Implementation of a fast running full core pin power reconstruction method in DYN3D
Creators
- 1. Instituto Nacional de Investigaciones Nucleares, Department of Nuclear Systems, Carretera Mexico – Toluca s/n, La Marquesa, 52750 Ocoyoacac (Mexico)
- 2. Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Hermann-vom-Helmhotz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)
- 3. Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstraße 400, 01328 Dresden (Germany)
Description
Highlights: • New pin power reconstruction (PPR) method for the nodal diffusion code DYN3D. • Flexible PPR method applicable to a single, a group or to all fuel assemblies (square, hex). • Combination of nodal with pin-wise solutions (non-conform geometry). • PPR capabilities shown for REA of a Minicore (REA) PWR whole core. - Abstract: This paper presents a substantial extension of the pin power reconstruction (PPR) method used in the reactor dynamics code DYN3D with the aim to better describe the heterogeneity within the fuel assembly during reactor simulations. The flexibility of the new implemented PPR permits the local spatial refinement of one fuel assembly, of a cluster of fuel assemblies, of a quarter or eight of a core or even of a whole core. The application of PPR in core regions of interest will pave the way for the coupling with sub-channel codes enabling the prediction of local safety parameters. One of the main advantages of considering regions and not only a hot fuel assembly (FA) is the fact that the cross flow within this region can be taken into account by the subchannel code. The implementation of the new PPR method has been tested analysing a rod ejection accident (REA) in a PWR minicore consisting of 3 × 3 FA. Finally, the new capabilities of DNY3D are demonstrated by the analysing a boron dilution transient in a PWR MOX core and the pin power of a VVER-1000 reactor at stationary conditions
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2014.04.028Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2014.04.028;
- PII
- S0029-5493(14)00253-2;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 274
- Journal Page Range
- p. 44-55
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46023394
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BORON; DILUTION; FUEL ASSEMBLIES; MATHEMATICAL SOLUTIONS; NEUTRON DIFFUSION EQUATION; NODAL EXPANSION METHOD; REACTOR KINETICS; REACTOR SAFETY; ROD EJECTION ACCIDENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EQUATIONS; KINETICS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SEMIMETALS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.