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NEA-0778 THYDE-B1/MOD2.

THYDE-B2, Thermohydraulic Transients During LOCA of BWR

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1. NAME OR DESIGNATION OF PROGRAM:  THYDE-B1/MOD2.
A Computer Code for the Analysis of Small-Break Loss-of-Coolant
Accident of Boiling Water Reactors.
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2. COMPUTERS
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

As this code has been developed and verified for relatively slow transients of BWR, users should be careful to apply this code to any rapid transients such as an early phase of a large break LOCA.
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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.
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.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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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.
NEA-0778/03
SPLPLOT-1           Plotting Program
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9. STATUS
Package ID Status date Status
NEA-0778/03 07-MAR-1989 Tested at NEADB
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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).
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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11. MACHINE REQUIREMENTS:
NEA-0778/03
Storage requirement for the test case on an IBM 3090 computer is 988K bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0778/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-0778/03
MVS/XA (IBM 3090)
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         K. Muramatsu and M. Akimoto
         Department of Nuclear Safety Evaluation
         Japan Atomic Energy Research Institute
         Tokai-mura, Naka-gun, Ibaraki-Ken, Japan
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16. MATERIAL AVAILABLE
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
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, hydraulics, loss-of-coolant accident, thermodynamics, transients.