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NESC0745 MATADOR.

MATADOR, Fission Products Release and Deposition in LWR Containment, Meltdown Accident

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1. NAME OR DESIGNATION OF PROGRAM:  MATADOR.
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2. COMPUTERS
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Program name Package id Status Status date
MATADOR NESC0745/03 Tested 07-MAR-1986
MATADOR NESC0745/04 Tested 13-DEC-1988

Machines used:

Package ID Orig. computer Test computer
NESC0745/03 CDC CYBER 180 CDC CYBER 740
NESC0745/04 IBM 3090 IBM 3090
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3. DESCRIPTION OF PROBLEM OR FUNCTION

MATADOR analyzes the transport  and deposition of radionuclides as vapor or aerosol through Light Water Reactor (LWR) containments during severe accidents and calculates environmental release fractions of radionuclides as a function of time. It is intended for use in system risk studies. The principal output is information on the timing and magnitude of radionuclides releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and the operation of engineered safety systems such as sprays. Input data on the source term from the primary system, the containment geometry and thermal-hydraulic conditions are required.
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4. METHOD OF SOLUTION

The containment is modeled as a series of interconnected control volumes. In each control volume, radionuclides can be in any of four different states: suspended in the atmosphere, deposited on the walls, picked up by spray water droplets, or residing in bulk water in the sump or on the containment floor. If the physical form of the radionuclides is aerosols, these states are further divided into size classes. Radionuclides can also be picked up and collected by engineered safety systems such as filters, ice condensers, and pressure suppression pools. Radionuclides can transfer from one state to another within each compartment as a result of processes such as deposition on the walls or spray water droplet pickup. They can also transfer from one compartment to another through inter-compartmental flows. A linear first-order differential equation is written for each species in each state and control volume to account for the transfer of species between states in a control volume or between control volumes. These equations are assembled into a matrix equation and solved simultaneously using the matrix expansion technique with scaling. The aerosol agglomeration and gravitational  settling calculations are done in series over each time-step using the moments approach. The discrete aerosol size distribution is converted to a log-normal distribution for agglomeration calculations. After these calculations, it is converted back into a
discrete distribution for transport calculations over the next time- step. Care is taken to conserve the total aerosol mass as well as individual species masses between conversions. The time-step size is regulated so that the two sets of calculations do not unduly affect  each other.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of -
   10 interconnected control volumes
   10 chemical species
   10 kinetic transport processes
   10 discrete size classes for aerosols
Application is limited to LWR systems. Noble gases are assumed to simply transfer in phase with the fluid flow and not deposit on the  surfaces or be affected by engineered safety systems.
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6. TYPICAL RUNNING TIME

A typical problem covering 1 hour of accident time without or with sprays operating requires 8 or 50 CP seconds, respectively, on a CDC CYBER180/855. Execution time increases by a factor of 1.5 on a CDC CYBER74 and by a factor of 6 on a CDC CYBER73. NESC executed the sample problem in 5 CP seconds on a CDC CYBER170/875.
NESC0745/03
NEA-DB ran the test case included in this package on a  CDC CYBER 740 computer in 17 seconds of CPU time.

NESC0745/04
The test cases included in this package ran at NEA-DB on an IBM 3090 computer in 6.5 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

MATADOR treats both vapor and aerosol behavior and can be used for both PWR and BWR applications.
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8. RELATED AND AUXILIARY PROGRAMS

MATADOR was developed to replace the CORRAL2 program. A physical processes program such as MARCH2, NESC Abstract 734, can be used to generate the thermal-hydraulic data required by MATADOR. MATADOR can directly accept source terms calculated by the TRAP-MELT program. The environmental radionuclide  release fractions calculated by MATADOR can be used in a radiological consequence program such as CRAC2, Nesc Abstract 722, to calculate the health effects of reactor accidents.
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9. STATUS
Package ID Status date Status
NESC0745/03 07-MAR-1986 Tested at NEADB
NESC0745/04 13-DEC-1988 Tested at NEADB
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10. REFERENCES

- H.I. Avci, S. Raghuram, and P. Baybutt,
  MATADOR (Methods for the Analysis of Transport and Deposition of
  Radionuclides) Code Description and User's Manual,
  NUREG/CR-4211 (BMI-2126), April 1985.
- H. Jordan, J.A. Gieseke, and P. Baybutt,
  TRAP-MELT User's Manual,
  NUREG/CR-0632 (BMI-2017), February 1979.
- R.O. Wooton, P. Cybulskis, and S.F. Quayle,
  MARCH2 (Meltdown Accident Response CHaracteristics) Code
  Description and User's Manual,
  NUREG/CR-3988 (BMI-2115), September 1984.
- Lynn T. Ritchie, Jay D. Johnson, and Roger M. Blond,
  Calculations of Reactor Accident Consequences Version 2 CRAC:
  Computer Code User's Guide,
  NUREG/CR-2326 (SAND81-1994), February 1983.
NESC0745/03, included references:
- L. Eyberger:
  MATADOR Tape Description and Implementation Information.
  NESC Note 85-72  (April 18, 1985)
- P. Baybutt, S. Raghuram and H.I. Avci:
  MATADOR: A Computer Code for the  Analysis of Radionuclide
  Behavior During Degraded Core Accidents in Light Water Reactors.
  NUREG/CR-4210, BMI-2125  (April 1985)
- P. Baybutt, S. Raghuram and H.I. Avci:
  MATADOR (Methods for the Analysis of Transport And Deposition Of
  Radionuclides) Code Description and User's Manual.
  NUREG/CR-4211, BMI-2126  (April 1985)
NESC0745/04, included references:
- P. Baybutt, S. Raghuram and H.I. Avci:
  MATADOR: A Computer Code for the  Analysis of Radionuclide
  Behavior During Degraded Core Accidents in Light Water Reactors.
  NUREG/CR-4210, BMI-2125  (April 1985)
- P. Baybutt, S. Raghuram and H.I. Avci:
  MATADOR (Methods for the Analysis of Transport And Deposition Of
  Radionuclides) Code Description and User's Manual.
  NUREG/CR-4210, BMI-2126  (April 1985)
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11. MACHINE REQUIREMENTS

MATADOR requires, without segmentation, approximately 335,000 (octal) words of central memory (SCM) and 116,000 (octal) words of extended core storage (ECS). NESC executed  the sample problem using the program and reducing the dimensions of  several arrays as outlined in the user's manual.
NESC0745/03
To run the test case of this package on CDC CYBER 740,  263,700 (octal) words of CM are required.

NESC0745/04
The test case ran on an IBM 3090 in 812K bytes of main  storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0745/03 FORTRAN-IV
NESC0745/04 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  NOS 2.3, NOS/BE 2.2, NOS 2.2 (CDC CYBER170).
NESC0745/03
The test case was run under NOS 1.4+531 (CYBER 740).

NESC0745/04
The test was executed under 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 AUTHOR

         H.I. Avci, P. Baybutt, and S. Raghuram
         Columbus Laboratories
         Battelle Memorial Institute
         505 King Avenue
         Columbus, Ohio  43201
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16. MATERIAL AVAILABLE
NESC0745/03
File name File description Records
NESC0745_03.001 information file 63
NESC0745_03.002 job control instructions 32
NESC0745_03.003 MATADOR source program (FORTRAN) 5121
NESC0745_03.004 MATADOR UPDATE source program 4935
NESC0745_03.005 MATADOR UPDATE corrections 31
NESC0745_03.006 SEGLOAD directives 15
NESC0745_03.007 MATADOR test case input data 684
NESC0745_03.008 MATADOR test case printed output 2805
NESC0745/04
File name File description Records
NESC0745_04.001 INFORMATION FILE 72
NESC0745_04.002 MATADOR FORTRAN SOURCE 5172
NESC0745_04.003 ORIGINAL JCL 48
NESC0745_04.004 JCL USED FOR TESTING 121
NESC0745_04.005 SAMPLE CASE INPUT 684
NESC0745_04.006 ORIGINAL SAMPLE CASE OUTPUT 2907
NESC0745_04.007 SAMPLE CASE OUTPUT OBTAINED ON TEST COMPUTER 2805
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: LWR reactors, accidents, aerosols, containment, engineered safety systems, radioisotopes, reactor cores, reactor safety.