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research article

Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems

Mikityuk, K.
•
Coddington, P.
•
Pelloni, S.
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2007
Nuclear Technology

A consistent analytical comparison has been made of the transient behavior of critical and subcritical fast-spectrum reactor systems, the basic core design assumed in each case being that of the 80-MW(thermal) mixed-oxide-fueled, Pb-Bi-cooled, experimental accelerator driven system (XADS). The transient calculations were performed using the FAST code system developed at the Paul Scherrer Institute. The present study demonstrates a high level of self-protection of both the critical and subcritical systems over a wide range of postulated events, including transient overpower due to reactivity insertion, loss of flow, station blackout, loss of coolant, and core overcooling accidents. The relative advantages and shortcomings of the two system types, from the viewpoint of transient behavior, are discussed on the basis of the corresponding simulation results obtained.

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Type
research article
DOI
10.13182/NT07-A3799
Author(s)
Mikityuk, K.
•
Coddington, P.
•
Pelloni, S.
•
Bubelis, E.
•
Chawla, R.  
Date Issued

2007

Publisher

American Nucl. Soc.

Published in
Nuclear Technology
Volume

157

Issue

1

Start page

18

End page

36

Subjects

accelerator-based transmutation

•

fission reactor accidents

•

fission reactor coolants

•

fission reactor design

•

fission reactor fuel

•

reactivity (fission reactors)

Note

Lab. for Reactor Phys. Syst. Behaviour, Paul Scherrer Inst., Villigen, Switzerland

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/20.500.14299/53894
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