NEA-0411 THESEE-3.
THESEE-3, Orgel Reactor Performance and Statistic Hot Channel Factors
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, CPU, UNUSUAL FEATURES OF THE PROGRAM, AUXILIARIES, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.
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.
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.
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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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.
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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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 |
Keywords: fuel element clusters, heavy water moderated reactors, iterative methods, organic cooled reactors, probability, reactor channels, reactor safety, thermodynamics.