TORT-TD/ATTICA3D: A Coupled Neutron Transport and Thermalhydraulics Code System for 3-D Transient Analysis of Gas Cooled High Temperature Reactors
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
D8-3 Multi-scale multi-physics couplings; Multiphysics applications to new generation reactors

Authors:
J. Lapins (Institut für Kernenergetik und Energiesysteme, Universität Stuttgart)
A. Seubert (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)
M. Buck (Institut für Kernenergetik und Energiesysteme, Universität Stuttgart)
J. Bader (EnBW Kernkraft GmbH)
E. Laurien (Institut für Kernenergetik und Energiesysteme, Universität Stuttgart)
  

Abstract

In this paper, the physical models and calculation capabilities of TORT-TD and ATTICA3D are presented, focusing on model improvements in ATTICA3D and extensions made in TORT-TD related to HTR application. For first applications, the OECD/NEA/NSC PBMR-400 benchmark has been chosen. Results obtained with TORT-TD/ATTICA3D will be shown for transient exercises, e.g. control rod withdrawal and a control rod ejection. Results are compared to other benchmark participants’ solutions with special focus on fuel temperature modelling features of ATTICA3D. The provided “grey-curtain” nuclear cross section libraries have been used. First results on 3-D effects during a control rod withdrawal transient will be presented.

Comprehensive safety studies of high temperature gas cooled reactors (HTR) require full three dimensional coupled treatments of both neutron kinetics and thermal-hydraulics. In a common effort, GRS and IKE developed the coupled code system TORT-TD/ATTICA3D for pebble bed type HTR that connects the 3-D transient discrete-ordinates transport code TORT-TD with the 3-D porous medium thermal-hydraulics code ATTICA3D.

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