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  4. Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
 
research article

Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code

Romano, A.
•
Wallin, H.
•
Zimmermann, M. A.
Show more
2006
Nuclear Engineering and Design

An improved version of the FALCON fuel performance code is used to model the thermal-mechanical behaviour of the test rod in the CABRI high-burnup RIA test CIP0-1. First, the original FALCON code (version MOD01) is modified by introducing new routines yielding a better description of the initial fuel and clad geometry, which allows the modelling of highly oxidized claddings with non-uniform axial oxide thicknesses. By calculating the Hoop strain exerted by the oxide layer on the cladding, the correct initial relative position between inner and fuel clad outer surfaces is obtained. Application of the new algorithm to the REP-NA4 experiment and comparison with the previous code results shows that the new version yields better predictions of the final clad outer diameter profile. The new code version is then employed to predict the thermal-mechanical behaviour of the CIP0-1 test rod. The measured clad diametral deformation, clad elongation and coolant temperature are taken as figures of merit, the code calculations being compared against these. The agreement between code calculations and measurements is remarkable: (a) the final clad diameter profile is correctly predicted, provided that the transient oxide spalling is taken into account; (b) the clad elongation is satisfactorily reproduced if a bonded cladding and large axial friction factors are assumed; and (c) the coolant temperatures at different axial locations are generally overpredicted, but can be satisfactorily reproduced if the thermal inertia of the thermocouple is considered. [All rights reserved Elsevier]

  • Details
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Type
research article
DOI
10.1016/j.nucengdes.2005.08.007
Web of Science ID

WOS:000236986700006

Author(s)
Romano, A.
Wallin, H.
Zimmermann, M. A.
Chawla, R.  
Date Issued

2006

Publisher

Elsevier

Published in
Nuclear Engineering and Design
Volume

236

Issue

3

Start page

284

End page

94

Subjects

fission reactor coolants

•

fission reactor cooling

•

fission reactor fuel

•

fission reactor fuel claddings

•

fission reactor instrumentation

•

nuclear engineering computing

•

thermocouples

Note

Lab. for Reactor Phys. Syst. Behaviour, 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/20.500.14299/53884
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