Monte-Carlo simulations (n- / γ-field calculations)


  • Development of the in house Monte Carlo code TRAMO
  • Fluence calculations of the of the reactor pressure vessel and internals using MCNP and TRAMO
 


Latest Publication

Advances from R2CA project on reactor simulations for burst rod number evaluation during LOCA

Belon, S. B.; Ederli, S.; Jobst, M.

Abstract

In the frame of the “Reduction of Radiological Consequences of design basis and extension accidents” European Union’s Horizon 2020 project, a specific effort was focused on the update and the development of methodologies to assess the radiological consequences of loss-of-coolant accidents. Evaluation of the radiological consequences associated to this accident is strongly linked to the prediction of the rod burst ratio and new approaches were investigated through research and development associated to accident simulation software. Complementarily to approaches chaining system thermalhydraulic simulation to fuel performance code, approaches with integral codes ASTEC, DRACCAR and ATHLET-CD were developed respectively by ENEA, IRSN and HZDR. These applications were demonstrated on LOCA simulation for PWR and highlighted the capabilities of the tools. The ASTEC PWR model was extended by ENEA, which proposes a 2D core model with an increased number of representative fuel rods. HZDR and IRSN proposes approaches based on 3D core model which are able to capture distinctive fuel assembly responses and predict the rod burst ratio according to the distribution of rod behaviors within the core. This work highlighted several possible core models to predict the rod burst ratio and which can be used in integral tools abled to couple thermal hydraulics and thermomechanics. Advanced core models simulating the thermomechanical response of several representative rods per fuel assemblies and using 3D thermal hydraulics model are recommended due to the heterogeneities on power distribution, which impacts flow distribution. The need to model RPV in 3D was underlined by ATHLET-CD large break loss-of-coolant demonstrative case, which exhibits non-symmetric core heat-up.
In addition, demonstrative cases proposed by ENEA and IRSN compared predictions obtained with the specific burst criteria developed in the frame of R2CA project and more classical one devoted to the core coolability assessment. The strong sensitivity of the rod burst ratio prediction to the burst criteria was highlighted. The need to handle uncertainties within a global methodology for rod burst ratio evaluation was underlined.
Finally, throughout the development of loss-of-coolant accident applications with ASTEC, DRACCAR and ATHLET-CD, some prospects of development were identified for the codes and should bring advances for LOCA simulation and RBR predictions.

Permalink: https://www.hzdr.de/publications/Publ-37989


More publications


Team

Foto: Gruppenbild der Abteilung

Head

NameBld./Office+49 351 260Email
Dr. Sören Kliem250/1082318
s.kliemAthzdr.de

Employees

NameBld./Office+49 351 260Email
Dr. Silvio Baier250/1113034
s.baierAthzdr.de
Dr. Yurii Bilodid250/2092020
y.bilodidAthzdr.de
Dr. Emil Fridman250/2092167
e.fridmanAthzdr.de
Jörg Konheiser250/1092416
j.konheiserAthzdr.de
Kerstin Kurde250/1073025
k.kurdeAthzdr.de
Dr. Evgeny Nikitin250/2072906
e.nikitinAthzdr.de
Dr. Frank Schäfer250/1172069
f.schaeferAthzdr.de