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

NESC1081 PWR-GALE.

PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR

top ]
1. NAME OR DESIGNATION OF PROGRAM:  PWR-GALE.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
PWR-GALE NESC1081/01 Tested 11-MAR-1988

Machines used:

Package ID Orig. computer Test computer
NESC1081/01 CDC 7600 CDC CYBER 830
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

The PWR-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 pressurized water reactors (PWRs). 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.
top ]
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.
top ]
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.
top ]
6. TYPICAL RUNNING TIME:
NESC1081/01
The test cases included in this package were executed at NEA-DB on a CDC CYBER 830 computer. The following CPU times were  required: 0.4 seconds (PGALEGS); 26.5 seconds (PGALELQ).
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

BWR-GALE was developed from GALE (CCC-0335) as a more up-to-date tool based on more recent information published in NUREG-017, Rev. 1.
top ]
9. STATUS
Package ID Status date Status
NESC1081/01 11-MAR-1988 Tested at NEADB
top ]
10. REFERENCES:
NESC1081/01, included references:
- T. Chandrasekaran, J.Y. Lee and C.A. Willis:
  Calculation of Releases of Radioactive Materials in Gaseous and
  Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)
  NUREG-0017  (April 1985)
- Changes/Errata for PWR GALE (NUREG-0017/Rev.1)
- L. Eyberger:
  PWR-GALE Tape Description and Implementation Information.
  NESC Note 87-79  (June 30, 1987)
top ]
11. MACHINE REQUIREMENTS:
NESC1081/01
To run the test cases of this package on a CDC CYBER 830 computer, main storage requirements are 30,100 (octal) words CM  for PGALEGS and 162,400 (octal) words CM for PGALELQ. In addition, 27,650 (octal) words of ECS are used.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC1081/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NESC1081/01
NOS2.5.1 (CDC CYBER 830).
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

     T. Chandrasekaran, J.Y. Lee, C.A. Willis
     Division of Systems Integration
     Office of Nuclear Reactor Regulation
     U.S. Nuclear Regulatory Commission
     Washington, D.C. 20566, U. S. A.
top ]
16. MATERIAL AVAILABLE
NESC1081/01
File name File description Records
NESC1081_01.001 Information file 68
NESC1081_01.002 JCL and control information 27
NESC1081_01.003 PGALEGS FORTRAN source 628
NESC1081_01.004 PGALEGS sample problem input 43
NESC1081_01.005 PGALELQ FORTRAN source 1921
NESC1081_01.006 PGALELQ sample problem input 45
NESC1081_01.007 Nuclear data library 1 1265
NESC1081_01.008 Nuclear data library 2 495
NESC1081_01.009 Nuclear data library 3 2305
NESC1081_01.010 PGALEGS sample problem output 113
NESC1081_01.011 PGALELQ sample problem output 994
top ]
17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

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