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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. Only liaison officers are authorised to submit online requests. Rules for requesters 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.