last modified: 30-APR-2001 | catalog | categories | new | search |

ESTS0050 RATAF.

RATAF, Radioactive Liquid Tank Failure

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1. NAME OR DESIGNATION OF PROGRAM:  RATAF.
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2. COMPUTERS
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Program name Package id Status Status date
RATAF ESTS0050/01 Arrived 30-APR-2001

Machines used:

Package ID Orig. computer Test computer
ESTS0050/01 IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

RATAF calculates the conse- quences of radioactive liquid tank failures. In each of the proces-  sing systems considered, RATAF can calculate the tank isotopic con-  centrations in either the collector tank or the evaporator bottoms tank.
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4. METHOD OF SOLUTION

The activity of the shim bleed wastes is based  on the primary coolant letdown system effluent activity. Input acti- vities are based on the weighted average activity of the composite stream entering the waste collection tanks. The tank factors provide the capability to consider radionuclide removal by demineralizers or other treatment equipment prior to the tank. For evaporator bottoms  tanks, the tank factors provide the capability to consider the effects of radionuclide concentration in the evaporator.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Maxima of -, 800 nuclides
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6. TYPICAL RUNNING TIME

NESC executed the sample problem in 5 CPU seconds on an IBM3033; 1.5 minutes on an IBM PS/2 Model 70 with a
math coprocessor; and 6.5 minutes on a Compaq 386s without a math coprocessor.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

RATAF is based on the PWR-GALE and  BWR-GALE computer programs.
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9. STATUS
Package ID Status date Status
ESTS0050/01 30-APR-2001 Masterfiled Arrived
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10. REFERENCES

- F.P. Cardile and R.R. Bellamy, Ed.,
Calculation of Releases of Radioactive Materials in Gaseous Liquid
Effluents from Boiling Water Reactors (BWR-GALE Code),
NUREG-0016, Revision 1, January 1979.
- Calculation of Releases of Radioactive Materials in Gaseous and
Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),
NUREG-0017, April 1976.
- M.J. Bell,
ORIGEN - The ORNL Isotope Generation and Depletion Code,
ORNL-4628, May 1973.
ESTS0050/01, included references:
- W.C. Burke and F.J. Congel:(Principal Investigators)
J.S. Boegli et al.:(Editors)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power
Plants, A Guidance Manual for Users of Standard Technical Specifications
NUREG-0133 (October 1978).
- L. Eyberger:
RATAF Tape Description and Sample Problem Input - NESC Note 83-25 (January 27,
1983).
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11. MACHINE REQUIREMENTS

300K bytes of memory are required to execute  the program.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
ESTS0050/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS-MVT; OS-MVS; MS-DOS 3.3; MS-DOS 4.0.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

370:      J.A. Shields
          Division of Automatic Data Processing
          U.S. Nuclear Regulatory Commission
          Washington, D.C. 20555

PC:       P. Johnson
          National Energy Software Center
          Argonne National Laboratory
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16. MATERIAL AVAILABLE
ESTS0050/01
source program   mag tapeRATAF Source File                          SRCTP
test-case data   mag tapeRATAF Sample Problem Input                 DATTP
symb data lib    mag tapeNuclear Lib. Data for Corrosion            LBSTP
symb data lib    mag tapeNuclear Lib. Data for Fuel Materials       LBSTP
symb data lib    mag tapeNuclear Lib. Data for Fission Procucts     LBSTP
test-case data   mag tapeJCL Control Information                    DATTP
report                   NUREG-0133 (October 1978)                  REPPT
prog. note               NESC Note 83-25 (1993) + S.P. Input        NOTPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: containers, failures, nuclear power plants, radioactive effluents.