atw 2018-09v3

inforum

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

References

468

AMNT 2018 | YOUNG SCIENTISTS' WORKSHOP

| | Fig. 3-1.

Overview of whole Nodalisation of the IPR-R1 (left) and 13 core channels (right) generated by the software for input deck

generation.

Power

[kW]

| | Tab. 3-2.

Thermal hydraulic data IPR-R1.

Core inlet

temperature

(Position 3)

[°C]

Core outlet

temperature

(Position 3)

[°C]

There is good agreement between

the published RELAP calculations in

[REI2009] and the calculated ATHLET

data.

4 Summary

A new method based on a heuristic

approach for modelling selected

research reactor types in thermal

hydraulic analysis codes is presented.

This new approach allows a fast and

reliable generation of the input deck’s

fundamental elements despite limited

technical documentation. Focusing on

one MTR and one TRIGA design, the

main steps of developing process and

the characteristics of the new method

are highlighted. This includes the

Core inlet

temperature

(Position 8)

[°C]

Core outlet

temperature

(Position 3)

[°C]

Calculation 51 20.87 27.97 20.87 23.94

Reference

[REI2009]

50 20.95 26.95 22.95 24.95

abstraction and modularisation of

research reactor plant designs as well

as the conception of type-specific

nodalisation. At the end of this paper,

an exemplary MTR and TRIGA

research reactor is presented, generated

by the developed software.

Focusing on the stationary conditions,

there is a good agreement between

the calculated and experimental data.

This proves the basic functionality of

the developed modelling system by

generating a realistic plant model for

TRIGA and MTR type. In future work,

the nodalisation for both research reactor

designs will be reviewed and

tested against a range of safety transients

and accidents.

ABD2008A

ABD2008B

ABD2015

I.D. Abdelrazek, E.A. Villarino:

ETRR-2 Nuclear Reactor: Facility

Specification; Coordinated

Research Project on Innovative

Methods in Research Reactor

Analysis, organised by IAEA,

October 2008.

I.D. Abdelrazek, E.A. Villarino:

ETRR-2 Nuclear Reactor:

Experimental Results

Coordinated Research Project

on Innovative Methods in

Research Reactor Analysis, organised

by IAEA, October 2008.

I.D. Abdelrazek, et al.: Thermal

hydraulic analysis of ETRR-2

using RELAP5 code, Kerntechnik

80, 2015.

ATH2016 G. Lerchl et.al.: ATHLET 3.1A

User’s Manual, GRS-P-1/Vol.1,

Ref.7, March 2016.

IAEA2005

IAEA2016

IAEA2016B

REI2009

RRDB2018

Authors

IAEA: Research reactor

utilization, safety, decommissioning,

fuel and waste management,

ISBN 92-0-113904-7,

IAEA 2005.

IAEA: Safety of Research

Reactors, IAEA Safety Standards

Series No. SSR-3, Vienna

Austria, 2016, ISSN 1020-525X.

IAEA: History, development and

future of TRIGA research

reactors, Technical Report

Series No. 482, ISBN 978-92-0-

102016-1, IAEA 2016.

P. A. L. Resi, et al.: Assessment of

a RELAP5 model for the IPR-R1

TRIGA research reactor, International

Nuclear Atlantic

Conference – INAC 2009,

ISBN: 978-85-99141-03-8.

IAEA: Research Reactor

Database, Website URL:

https://nucleus.iaea.org/RRDB/

RR/ReactorSearch.aspx?rf=1

(01.02.2018).

Vera Koppers

Prof. Dr.-Ing. Marco K. Koch

Responsible Professor

Ruhr-Universität Bochum (RUB)

Universitätsstraße 150

44801 Bochum, Germany

| | Fig. 3-2.

Core inlet (left) and core outlet (right) temperature.

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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