The time-dependent 3D discrete ordinates code TORT-TD with thermal-hydraulic feedback by ATHLET models
Creators
- 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Forschungsinstitute, D-85748 Garching (Germany)
Description
This paper describes the time-dependent 3D discrete ordinates transport code TORT-TD. Thermal-hydraulic feedback is considered by coupling TORT-TD with the thermal-hydraulics system code ATHLET. The coupled code TORT-TD/ATHLET allows 3D pin-by-pin analyses of transients in few energy groups and anisotropic scattering by solving the time-dependent transport equation using the unconditionally stable implicit method. The nuclear cross sections are interpolated between pre-calculated table values of fuel temperature, moderator density and boron concentration. For verification of the implementation, selected test cases have been calculated by TORT-TD/ATHLET. They include a control rod ejection transient in a small PWR fuel assembly arrangement and a local boron concentration change in a single PWR fuel assembly. In the latter, special attention has been paid to study the influence of the thermal-hydraulic feedback modelling in ATHLET. The results obtained for a control rod ejection accident in a PWR quarter core demonstrate the applicability of TORT-TD/ATHLET. (authors)
Additional details
Publishing Information
- Publisher
- Paul Scherrer Institut - PSI
- Imprint Place
- Villigen PSI (Switzerland)
- ISBN
- 978-3-9521409-5-6
- Imprint Pagination
- 9 p.
Conference
- Title
- International Conference on the Physics of Reactors 'Nuclear Power: A Sustainable Resource'
- Acronym
- PHYSOR'08
- Dates
- 14-19 Sep 2008
- Place
- Interlaken (Switzerland)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- France
- INIS RN
- 41116104
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; BORON; CONTROL ELEMENTS; CROSS SECTIONS; DISCRETE ORDINATE METHOD; FEEDBACK; FUEL ASSEMBLIES; PWR TYPE REACTORS; REACTOR CORES; SIMULATION; THERMAL HYDRAULICS; TIME DEPENDENCE; TRANSIENTS; TRANSPORT THEORY
- Descriptors DEC
- CALCULATION METHODS; ELEMENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.; proceedings are available as a CD-ROM on request to info'at'physor08.ch