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research article

Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems

Mikityuk, K.
•
Coddington, P.
•
Bubelis, E.
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2006
Nuclear Engineering and Design

The paper presents a comparison of transient calculations for two 80-MWt MOX-fuelled experimental accelerator-driven systems (XADS), one cooled by lead-bismuth eutectic and the other by helium. The results for protected (with accelerator beam trip) and unprotected (without accelerator beam trip) transient overpower, spurious beam trip, loss of flow, loss of heat sink, and loss of coolant accidents, as well as the failure of heat exchanger tubes, are analysed for the two systems. The analysis was performed using TRAC/AAA, which is part of the PSI FAST code system. The advantages and shortcomings of the two designs from the viewpoint of their transient behaviour are discussed. [All rights reserved Elsevier]

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Type
research article
DOI
10.1016/j.nucengdes.2006.03.012
Web of Science ID

WOS:000241899800005

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

2006

Publisher

Elsevier

Published in
Nuclear Engineering and Design
Volume

236

Issue

23

Start page

2452

End page

73

Subjects

fission reactor coolants

•

fission reactor cooling

•

fission reactor fuel claddings

•

fission reactor safety

•

nuclear engineering computing

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/20.500.14299/53880
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