Comparison of square and hexagonal fuel lattices for high conversion PWRs
-
D. Kotlyar
and E. Shwageraus
Abstract
This paper reports on an investigation into fuel design choices of a pressurized water reactor operating in a self-sustainable Th-233U fuel cycle. In order to evaluate feasibility of this concept, two types of fuel assembly lattices were considered: square and hexagonal. The hexagonal lattice may offer some advantages over the square one. For example, the fertile blanket fuel can be packed more tightly reducing the blanket volume fraction in the core and potentially allowing to achieve higher core average power density. The calculations were carried out with Monte-Carlo based BGCore code system and the results were compared to those obtained with Serpent Monte-Carlo code and deterministic transport code BOXER. One of the major design challenges associated with the SB concept is high power peaking due to the high concentration of fissile material in the seed region. The second objective of this work is to estimate the maximum achievable core power density by evaluation of limiting thermal hydraulic parameters. The analysis showed that both fuel assembly designs have a potential of achieving net breeding. Although hexagonal lattice was found to be somewhat more favorable because it allows achieving higher power density, while having breeding performance comparable to the square lattice case.
Kurzfassung
In diesem Beitrag werden Untersuchungen zur Auswahl verschiedener Brennelementanordnungen für DWR mit Th233-U Brennstoffkreislauf untersucht. Dabei wurde die Realisierbarkeit einer quadratischen und einer hexagonalen Anordnung der Brennelemente verglichen. Hexagonale Anordnungen zeichnen sich durch eine mögliche höhere Packungsdichte des Brutmaterials im Kern und damit durch eine höhere mittlere Leistungsdichte aus im Vergleich zu quadratischen Anordnungen. Die Berechnungen wurden mit dem auf der Monte-Carlo Methode basierenden Programmsystem BGCore, dem Serpent Monte-Carlo Programm und dem deterministischen Transportcode BOXER durchgeführt und miteinander verglichen. Hohe Leistungspeaks infolge der hohen Konzentration von spaltbarem Material in der Brutzone sind eine wesentliche Herausforderung an die DWR-Konzepte mit Th233-U Brennstoffkreisläufen. Ein weiteres Ziel der Berechnungen war die Bestimmung dieser Leistungspeaks und die Berechnung der maximal möglichen Kernleistungsdichte unter Beachtung der limitierenden thermohydraulischen Parameter. Die Analysen zeigten, dass in beiden Brennstabanordnungen positive Brutraten erzielt werden können. Die hexagonale Anordnung wird derzeit etwas mehr favorisiert, weil für diese höhere Leistungsdichten bei im Vergleich zur quadratischen Anordnung vergleichbaren Brutraten erzielt werden können.
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© 2012, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – Selected contributions to the XXIst Symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Development of multi-group spectral code TVS-M
- Qualification of the APOLLO2 lattice physics code of the NURISP platform for VVER hexagonal lattices
- The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D
- An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies
- Studies on boiling water reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG
- Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
- Analysis of coolant flow in central tube of VVER-440 fuel assemblies
- Effect of spacer grid mixing vanes on coolant outlet temperature distribution
- Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
- Assessment of spectral history influence on PWR and WWER core
- New practice for the evaluation of rod efficiency measurement by rod drop at the NPP Paks
- Comparison of square and hexagonal fuel lattices for high conversion PWRs
- VVER-440 with inert matrix fuel – viable direction to sustainability
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – Selected contributions to the XXIst Symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Development of multi-group spectral code TVS-M
- Qualification of the APOLLO2 lattice physics code of the NURISP platform for VVER hexagonal lattices
- The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D
- An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies
- Studies on boiling water reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG
- Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
- Analysis of coolant flow in central tube of VVER-440 fuel assemblies
- Effect of spacer grid mixing vanes on coolant outlet temperature distribution
- Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
- Assessment of spectral history influence on PWR and WWER core
- New practice for the evaluation of rod efficiency measurement by rod drop at the NPP Paks
- Comparison of square and hexagonal fuel lattices for high conversion PWRs
- VVER-440 with inert matrix fuel – viable direction to sustainability