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.

1.
Mikityuk
,
K.
,
Pelloni
,
S.
,
Coddington
,
P.
,
Bubelis
,
E.
, and
Chawla
,
R.
, 2005, “
FAST: An Advanced Code System for Fast Reactor Transient Analysis
,”
Ann. Nucl. Energy
0306-4549,
32
, pp.
1613
1631
.
2.
Doriath
,
J. Y.
,
McCallien
,
C.
,
Kiefhaber
,
E.
,
Wehmann
,
U.
, and
Rieunier
,
J. M.
, 1993, “
ERANOS 1: The Advanced European System of Codes for Reactor Physics Calculations
,”
Proceedings of the Joint Conference on Mathematical Methods and Supercomputing in Nuclear Applications
, Karlsruhe, Germany.
3.
Joo
,
H. G.
,
Barber
,
D. A.
,
Jiang
,
G.
, and
Downar
,
T. J.
, 1998, “
PARCS, A Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nonlinear Nodal Method
,”
Purdue University
Technical Report No. PU/NE-98-26.
4.
2007, “
Field Equations, Solution Methods, and Physical Models
,”
TRACE V5.0 Theory Manual
,
US Nuclear Regulatory Commission
,
Washington, DC
.
5.
Mikityuk
,
K.
, and
Fomitchenko
,
P.
, 2000, “
FRED: Calculational Model of Fuel Rod Behavior Under Accident Conditions Coupled With RELAP5/MOD3
,”
Proceedings of the Eighth International Conference on Nuclear Engineering (ICONE-8)
, Baltimore, MD.
6.
Krepel
,
J.
,
Pelloni
S.
,
Mikityuk
,
K.
, and
Coddington
P.
, 2009, “
EQL3D: ERANOS Based Equilibrium Fuel Cycle Procedure for Fast Reactors
,”
Ann. Nucl. Energy
0306-4549,
36
(
5
), pp.
550
561
.
7.
Krepel
,
J.
, and
Pelloni
,
S.
, 2008, “
Comparative Analysis of Equilibrium Cycle for Generation IV Fast-Reactors Using the EQL3D Procedure
,”
Proceedings of the PHYSOR‘08 International Conference
, Switzerland.
8.
Pelloni
,
S.
, and
Krepel
,
J.
, 2008, “
A New 3D Methodology for the Equilibrium Cycle and Its Application to a Large Helium-Cooled Fast Reactor
,”
Proceedings of PHYSOR ‘08 International Conference
, Switzerland.
9.
Krepel
,
J.
,
Pelloni
,
S.
, and
Mikityuk
,
K.
, 2008, “
Equilibrium Cycle Analysis of a Gas Cooled Fast Reactor With the EQL3D Procedure
,”
Proceedings of the PHYSOR ‘08 International Conference
, Switzerland.
10.
Krepel
,
J.
,
Mikityuk
,
K.
,
Sun
,
K.
, and
Rimpault
,
G.
, 2009, “
SFR Equilibrium Cycle Analysis With the EQL3D Procedure
,”
Proceedings of the ICAPP ‘09
, Tokyo, Japan.
11.
Krepel
,
J.
,
Sarotto
,
M.
,
Mikityuk
,
K.
, and
Artioli
,
C.
, 2009, “
EFIT Fuel Cycle Analysis With the EQL3D Procedure
,”
Proceedings of the ICAPP ‘09
, Tokyo, Japan.
12.
Pelloni
,
S.
,
Mikityuk
,
K.
, and
Epiney
,
A.
, 2009, “
A New Cross Section Generation Model in the FAST Code System and Its Application to the Gen-IV Gas-Cooled Fast Reactor
,”
Proceedings of the International Conference on Mathematics, Computational Methods and Reactor Physics (M&C 2009)
, Saratoga Springs, New York, May 3–7.
13.
Chenu
,
A.
,
Mikityuk
,
K.
, and
Chawla
,
R.
, 2009, “
Modeling of Sodium Two-Phase Flow With the TRACE Code
,”
Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17
, Brussels, Belgium, July 12–16.
14.
Mikityuk
,
K.
, 2009, “
Heat Transfer to Liquid Metal: Review of Data and Correlations for Tube Bundles
,”
Nucl. Eng. Des.
0029-5493,
239
(
4
), pp.
680
687
.
15.
Petkevich
,
P.
,
Mikityuk
,
K.
,
Coddington
,
P.
, and
Chawla
,
R.
, 2007, “
Development and Benchmarking of a 2D Transient Thermal Model for GFR Plate-Type Fuel
,”
Ann. Nucl. Energy
0306-4549,
34
, pp.
707
718
.
16.
Petkevich
,
P.
, 2008, “
Development and Application of an Advanced Fuel Model for the Safety Analysis of the Generation IV Gas-Cooled Fast Reactor
,” Ph.D. thesis, Ecole Polytechnique Fédérale de Lausanne, Switzerland.
17.
Martinelli
,
L.
,
Balbaud-Célérier
,
F.
,
Picard
,
G.
, and
Santarini
,
G.
, 2007, “
High-Temperature Oxidation of Fe-9Cr-1Mo Steel in Stagnant Liquid Lead-Bismuth at Different Temperatures
,”
Proceedings of the Fourth Workshop on Materials for HLM-Cooled Reactors and Related Technologies
, Sala Marconi—CNR Headquarters, Roma, Italy, May 21–23.
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