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PSR-0563 FEAST-METAL.

FEAST-METAL-V.1.0, Fuel Engineering and Structural analysis Tool

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1. NAME OR DESIGNATION OF PROGRAM:  FEAST-METAL-V.1.0
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
FEAST-METAL PSR-0563/01 Arrived 15-APR-2011

Machines used:

Package ID Orig. computer Test computer
PSR-0563/01 Linux-based PC,Macintosh,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

FEAST-METAL is a fuel performance code developed for predicting steady state and transient behavior of U-Pu-Zr metallic fuel alloys with stainless steel clad in sodium fast reactor environments.
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4. METHODS

The code currently adopts HT9 cladding properties. The code includes several physics based semi-empirical continuum level models to predict various important phenomena occurring under normal and off-normal scenarios. Details of the physical models can be found in references.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

Running times are extremely problem dependent. Sample problems required several hours.
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9. STATUS
Package ID Status date Status
PSR-0563/01 15-APR-2011 Masterfiled Arrived
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10. REFERENCES

- A. Karahan, "Modeling of Thermo-mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors," Ph. D. Thesis, Nuclear Science and Engineering Department, Massachusetts Institute of Technology, Cambridge, MA, (2009).
PSR-0563/01, included references:
- Aydin Karahan:
"FEAST-METAL VERSION-1 USER'S MANUAL" Center for Advanced Nuclear Energy
Systems, Massachusetts Institute of Technology, Cambridge MA (December, 2010).
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11. HARDWARE REQUIREMENTS:  PC, Mac or Workstation.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0563/01 FORTRAN-90
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13. SOFTWARE REQUIREMENTS

Package includes precompiled executables for Windows operating systems. OS X and Linux users will require a Fortran90 equivalent compiler.
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA

Developed by:   U.S. Nuclear Regulatory Commission, Washington, DC, USA
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16. MATERIAL AVAILABLE
PSR-0563/01
source code
precompiled executable for Windows systems
two test cases
documentation
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17. CATEGORIES
  • C. Static Design Studies
  • E. Space-Independent Kinetics
  • I. Deformation and Stress Distributions, Structural Analysis and Engineering Design Studies

Keywords: fuel management, spent fuel characterisation, structural safety analysis.