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research article

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

Petkevich, P.
•
Mikityuk, K.
•
Coddington, P.
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2007
Annals of Nuclear Energy

Several new fuel designs are currently being considered within the generation-IV gas-cooled fast reactor (GFR) project. One of them, which is the GFR reference design, is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinders. The fuel is mixed plutonium-uranium carbide, while the matrix material is silicon carbide. A two-dimensional approach to simulation of the thermal behaviour (for both steady-state and transient analysis) of such fuel, taking into account the inner heterogeneity, has been developed and benchmarked against detailed finite-element calculations. The resultant model can provide reliable fuel and matrix temperatures to determine neutronic feedbacks, as also to evaluate fuel integrity. As such, it has been integrated into PSIs coupled code system FAST, which aims at the comprehensive safety analysis of advanced fast reactor systems.[All rights reserved Elsevier].

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Type
research article
DOI
10.1016/j.anucene.2007.03.009
Web of Science ID

WOS:000250021300004

Author(s)
Petkevich, P.
Mikityuk, K.
Coddington, P.
Chawla, R.  
Date Issued

2007

Publisher

Elsevier Science Ltd.

Published in
Annals of Nuclear Energy
Volume

34

Issue

9

Start page

707

End page

18

Subjects

benchmark testing

•

finite element analysis

•

fission reactor fuel

•

fission reactor safety

Note

Paul Scherrer Inst., Villigen, Switzerland

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
LRS  
Available on Infoscience
September 17, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/53895
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