Computer Programs
NEA-0684 SSYST-2.
last modified: 21-MAY-1987 | catalog | categories | new | search |

NEA-0684 SSYST-2.

SSYST, Modular System for Transient Fuel Rod Behaviour Under Accident Condition

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1. NAME OR DESIGNATION OF PROGRAM:  SSYST-2.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
SSYST-3 NEA-0684/06 Tested 21-MAY-1987

Machines used:

Package ID Orig. computer Test computer
NEA-0684/06 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION

SSYST is a code system for analyzing transient fuel rod behaviour under off-normal conditions,  developed jointly by the Institut fuer Kernenergetik und Energie- systeme (IKE), Stuttgart, and Kernforschungszentrum Karlsruhe (KfK)  under contract for the Projekt Nukleare Sicherheit (PNS) at KfK. Main differences versus codes with similar applications are:

   (1) an open-ended modular code organisation
   (2) a preference for simple models, wherever possible.

While feature (1) makes SSYST a very flexible tool, easily adapted to changing requirements, feature (2) leads to short execution times. The analysis of transient rod behaviour under LOCA boundary conditions takes 2 minutes CPU time on IBM 3033, so that extensive parametric studies are feasible.

Main differences between SSYST-3 and previous versions are related to a general clean-up of the code system, which reduces the implementation effort:
- advanced modules for cladding deformation and oxidation and   reflooding conditions are included;
- an input processor thoroughly checks all input data.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

The analysis of transient rod behaviour under LOCA conditions takes 2 minutes of CPU time on IBM 3081.
NEA-0684/06
The sample problems supplied with the package each take under 9 seconds of CPU time on IBM 3084.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-0684/06 21-MAY-1987 Tested at NEADB
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10. REFERENCES

- S. Raff: Report KfK 3184 (1982)
- S. Raff, R. Meyder:
  "NORA-2, A Model for Creep Deformation and Rupture of Zircaloy at
   High Temperatures"
  in:
  J. Grittus, Ed.
  "Water Reactor Fuel Element Performance Computer Modelling"
  Applied Science Publ., Barking 1983
- "A Probabilistic SSYST-3 Analysis of a PWR Large Break LOCA"
  KfK 3873 (to be published). In German
- E.J. Kersting:
  "Code REFLOS, A Program for Refill and Reflood Calculations"
  GRS-A-163 (September 1978) In German
NEA-0684/06, included references:
- R. Meyder:
  "SSYST-3, Input Description and Handling"
  KfK 3654 (December 1983). In German
- H. Borgwaldt, W. Gulden:
  "SSYST, A Code System for Analysing Transient LWR Fuel Rod
  Behaviour Under Off-Normal Conditions"
  KfK 3359 (June 1982)
- H. Borgwaldt, et al.:
  "The Code System SSYST, Present Status and Current Development"
  Paper submitted to the Technical Committee/Workshop on the IAEA
  Programme in the Use of Computer Codes for Safety Analysis,
  Varna, Bulgaria, 28 May - 1 June 1984
- H. Borgwaldt:
  "PREPRO, A Preprocessor Code for SSYST Input"
  KfK 3537 (May 1983)
- W. Sengpiel:
  "SSYST-3 Module DESIGN"
  PNS-Nr. 605/81 (July 1981). In German
- W. Sengpiel:
  "SSYST-3 Module REGRES"
  PNS-Nr. 606/81 (July 1981). In German
- W. Sengpiel:
  "SSYST-3 Module MOCA"
  PNS-Nr. 607/81 (July 1981). In German
- S. Malang:
  "Code MULTRAN to Calculate High-Temperature Water-Vapour Zircaloy
  in Fuel Cladding of Water-Cooled Reactors"
  PNS-Nr. 750/83 (July 1983). In German
- J. Linek:
  Modelling of WWER Type Fuel Rods with the SSYST Code.
  Reprint from "Kernenergie", 30(1987)5, 189-192
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11. MACHINE REQUIREMENTS:
NEA-0684/06
Main storage requirements for running the test cases included in the package are less than 500K bytes on IBM 3084Q.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0684/06 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

MVS-SP (IBM 3084).
Compilers: FORTRAN-H-EXTENDED Version 2.3.0
           ASSEMBLER-H Version 0.5
           PL/I.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

W. Gulden, Projekt Nukleare Sicherheit
R. Meyder, Institut fuer Reaktorentwicklung
H. Borgwaldt, Institut fuer Neutronenphysik und Reaktortechnik
Kernforschungszentrum Karlsruhe GmbH
Postfach 3640
D-7500 KARLSRUHE, F.R. of Germany
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16. MATERIAL AVAILABLE
NEA-0684/06
File name File description Records
NEA0684_06.001 Information File 165
NEA0684_06.002 JCL to generate PDS files 44
NEA0684_06.003 NUCLEUS source program (FORTRAN-IV) 4405
NEA0684_06.004 SERVICE source program (FORTRAN-IV) 5631
NEA0684_06.005 PHYSICS source program (FORTRAN-IV) 26787
NEA0684_06.006 Control JCL & data 415
NEA0684_06.007 PREPRO source program (PL/I) 2736
NEA0684_06.008 MATPRO material properties lib (bin) 5
NEA0684_06.009 Test case JCL & data 1741
NEA0684_06.010 NEWBASIS test case printed output 437
NEA0684_06.011 COMPLETE test case printed output 55
NEA0684_06.012 SAMPLE1 test case printed output 160
NEA0684_06.013 SAMPLE2 test case printed output 119
NEA0684_06.014 SAMPLE3 test case printed output 702
NEA0684_06.015 SAMPLE4 test case printed output 1615
NEA0684_06.016 PREPROA test case printed output 283
NEA0684_06.017 PREPROB test case printed output 95
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, fuel rods, loss-of-coolant accident, transients.