3-D transient analysis of pebble-bed HTGR by TORT-TD/ATTICA3D
- Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS MbH, Forschungszentrum, D-85748 Garching (Germany)
- Institut fuer Kernenergetik und Energiesysteme IKE, Universitaet Stuttgart, Pfaffenwaldring 31, D-70569 Stuttgart (Germany)
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)
- Research Organization:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
- OSTI ID:
- 22105874
- 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
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Related Subjects
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