atw 2018-09v3


atw Vol. 63 (2018) | Issue 8/9 ı August/September



| | Award winners, sponsors and jury of the 49 th Annual Meeting on Nuclear Technology (AMNT 2018)

Young Scientists Workshop: (from left): Dr. Wolfgang Steinwarz, Prof. Dr. Marco K. Koch (Ruhr-Universität

Bochum), Dr. Katharina Stummeyer (Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH),

Vera Koppers, Winner of the 2018 Young Scientists' Award, Dr. Jens Schröder (GNS Gesellschaft für

Nuklear- Service mbH), Katharina Amend (2 nd ranked young scientist), Prof. Dr. Jörg Starflinger

( Universität Stuttgart), María Freiría López 3 rd ranked young scientist.

several different sections, each of

them modelled separately with

different correlations. A comparison

with experimental data showed fairly

reasonable results which are subject

for improvement as a next step.

Tobias Jankowski (Ruhr-Universität

Bochum, mentoring: Prof. Koch) reported

about Development and

Validation of a Correlation for

Droplet Re-Entrainment Estimation

from Liquid Pools. The correlation is

based on a dimensional analysis and

therefore considers thermohydraulic

boundary conditions by dimensionless

quantities, which are quantified

by empirical constants. These constants

are obtained by four nearly

steady test phases, taken from two

experimental facilities of different

scale. The correlation results are in a

good agreement with experimental


The presentation entitled Comparison

of Different Wash-off

Models for Fission Products on

Containment Walls was given by

Katharina Amend (Universität der

Bundeswehr München, mentoring:

Prof. Klein). A parameter variation

was conducted with in the setting of a

simplified geometry and with the

geometry of the laboratory tests. One

key influencing parameter for the

resulting washed off mass is the

percentage of area covered by water

in each case, which differs with

­inclination and mass flow rate. First

simulations with the laboratory

geometry show satisfactory agreement,

when compared to the experiments.

Moritz Schenk (Karlsruhe Institute

of Technology (KIT), mentoring: Prof.

Cheng) gave a presentation about CFD

Analysis of centrifugal Liquid Metal

Pumps. Using the open-source software

OpenFOAM the influence of the

physical properties of liquid metals on

the performance of a pump impeller

and on the flow field is investigated.

In general, the simulations show a

­relatively strong negative influence on

head and efficiency for much higher

viscosities and nearly no effect for

lower viscosities compared to water.

This qualitative behaviour is in good

agreement with the literature. The

optimization of the liquid metal pump

is ongoing, focussing on the corrosion

potential of the liquid metal.

Summarizing, the scientific quality

of papers presented by the young

scientists in this year reached again

a very high level. Therefore, all participants

of the workshop should get

honourable recognition.

The jury awarded Vera Koppers

(Gesellschaft für Anlagen- und Reaktorsicherheit

(GRS) gGmbH) the 1 st price

of the 2018 competition. Her compact

as well as those of both the 2 nd ranked

author, Katharina Amend (Universität

der Bundeswehr München) and the 3 rd

ranked author Maria Freiria (Universität

Stuttgart) are published in this

issue of atw – nucmag.


Prof. Dr.-Ing. Jörg Starflinger

Institute of Nuclear Technology

and Energy Systems (IKE)

Pfaffenwaldring 31

70569 Stuttgart, Germany





Vera Koppers was

awarded with the

1 st price of the 49 th

Annual Meeting on

Nuclear Technology

(AMNT 2018) Young

Scientists' Workshop.

Heuristic Methods in Modelling

Research Reactors for Deterministic

Safety Analysis

Vera Koppers and Marco K. Koch

1 Introduction The national and international fundamental nuclear safety objective is to protect the public

from ionising radiation [IAEA2016]. Although research reactors may have a smaller risk potential to the public than

nuclear power plants, operators and researchers are at a higher risk [IAEA2016]. Deterministic safety analyses using

thermal-hydraulic system codes are a prevalent and important instrument to evaluate the safety of nuclear power plants

and research reactors. A wide range of safety analysis codes that are used for simulations of nuclear power plants are

applicable to simulations of research reactors. The application range of the thermal-hydraulic system code ATHLET

(Analysis of thermal-hydraulics of leaks and transients) – developed by GRS (Gesellschaft für Anlagen- und Reaktorsicherheit

gGmbH) – was extended to simulated subcooled nucleate boiling processes at low pressure in 1994 [GRS2009].

AMNT 2018 | Young Scientists' Workshop

Heuristic Methods in Modelling Research Reactors for Deterministic Safety Analysis ı Vera Koppers and Marco K. Koch

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