Abstract
In this paper, we present a novel, lightweight fuel
behavior code, FINIX. FINIX provides an advanced
description of the nuclear fuel rod for non-fuel-specific
codes, such as reactor physics, thermal hydraulics and
system codes, allowing realistic modeling of the thermal
and mechanical behavior of the fuel during transients.
FINIX can be implemented within the main code on a source
code level, and includes a high-level interface for
accessing the fuel behavior model with minimal knowledge
of its internal implementation. The interface also
reduces the need for modifying the main code even when
the internal FINIX models are significantly updated,
allowing simultaneous code development and integration.
In addition to FINIX, we are developing a method for
initializing the model for accumulated burn-up. The basis
of the method is described in this paper. We also present
initial results calculated both with the stand-alone
version of FINIX, and as an integrated part of the Monte
Carlo reactor physics code Serpent
Original language | English |
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Title of host publication | Proceedings of LWR Fuel Performance Meeting TopFuel 2013 |
Publisher | American Nuclear Society (ANS) |
Pages | 726-733 |
ISBN (Print) | 978-0-89448-701-9 |
Publication status | Published - 2013 |
MoE publication type | A4 Article in a conference publication |
Event | LWR Fuel Performance Meeting, Top Fuel 2013 - Charlotte, NC, United States Duration: 15 Sept 2013 → 19 Sept 2013 |
Conference
Conference | LWR Fuel Performance Meeting, Top Fuel 2013 |
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Country/Territory | United States |
City | Charlotte, NC |
Period | 15/09/13 → 19/09/13 |
Keywords
- FINIX
- fuel behaviour modelling
- multiphysics
- nuclear fuel