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NEA-0411 THESEE-3.

THESEE-3, Orgel Reactor Performance and Statistic Hot Channel Factors

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1. NAME OR DESIGNATION OF PROGRAM:  THESEE-3.
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2. COMPUTERS
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Program name Package id Status Status date
THESEE-3 NEA-0411/01 Tested 01-MAR-1974

Machines used:

Package ID Orig. computer Test computer
NEA-0411/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The code applies to a heavy-water moderated organic-cooled reactor channel. Different fuel cluster models can be used (circular or hexagonal patterns). The code gives  coolant temperatures and velocities and cladding temperatures throughout the channel and also channel performances, such as power, outlet temperature, boiling and burn-out safety margins (see THESEE-1). In a further step, calculations are performed with statistical values obtained by random retrieval of geometrical in- put data and taking into account construction tolerances, vibra- tions, etc. The code evaluates the mean value and standard devia- tion for the more important thermal and hydraulic parameters.
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4. METHOD OF SOLUTION

First step calculations are performed for nominal values of parameters by solving iteratively the non-linear system of equations which give the pressure drops in subchannels of  the current zone (see THESEE-1). Then a Gaussian probability distribution of possible statistical values of the geometrical input data is assumed. A random number generation routine determines the statistical case. Calculations are performed  in the same way as for the nominal case. In the case of several channels, statistical performances must be adjusted to equalize the  normal pressure drop. A special subroutine (AVERAGE) then determines the mean value and standard deviation, and thus probability functions of the most significant thermal and hydraulic results.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum 7 fuel clusters, each divided into 10 axial zones. Fuel bundle geometries are restricted to the following models - circular pattern 6/7, 18/19, 36/67 rods, with or without fillers. The fuel temperature distribution is not studied. The probability distribution of the statistical input is assumed to be a Gaussian function. The principle of random retrieval of statistical values is correct, but  some additional correlations could be found from a more accurate study of the channel geometry, in order to approximate the real case better.
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES OF THE PROGRAM

Energy and mass transfer between adjacent subchannels, non-uniform heat generation throughout fuel rods and bundle, in the same cross section are taken into account.
By changing some routines, other bundle geometries and other one-phase liquid coolants can be handled. The statistical treatment  of input data allows understanding the importance of construction and erection tolerances on the channel performances, to determine the maximum cladding temperature and hot channel factor in a more realistic way.
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0411/01 01-MAR-1974 Tested at NEADB
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10. REFERENCES: - B. Chambaud:, report EUR 4201 F.
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11. MACHINE REQUIREMENTS:  200k to 300k bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0411/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 360/370 OS.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

   B. Chambaud
   J.R.C. EURATOM
   Ispra Establishment, Italy.
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16. MATERIAL AVAILABLE
NEA-0411/01
File name File description Records
NEA0411_01.001 SOURCE PROGRAM (FORTRAN) 1994
NEA0411_01.002 SAMPLE PROBLEM 123
NEA0411_01.003 OUTPUT LIST OF SAMPLE PROBLEM 1664
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: fuel element clusters, heavy water moderated reactors, iterative methods, organic cooled reactors, probability, reactor channels, reactor safety, thermodynamics.