NEA-0745 TRAP-SCO-2.
TRAPSCO-2, Pressure and Temperature Transients in PWR Subcompartments During LOCA
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| TRAPSCO-2 | NEA-0745/01 | Tested | 01-FEB-1984 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0745/01 | IBM 3081 | IBM 3081 |
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4. METHOD OF SOLUTION
Conservation of mass and energy are solved in a finite difference solution using the predictor-corrector method (Simpson integration). Conservation of momentum is solved for problems involving inertial-frictional effects. The program rigorously treats the thermodynamics of two-phase components mixtures of water and an inert gas and contains three critical flow options (homogeneous, MOODY, HENRI-FAUSKE) options include: Discharge coefficient, water entrainment, fly-out panels.
Conservation of mass and energy are solved in a finite difference solution using the predictor-corrector method (Simpson integration). Conservation of momentum is solved for problems involving inertial-frictional effects. The program rigorously treats the thermodynamics of two-phase components mixtures of water and an inert gas and contains three critical flow options (homogeneous, MOODY, HENRI-FAUSKE) options include: Discharge coefficient, water entrainment, fly-out panels.
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7. UNUSUAL FEATURES OF THE PROGRAM
The program is especially designed to treat depressurization phenomena for high pressure water-vapour systems during the initial phases whereby heat transfer effects can be ignored.
Different initial thermodynamic conditions may be specified for each node ranging from atmospheric pressure to 165 bar for saturated water to overheated vapour.
The program is especially designed to treat depressurization phenomena for high pressure water-vapour systems during the initial phases whereby heat transfer effects can be ignored.
Different initial thermodynamic conditions may be specified for each node ranging from atmospheric pressure to 165 bar for saturated water to overheated vapour.
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10. REFERENCES
- ZOCO V: Nuclear Engineering and Design Vol. 23, 1972.
- F.J. Moody,
Maximum Flow Rate of a Single Component, Two Phase Mixture,
Transactions of the ASME - February 1965.
- R. Henry, H.K. Fauske,
Two Phase Critical Flow of One Component Mixtures in Nozzles,
Orifices and Short Tubes.
Journal of Heat Transfer, May 1971.
- C.W. Savery et al.,
Subcompartment Analysis of High Energy Pipe Ruptures,
Nuclear Technology November 1975.
- E.J. Stubbe, J. Robeyns, A. Danguy (Tractionel)
TRAP: Computer Codes for the Evaluation of the Pressure Transients in the Subcompartments (TRAP-SCO) and the Containment (TRAP-CON)
of a Reactor Plant Following a High Energy Line Break,
Proceedings of the ENS/ANS international Topical Meeting on
Nuclear Power Reactor Safety,
Brussels, October 1978, Vol III p.2168.
- W. Winkler,
Comparison Report on OECD-CSNI Containment Standard Problem no 1,
CSNI Report no 41, 1980.
- D.L. Ngyuen,
Comparison Report on OECD-CSNI Containment Standard Problem no 2,
CSNI Report no 65 (DRAFT) 1981.
- ZOCO V: Nuclear Engineering and Design Vol. 23, 1972.
- F.J. Moody,
Maximum Flow Rate of a Single Component, Two Phase Mixture,
Transactions of the ASME - February 1965.
- R. Henry, H.K. Fauske,
Two Phase Critical Flow of One Component Mixtures in Nozzles,
Orifices and Short Tubes.
Journal of Heat Transfer, May 1971.
- C.W. Savery et al.,
Subcompartment Analysis of High Energy Pipe Ruptures,
Nuclear Technology November 1975.
- E.J. Stubbe, J. Robeyns, A. Danguy (Tractionel)
TRAP: Computer Codes for the Evaluation of the Pressure Transients in the Subcompartments (TRAP-SCO) and the Containment (TRAP-CON)
of a Reactor Plant Following a High Energy Line Break,
Proceedings of the ENS/ANS international Topical Meeting on
Nuclear Power Reactor Safety,
Brussels, October 1978, Vol III p.2168.
- W. Winkler,
Comparison Report on OECD-CSNI Containment Standard Problem no 1,
CSNI Report no 41, 1980.
- D.L. Ngyuen,
Comparison Report on OECD-CSNI Containment Standard Problem no 2,
CSNI Report no 65 (DRAFT) 1981.
NEA-0745/01, included references:
- E. Stubbe et A. Danguy:Programme TRAPSCO-2: Analyse a court terme des surpressions entre
logettes dans l'enceinte d'une centrale nucleaire suite a un
accident LOCA. 51257/NT/NU/TC-0324 (March 25,1982).
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NEA-0745/01
| File name | File description | Records |
|---|---|---|
| NEA0745_01.003 | TRAPSCO-2 INFORMATION FILE | 60 |
| NEA0745_01.004 | TRAPSCO-2 SOURCE (CARD-IAMAGES) | 3105 |
| NEA0745_01.006 | TRAPSCO-2 JCL FOR TEST CASE | 55 |
| NEA0745_01.007 | TRAPSCO-2 INPUT DATA FOR TEST CASE | 64 |
| NEA0745_01.008 | TRAPSCO-2 OUTPUT OF TEST CASE | 1446 |
Keywords: accidents, containment, failures, flow models, fluid flow, pressure, pressure gradients, reactor safety, temperature gradients, thermodynamics, transients, two-phase flow.