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research article

FAST: An advanced code system for fast reactor transient analysis

Mikityuk, K.
•
Pelloni, S.
•
Coddington, P.
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2005
Annals of Nuclear Energy

One of the main goals of the FAST project at PSI is to establish a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants. Both static and transient core physics, as well as the behaviour and safety of the power plant as a whole, are studied. The paper discusses the structure of the code system, including the organisation of the interfaces and data exchange. Examples of validation and application of the individual programs, as well as of the complete code system, are provided using studies carried out within the context of designs for experimental accelerator-driven, fast-spectrum systems. [All rights reserved Elsevier]

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Type
research article
DOI
10.1016/j.anucene.2005.06.002
Web of Science ID

WOS:000232810200001

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

2005

Publisher

Elsevier

Published in
Annals of Nuclear Energy
Volume

32

Issue

15

Start page

1613

End page

31

Subjects

fission reactor coolants

•

fission reactor core control

•

fission reactor physics

•

fission reactor safety

•

nuclear engineering computing

•

nuclear power stations

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/20.500.14299/53867
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