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GALE Overview

The Gaseous and Liquid Effluents (GALE) series of codes consists of four codes that calculate the gaseous and liquid effluent releases from pressurized-water reactors (PWRs) and boiling-water reactors (BWRs). These are:
  • Pressurized-water reactor liquid effluent (PWRLE)
  • Pressurized-water reactor gaseous effluent (PWRGE)
  • Boiling-water reactor liquid effluent (BWRLE)
  • Boiling-water reactor gaseous effluent (BWRGE)
This Fortran-based code uses a combination of input data and hardwired parameters to calculate the source term of radionuclides generated by a nuclear power plant during routine operation. Parameters that vary from plant to plant are treated as “inputs”; GALE asks the operator for input values on each run. Hardwired parameters are plant characteristics that are assumed to be the same for all reactors. GALE is maintained at the Pacific Northwest National Laboratory (PNNL) under contract for the U.S. NRC Office of Research.
GALE-86 - This version of the code is based upon the reactor coolant source term (tables and adjustment equations) described in the ANSI/ANS-18.1-1984 and the hard wired parameters discussed in NUREG-0017, Revision 1 for GALE-PWR 86 and NUREG-0016, Revision 1 for GALE-BWR 86.
GALE-08 - PNNL modified GALE-86 to use the tables and adjustment equations described in ANSI/ANS-18.1-1999, updates in liquid radioactive waste processing in ANSI/ANS-55.6-1993 (2007R) and iodine removal efficiencies in RG 1.140, Revision 2 (GALE-BWR 08 & GALE-PWR0 08).
GALE-09 - PNNL performed a review of recent reactor operational experience and recommended updates (PNNL-18150 and PNNL-18957) to the GALE-08 code. The following changes were made to GALE-08 hardwired parameters in GALE-09:
  • Plant capacity factor was increased from 0.8 to 0.9 (GALE-PWR 08 & GALE-BWR 09).
  • Tritium release rate was decreased from 0.4 Ci/yr/Mwt to 0.27 Ci/yr/Mwt (GALE-PWR 08).
  • Argon-41 release rate was decreased from 34 to 6 Ci/yr (GALE-PWR 08).
  • Carbon-14 release rate was decreased from 7.3 to 5.9 Ci/yr (GALE-PWR 08).
  • Unexpected release rate was decreased from 0.16 to 1.6E-04 Ci/yr GALE-PWR 08).
  • Condensate demineralizer DF for “Other Radionuclides” was changed from 50 to 10 (GALE-PWR 08).
  • Radioiodine release rates from various buildings during normal operations were increased by multiplying by 1.125 (GALE-BWR 09).
  • Radioiodine release rates from various buildings during extended shutdown were decreased by multiplying by 0.5 (GALE-BWR 09).
  • Carbon-14 release rate was decreased from 9.5 to 10.7 Ci/yr (GALE-BWR 09).
  • Unexpected release rate was decreased from 0.1 to 1.4E-02 Ci/yr (GALE-BWR 09).
GALE-2.0 - PNNL developed a graphical user interface (GUI) for the GALE-09 code to allow greater flexibility by users, which resulted in the development of GALE-PWR 2.0 and GALE-BWR 2.0 codes. Because the updates to the GALE 2.0 source codes did not involve changes in the model formulations, the revised source code had exactly the same functionality as the GALE-09 versions with differences in the outputs reflecting only the standards and operation-derived changes in hard-code parameter values.
BW Once-thorugh Steam Generator
BWR Gaseous Radwaste Treatment Screen
BWR General Reactor Parameters screen
BWR Liquid Radwaste Treatment Screen
BWR Schematic
CE U-tube Steam Generator
Clean Waste Screen
Equipmewnt Drain Waste Screen
Fixed Parameter Text File
GALE Excel Spread Sheet
GALE-BWR 3.0 Titel screen
GALE-PWR 3.0 Title Screen
Liguid waste processing system flow stream
Miscellaneous Dirty Waste Screen
PWR General Reactor Parameters Screen
PWR Schematic
PWR Schematic
Wast Collection time, and processing and discharge time calculation screen
Westinghouse U-tube Steam Generator