NESC1080 BWR-GALE.

1. NAME OR DESIGNATION OF PROGRAM:  BWR-GALE.

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.

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.

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.

6. TYPICAL RUNNING TIME:

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).

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:

10. 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)

11. MACHINE REQUIREMENTS:

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.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

NOS2.5.1 (CDC CYBER 830).

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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.

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