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Title: 3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D

Abstract

As most of the acceptance criteria are local core parameters, application of transient 3-D fine mesh neutron transport and thermal hydraulics coupled codes is mandatory for best estimate evaluations of safety margins. This also applies to high-temperature gas cooled reactors (HTGR). Application of 3-D fine-mesh transient transport codes using few energy groups coupled with 3-D thermal hydraulics codes becomes feasible in view of increasing computing power. This paper describes the discrete ordinates based coupled code system TORT-TD/ATTICA3D that has recently been extended by a fine-mesh diffusion solver. Based on transient analyses for the PBMR-400 design, the transport/diffusion capabilities are demonstrated and 3-D local flux and power redistribution effects during a partial control rod withdrawal are shown. (authors)

Authors:
;  [1]; ;  [2];  [2];  [3];  [2]
  1. Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS MbH, Forschungszentrum, D-85748 Garching (Germany)
  2. Institut fuer Kernenergetik und Energiesysteme IKE, Universitaet Stuttgart, Pfaffenwaldring 31, D-70569 Stuttgart (Germany)
  3. (Germany)
Publication Date:
Research Org.:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
OSTI Identifier:
22105874
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 10 refs.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 97 MATHEMATICAL METHODS AND COMPUTING; COMPUTER CODES; CONTROL ELEMENTS; DESIGN; DISCRETE ORDINATE METHOD; HTGR TYPE REACTORS; NEUTRON TRANSPORT; PEBBLE BED REACTORS; POROUS MATERIALS; POWER DISTRIBUTION; SAFETY MARGINS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; TRANSIENTS

Citation Formats

Seubert, A., Sureda, A., Lapins, J., Buck, M., Bader, J., EnBW Kernkraft GmbH, Kernkraftwerk Philippsburg, Rheinschanzinsel, D-76661 Philippsburg, and Laurien, E. 3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D. United States: N. p., 2012. Web.
Seubert, A., Sureda, A., Lapins, J., Buck, M., Bader, J., EnBW Kernkraft GmbH, Kernkraftwerk Philippsburg, Rheinschanzinsel, D-76661 Philippsburg, & Laurien, E. 3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D. United States.
Seubert, A., Sureda, A., Lapins, J., Buck, M., Bader, J., EnBW Kernkraft GmbH, Kernkraftwerk Philippsburg, Rheinschanzinsel, D-76661 Philippsburg, and Laurien, E. Sun . "3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D". United States.
@article{osti_22105874,
title = {3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D},
author = {Seubert, A. and Sureda, A. and Lapins, J. and Buck, M. and Bader, J. and EnBW Kernkraft GmbH, Kernkraftwerk Philippsburg, Rheinschanzinsel, D-76661 Philippsburg and Laurien, E.},
abstractNote = {As most of the acceptance criteria are local core parameters, application of transient 3-D fine mesh neutron transport and thermal hydraulics coupled codes is mandatory for best estimate evaluations of safety margins. This also applies to high-temperature gas cooled reactors (HTGR). Application of 3-D fine-mesh transient transport codes using few energy groups coupled with 3-D thermal hydraulics codes becomes feasible in view of increasing computing power. This paper describes the discrete ordinates based coupled code system TORT-TD/ATTICA3D that has recently been extended by a fine-mesh diffusion solver. Based on transient analyses for the PBMR-400 design, the transport/diffusion capabilities are demonstrated and 3-D local flux and power redistribution effects during a partial control rod withdrawal are shown. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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