Sören Kliem

Dr. Sören Kliem

Reactor Safety Division, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rosendorf, D-01328 Dresden, Germany

Research Focus & Metrics

Academic Career Length

26Years (2001-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

View All Publications
1 May 2016 in Progress in Nuclear Energy
Verified
Journal Article
Closed access
URUlrich Rohde
Ulrich Rohde
Sören KliemSören Kliem
Sören Kliem
UGUlrich Grundmann
Ulrich Grundmann
SBSilvio Baier
Silvio Baier
YBYuri Bilodid
Yuri Bilodid
SMSiegfried Mittag
Siegfried Mittag

1 September 2007 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
URU. Rohde
U. Rohde
Thomas HöhneThomas Höhne
Thomas Höhne
Sören KliemSören Kliem
Sören Kliem
BHB. Hemström
B. Hemström
MSM. Scheuerer
M. Scheuerer
TDT. Dury
T. Dury

1 June 2006 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
Thomas HöhneThomas Höhne
Thomas Höhne
Sören KliemSören Kliem
Sören Kliem
UBUlrich Bieder
Ulrich Bieder

1 March 2008 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
Sören KliemSören Kliem
Sören Kliem
TST. Sühnel
T. Sühnel
URU. Rohde
U. Rohde
Thomas HöhneThomas Höhne
Thomas Höhne
HPH.-M. Prasser
H.-M. Prasser
FWF.-P. Weiss
F.-P. Weiss

1 July 2003 in Nuclear Technology
Verified
Journal Article
Closed access
HPHorst-Michael Prasser
Horst-Michael Prasser
GGGerhard Grunwald
Gerhard Grunwald
Thomas HöhneThomas Höhne
Thomas Höhne
Sören KliemSören Kliem
Sören Kliem
URUlrich Rohde
Ulrich Rohde
FWFrank-Peter Weiss
Frank-Peter Weiss
The reactor transient caused by a perturbation of boron concentration or coolant temperature at the inlet of a pressurized water reactor (PWR) depends on the mixing inside the reactor pressure vessel (RPV). Initial steep gradients are partially lessened by turbulent mixing with coolant from the unaffected loops and with the water inventory of the RPV. Nevertheless the assumption of an ideal mixing in the downcomer and the lower plenum of the reactor leads to unrealistically small reactivity inserts. The uncertainties between ideal mixing and total absence of mixing are too large to be acceptable for safety analyses. In reality, a partial mixing takes place. For realistic predictions it is necessary to study the mixing within the three-dimensional flow field in the complicated geometry of a PWR. For this purpose a 1:5 scaled model [the Rossendorf Coolant Mixing Model (ROCOM) facility] of the German PWR KONVOI was built. Compared to other experiments, the emphasis was put on extensive measuring inst...

1 October 2015 in Annals of Nuclear Energy
Verified
Journal Article
Open access
BCBruno Chanaron
Bruno Chanaron
CACarol Ahnert
Carol Ahnert
NCNicolas Crouzet
Nicolas Crouzet
Victor Hugo Sánchez EspinozaVictor Hugo Sánchez Espinoza
Victor Hugo Sánchez Espinoza
NKNikola Kolev
Nikola Kolev
APAngel Papukchiev
Angel Papukchiev
Since some years, there is a worldwide trend to move towards “higher-fidelity” simulation techniques in reactor analysis. One of the main objectives of the research in this area is to enhance the prediction capability of the computations used for safety demonstration of the current LWR nuclear power plants through the dynamic 3D coupling of the codes simulating the different physics of the problem into a common multi-physics simulation scheme. In this context, the NURESAFE European project aims at delivering to the European stakeholders an advanced and reliable software capacity usable for safety analysis needs of present and future LWR reactors and developing a high level of expertise in Europe in the proper use of the most recent simulation tools including uncertainty assessment to quantify the margins toward feared phenomena occurring during an accident. This software capacity is based on the NURESIM European simulation platform created during FP6 NURESIM project which includes advanced core physics, two-phase thermal–hydraulics, fuel modeling and multi-scale and multi-physics features together with sensitivity and uncertainty tools. These physics are fully integrated into the platform in order to provide a standardized state-of-the-art code system to support safety analysis of current and evolving LWRs