GALE86: Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents from Boiling Water and Pressurized Water Reactors.
U.S. Nuclear Regulatory Commission, Washington, D.C., USA.
Fortran IV with updates; PC, MAC (C00506MNYCP02).
4. NATURE OF PROBLEM
GALE is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs) and 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. The CCC-506/GALE86 code package was developed as a newer tool based on more recent information published in NUREG-017, Rev. 1. RSICC retains the CCC-335/GALE package for use with plants licensed with the earlier technology.
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.
The liquid release portion of GALE uses subroutines taken from the ORIGEN program (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.
7. TYPICAL RUNNING TIME
A few seconds.
PC and MAC.
Linux, Windows and MacOS platforms. A Fortran compiler is required if compiling source.
a) Included Documentation
P. A. Bell, Changes/Errata for GALE BWR (NUREG-016, Rev. 1) and GALE PWR (NUREG-017, Rev. 1), Memo 1986.
F. P. Cardile and R. R. Bellamy, Eds., “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code),” NUREG-0016, Rev 1 (January 1979).
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, Rev. 1 (April 1985).
Included in the GALE86 package is documentation, readme files, source code, pre-compiled windows and linux executables, test input and output.
January 1982; updated March 1983, July 1986, January 1987, April 2002, February 2013.
KEYWORDS: RADIOLOGICAL SAFETY; NUCLIDE TRANSPORT; ENVIRONMENTAL DOSE; FISSION PRODUCT INVENTORY; RADIOACTIVITY RELEASE