NEA-0778 THYDE-B1/MOD2.
THYDE-B2, Thermohydraulic Transients During LOCA of BWR
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| THYDE-B1/MOD2 | NEA-0778/03 | Tested | 07-MAR-1989 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0778/03 | FACOM M-200 | IBM 3090 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
THYDE-B1/MOD2 is a computer code to analyze thermo-hydraulic transients of the reactor cooling system of a BWR, mainly during a small-break loss-of coolant accident (SB-LOCA) with special emphasis on the behavior of pressure and mixture level in the pressure vessel.
THYDE-B1/MOD2 is a computer code to analyze thermo-hydraulic transients of the reactor cooling system of a BWR, mainly during a small-break loss-of coolant accident (SB-LOCA) with special emphasis on the behavior of pressure and mixture level in the pressure vessel.
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4. METHOD OF SOLUTION
In THYDE-B1/MOD2, the coolant behavior is simulated with a volume-and-junction method based on the assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions, i.e., subcooled liquid, saturated mixture and saturated steam regions are allowed to exist. The regions are separated by moving boundaries tracked by mass and energy balances in each region. The pressure vessel is represented by two volumes with three regions, one for the inside of the shroud and the other for the outside. Other portions of the system are treated with the homogeneous model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SB-LOCAs in which the hydraulic transient is relatively slow and the cooling of the core strongly depends on the mixture level behavior in the vessel. In order to simulate the reactor system behavior, THYDE-B1/MOD2 is provided with analytical models for reactor kinetics, heat generation and conduction in fuel rods and structures, heat transfer between coolant and solid surfaces, coolant injection systems, breaks and discharge systems, jet pumps, recirculation pumps, and so on.
In THYDE-B1/MOD2, the coolant behavior is simulated with a volume-and-junction method based on the assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions, i.e., subcooled liquid, saturated mixture and saturated steam regions are allowed to exist. The regions are separated by moving boundaries tracked by mass and energy balances in each region. The pressure vessel is represented by two volumes with three regions, one for the inside of the shroud and the other for the outside. Other portions of the system are treated with the homogeneous model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SB-LOCAs in which the hydraulic transient is relatively slow and the cooling of the core strongly depends on the mixture level behavior in the vessel. In order to simulate the reactor system behavior, THYDE-B1/MOD2 is provided with analytical models for reactor kinetics, heat generation and conduction in fuel rods and structures, heat transfer between coolant and solid surfaces, coolant injection systems, breaks and discharge systems, jet pumps, recirculation pumps, and so on.
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6. TYPICAL RUNNING TIME
The running time depends on the number of time steps and the complexity of the nodalization of the system to be analyzed. A rough estimate of CPU time requirements is about 6ms/volume.step on FACOM M-200. As a BWR is usually modelled by 4 to 6 volumes with time step size of 3 to 10 milliseconds, the total CPU time for a transient of 500 seconds is about 0.5 to 2 hours.
The running time depends on the number of time steps and the complexity of the nodalization of the system to be analyzed. A rough estimate of CPU time requirements is about 6ms/volume.step on FACOM M-200. As a BWR is usually modelled by 4 to 6 volumes with time step size of 3 to 10 milliseconds, the total CPU time for a transient of 500 seconds is about 0.5 to 2 hours.
NEA-0778/03
NEA-DB ran the test case included in this package on an IBM 3090 computer. Execution was terminated after a pre-fixed time of 570 seconds.[ top ]
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8. RELATED AND AUXILIARY PROGRAMS
Since THYDE-B1/MOD2 uses the steam table subroutines of RELAP-4, the same steam table dataset as used in RELAP-4 must be supplied.
The results of a THYDE-B1/MOD2 calculation can be plotted by the SPLPACK-1 program generally designed for transient analysis codes.
Since THYDE-B1/MOD2 uses the steam table subroutines of RELAP-4, the same steam table dataset as used in RELAP-4 must be supplied.
The results of a THYDE-B1/MOD2 calculation can be plotted by the SPLPACK-1 program generally designed for transient analysis codes.
NEA-0778/03
SPLPLOT-1 Plotting Program[ top ]
10. REFERENCES
- K. Muramatsu et Al.
Users Manual for SPLPACK-1
A Program Package for Plotting and Editing of Experimental and
Analytical Data of Various Transient Systems,
JAERI-M 83-166 (1983).
- K. Muramatsu et Al.
Analysis of ROSA-III Small-Break LOCA Experiment RUN 804 by
THYDE-B1 Computer Code,
JAERI-M 9413 (1981).
- T. Simizu
Verification of LOCA/ECCS Analysis Code ALARM-B2 and THYDE-B1 by
Comparision with RELAP4/MOD6/U4/J3.
JAERI-M 82-094 (1982).
- K. Muramatsu et Al.
Users Manual for SPLPACK-1
A Program Package for Plotting and Editing of Experimental and
Analytical Data of Various Transient Systems,
JAERI-M 83-166 (1983).
- K. Muramatsu et Al.
Analysis of ROSA-III Small-Break LOCA Experiment RUN 804 by
THYDE-B1 Computer Code,
JAERI-M 9413 (1981).
- T. Simizu
Verification of LOCA/ECCS Analysis Code ALARM-B2 and THYDE-B1 by
Comparision with RELAP4/MOD6/U4/J3.
JAERI-M 82-094 (1982).
NEA-0778/03, included references:
- K. Muramatsu and M. Akimoto:THYDE-B1/MOD1: A Computer Code for Analysis of Small-Break Loss
of-Coolant Accidents of Boiling Water Reactors.
JAERI-M 82-126 (August 1982)
- Library Functions and Subroutines Used in THYDE-B1 and SPLPLOT-1
- THYDE-B1/MOD2 SPLPLOT-1: Plotting Output
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NEA-0778/03
Storage requirement for the test case on an IBM 3090 computer is 988K bytes.[ top ]
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NEA-0778/03
| File name | File description | Records |
|---|---|---|
| NEA0778_03.001 | INFORMATION FILE | 212 |
| NEA0778_03.002 | THYDEB FORTRAN SOURCE FILE 1 | 11144 |
| NEA0778_03.003 | THYDEB FORTRAN SOURCE FILE 2 | 10946 |
| NEA0778_03.004 | THYDEB FORTRAN SOURCE FILE 3 | 8677 |
| NEA0778_03.005 | TTIMER AND DATE(DUMMY) FORTRAN SOURCE | 40 |
| NEA0778_03.006 | LOCF FUNCTION ASSEMBLER SOURCE | 7 |
| NEA0778_03.007 | FORTRAN LIBRARY CONVERSION PROGRAM | 19 |
| NEA0778_03.008 | STEAM-TABLE (formatted) | 2544 |
| NEA0778_03.009 | INPUT DATA, 1ST SAMPLE PROB. | 518 |
| NEA0778_03.010 | INPUT DATA, 2ND SAMPLE PROB. | 602 |
| NEA0778_03.011 | FT03 INPUT, MAX CPU TIME | 1 |
| NEA0778_03.012 | JCL USED IN TESTING | 324 |
| NEA0778_03.013 | FT06 TEST O/P, 1ST SAMPLE PROB. | 4620 |
| NEA0778_03.014 | FT06 TEST O/P, 2ND SAMPLE PROB. | 2170 |
| NEA0778_03.015 | FT06 ORIGINAL O/P, 1ST SAMPLE PROB. | 4618 |
| NEA0778_03.016 | FT06 ORIGINAL O/P, 2ND SAMPLE PROB. | 2169 |
| NEA0778_03.017 | SPLPLOT FORTRAN SOURCE | 17543 |
| NEA0778_03.018 | SPLPLOT INPUT, 1ST SAMPLE PROB. | 118 |
| NEA0778_03.019 | SPLPLOT INPUT, 2ND SAMPLE PROB. | 152 |
| NEA0778_03.020 | LABELLING DATA | 272 |
| NEA0778_03.021 | SPLPLOT FT06 ORIGINAL O/P, 1ST SAMPLE PROB. | 463 |
| NEA0778_03.022 | SPLPLOT FT06 ORIGINAL O/P, 2ND SAMPLE PROB. | 559 |
Keywords: BWR reactors, hydraulics, loss-of-coolant accident, thermodynamics, transients.