last modified: 11-MAR-1988 | catalog | categories | new | search |

NESC1080 BWR-GALE.

BWR-GALE, Radioactive Gaseous and Liquid Waste Release from BWR

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1. NAME OR DESIGNATION OF PROGRAM:  BWR-GALE.
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2. COMPUTERS
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Program name Package id Status Status date
BWR-GALE NESC1080/01 Tested 11-MAR-1988

Machines used:

Package ID Orig. computer Test computer
NESC1080/01 CDC 7600 CDC CYBER 830
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating  reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials  that may be released to the environment.
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4. METHOD OF SOLUTION

GALE calculates expected releases based on 1) standardized coolant activities derived from ANS Standards 18.1 Working Group recommendations, 2) release and transport mechanisms that result in the appearance of radioactive material in liquid and  gaseous waste streams, 3) plant-specific design features used to reduce the quantities of radioactive materials ultimately released to the environs, and 4) information received on the operation of nuclear power plants.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The liquid release portion of GALE uses subroutines taken from the ORIGEN (CCC-217) to  calculate radionuclide buildup and decay during collection, processing, and storage of liquid radwaste. Memory requirements for  this part of the program are determined by the large nuclear data base accessed by these subroutines.
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6. TYPICAL RUNNING TIME:
NESC1080/01
The test cases included in this package were run by NEA-DB on a CDC CYBER 830 computer. The following execution times were found: 0.38 CP seconds (BGALEGS); 23.1 CP seconds (BGALELQ).
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NESC1080/01 11-MAR-1988 Tested at NEADB
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10. REFERENCES:
NESC1080/01, included references:
- F.P. Cardile, R.R. Bellamy et al.:
  Calculation of Releases of Radioactive Materials in Gaseous Liquid
  Effluents from Boiling Water Reactors (BWR-GALE Code)
  NUREG-0016  (January 1979)
- Changes/Errata for BWR GALE (NUREG-0016/Rev.1)
- L. Eyberger:
  BWR-GALE Tape Description and Implementation Information.
  NESC Note 87-78  (June 30, 1987)
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11. MACHINE REQUIREMENTS:
NESC1080/01
To run the test cases included in this package, main storage requirements were: 26,600 (octal) words (BGALEGS); 151,200 (octal) words (BGALELQ). In addition, 27,6750 (octal) words of ECS were used.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC1080/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NESC1080/01
NOS2.5.1 (CDC CYBER 830).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

     F.P. Cardile, and R.R. Bellamy, Editors
     Effluent Treatment Systems Branch
     Division of Site Safety and Environmental Analysis
     Office of Nuclear Reactor Regulation
     U.S. Nuclear Regulatory Commission
     Washington, D.C. 20566, U. S. A.
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16. MATERIAL AVAILABLE
NESC1080/01
File name File description Records
NESC1080_01.001 Information file 68
NESC1080_01.002 JCL and control information 27
NESC1080_01.003 BGALEGS FORTRAN source 535
NESC1080_01.004 BGALEGS sample problem input 34
NESC1080_01.005 BGALELQ FORTRAN source 1710
NESC1080_01.006 BGALELQ sample problem input 36
NESC1080_01.007 Nuclear data library 1 1265
NESC1080_01.008 Nuclear data library 2 495
NESC1080_01.009 Nuclear data library 3 2305
NESC1080_01.010 BGALEGS sample problem output 109
NESC1080_01.011 BGALELQ sample problem output 992
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, gaseous wastes, liquid wastes, radioactive effluents, radioactive release.