Research Papers: Nuclear Power

FAST Code System: Review of Recent Developments and Near-Future Plans

[+] Author and Article Information
Konstantin Mikityuk

 Paul Scherrer Institut (PSI), Villigen 5232, Switzerlandkonstantin.mikityuk@psi.ch

Jiri Krepel, Sandro Pelloni

 Paul Scherrer Institut (PSI), Villigen 5232, Switzerland

Aurelia Chenu, Petr Petkevich, Rakesh Chawla

 Paul Scherrer Institut (PSI), Villigen 5232, Switzerland;Ecole Polytechnique Fédérale de Lausanne (EPFL), 1015 Lausanne, Switzerland

J. Eng. Gas Turbines Power 132(10), 102915 (Jul 08, 2010) (7 pages) doi:10.1115/1.4000336 History: Received July 17, 2009; Revised July 20, 2009; Published July 08, 2010; Online July 08, 2010

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.

Copyright © 2010 by American Society of Mechanical Engineers
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Figure 1

FAST code system flowchart

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Figure 2

Illustration of complex reloading patterns for a GFR core within a closed multibatch cycle

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Figure 3

Chart of the actinides flow within EQL3D

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Figure 4

Reactivity evolution for three different batch reloading patterns during the first two cycles (six batches) of the GFR open cycle operation

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Figure 5

Comparison of the Doppler constant for SFR, GFR, and LFR cores and for nominal and voided conditions (residence time: GFR and LFR 2493, and SFR 2040 EFPD)

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Figure 6

GFR reactor power in transient with inlet coolant temperature reduction: comparison of different cross section generation models

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Figure 7

Simplified diagram of the KNS sodium boiling loop

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Figure 8

Measured and calculated axial sodium temperature profiles: (a) steady state and (b) just before boiling

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Figure 9

Database: Nusselt number versus Peclet number

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Figure 10

Predictions of the Nusselt number calculated by the new correlation versus the experimental data for liquid metal flow in tube bundles

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Figure 11

Diagram of the main variables and phenomena taken into account by the model

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Figure 12

Predictions of oxide layer growth rate versus test data for stagnant lead-bismuth eutectics at 470°C(17)

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Figure 13

Comparison of measured versus calculated results for the oxide layer thickness for different test data

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Figure 14

GFR (a) fuel element (plate) and (b) fuel assembly

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Figure 15

ANSYS model of the GFR fuel cell used for benchmarking: (a) simulated sector and (b) isometric view

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Figure 16

Comparison of the temperature field along the GFR fuel cell axis (2D model versus ANSYS )



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