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research article

FAST code system: Review of recent developments and near-future plans

Mikityuk, Konstantin
•
Krepel, Jiri
•
Pelloni, Sandro
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2010
Journal of Engineering for Gas Turbines and Power

The FAST code system is currently being developed and used at the Paul Scherrer Institut for static and transient analysis of the main Generation 4 fast-spectrum reactor concepts: sodium-, helium-, and gas-cooled fast reactors. The code system includes the ERANOS code system for static neutronics calculations, as well as coupled TRACE/PARCS/FRED for neutron kinetics, thermal hydraulic, and fuel transient analysis. The paper presents the status of the recent developments in neutronics (new 3D procedure for equilibrium cycle simulation and new transient cross section generation procedure), in thermal hydraulics and chemistry (equations-of-state for new coolants, two-phase flow models for sodium, and new model for oxide layer buildup in heavy-metal flow), and in fuel behavior (new model for the dispersed gas-cooled fast reactor fuel). Near-future plans for the further development of FAST are outlined. 2010 by ASME.

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Type
research article
DOI
10.1115/1.4000336
Web of Science ID

WOS:000280000100015

Author(s)
Mikityuk, Konstantin
Krepel, Jiri
Pelloni, Sandro
Chenu, Aurelia  
Petkevich, Petr
Chawla, Rakesh  
Date Issued

2010

Publisher

American Society of Mechanical Engineers

Published in
Journal of Engineering for Gas Turbines and Power
Volume

132

Issue

10

Start page

1

End page

7

Subjects

Transient analysis

•

Fast reactors

•

Helium

•

Hydraulics

•

Multiphase flow

•

Nuclear fuels

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Sodium

•

Three dimensional

Note

Paul Scherrer Institut (PSI), Villigen 5232, 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/20.500.14299/53921
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