last modified: 25-JUN-1987 | catalog | categories | new | search |

NEA-0712 CASSANDRE.

CASSANDRE, 2-D Reactor Dynamic FEM Program with Thermohydraulic Feedback

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1. NAME OR DESIGNATION OF PROGRAM:  CASSANDRE.
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2. COMPUTERS
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Program name Package id Status Status date
CASSANDRE NEA-0712/01 Tested 25-JUN-1987

Machines used:

Package ID Orig. computer Test computer
NEA-0712/01 IBM 370 series IBM 3084
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3. DESCRIPTION OF PROGRAM OR FUNCTION

CASSANDRE is a two-dimensional  (x-y or r-z) finite-elements neutronics code with thermohydraulic feedback for reactor dynamics prior to the disassembly phase. The code was conceived in order to be coupled with any thermohydraulics  module, although thermohydraulics feedback is only considered in r-z geometry. In the steady state, criticality search is possible either by control-rod insertion or by homogeneous poisoning of the coolant.
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4. METHOD OF SOLUTION

The program uses multigroup diffusion theory. Its main characteristics are the use of a generalized quasi-static model, the use of a flexible multigroup point-kinetics algorithm allowing for spectral matching, and the use of a finite elements description.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  The user must prepare a cross section library.
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6. TYPICAL RUNNING TIME:
NEA-0712/01
NEA-DB executed the test case included in this package  on an IBM 3084 computer in 88 seconds of CPU time.
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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-0712/01 25-JUN-1987 Tested at NEADB
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10. REFERENCES:
NEA-0712/01, included references:
- B. Arien, A. Siebertz, J. Devooght and E. Mund:
  CASSANDRE: A Two-Dimensional Multigroup Diffusion Code For Reactor
  Transients Analysis.
  BLG 571  (September 1984)
- B. Arien and J. Daniels:
  CASSANDRE: A Two-Dimensional Multigroup Diffusion Code For Reactor
  Transients Analysis. Code Description and User's Guide.
  BLG 591  (December 1986)
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11. MACHINE REQUIREMENTS:
NEA-0712/01
On an IBM 3084 computer, 952K bytes of main storage (without overlay) were required to execute the test case.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0712/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-0712/01
MVS-SP (IBM 3084).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

     B. ARIEN and J. DANIELS
     Centre d'etudes de l'energie nucleaire
     1, rue Ch. Lemaire
     1160 BRUXELLES, Belgium
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16. MATERIAL AVAILABLE
NEA-0712/01
File name File description Records
NEA0712_01.001 Information file 54
NEA0712_01.002 Fortran source (neutronics part) 9014
NEA0712_01.003 Fortran source (thermohydraulics part) 340
NEA0712_01.004 Fortran source (thermohydraulics benchmark) 128
NEA0712_01.005 Fortran source (dummy subroutines) 9
NEA0712_01.006 Data (Benchmark test problem) 200
NEA0712_01.007 Sample problem output list 5430
NEA0712_01.008 Sample JCL used at NEA-DB 143
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: criticality searches, diffusion equations, finite element method, hydraulics, kinetics, multigroup, r-z, reactor kinetics, thermodynamics, two-dimensional, x-y.