RSICC CODE PACKAGE CCC-681
1. NAME AND TITLE
RATAF: Code System for the Radioactive Liquid Tank Failure Study.
2. CONTRIBUTORS
U. S. Nuclear Regulatory Commission, Washington, D.C., through the Energy Science Technology Software Center, Oak Ridge, TN.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; IBM 3033 and IBM PS/2 (C00681IMFPC01).
4. NATURE OF PROBLEM SOLVED
RATAF calculates the consequences of radioactive liquid tank failures. In each of the processing systems considered, RATAF can calculate the tank isotopic concentrations in either the collector tank or the evaporator bottoms tank.
5. METHOD OF SOLUTION
The activity of the shim bleed wastes is based on the primary coolant letdown system effluent activity. Input activities are based on the weighted average activity of the composite stream entering the waste collection tanks. The tank factors provide the capability to consider radionuclide removal by demineralizers or other treatment equipment prior to the tank. For evaporator bottoms tanks, the tank factors provide the capability to consider the effects of radionuclide concentration in the evaporator.
6. RESTRICTIONS OR LIMITATIONS
Maximum of 800 nuclides.
7. TYPICAL RUNNING TIME
NESC executed the sample problem in 1.5 minutes on an IBM PS/2 Model 70 with a math coprocessor, and 6.5 minutes on a Compaq 386s without a math coprocessor.
8. COMPUTER HARDWARE REQUIREMENTS
300 Kbytes of memory are required to execute the program on an IBM mainframe. RSICC tested the package on an IBM 9672 and on a Pentium in a DOS Window of Windows95.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran 77 compiler is required on the mainframe. RATAF was compiled and tested at RSICC on an IBM Mainframe 9672 Model 52 running MVS/ESA 4.2.2 and OS/390 Version 1.3 using VS Fortran 2.5.0. The PC version was tested on a Dell Pentium 100 in a DOS window under Windows 95. An executable is included with the PC version of the code, which was originally packaged by NESC in July 1989. The mainframe version of RATAF was originally packaged by NESC in 1983 then transferred to ESTSC and then to RSICC. No changes were made to the package when it was transferred to RSICC in 1999.
10. REFERENCES
10.a) Included in documentation:
L. Eyberger, "RATAF, NESC No. 1004, RATAF Tape Description and Sample Problem Input," National Energy Software Center Note 83-25 (July 28, 1989).
J.S. Boegli, R.R. Bellamy, W.L. Britz, and R.L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
10.b) Background information:
F.P. Cardile and R.R. Bellamy, Ed., "Calculation of Releases of Radioactive Materials in Gaseous Liquid Effluents from Boiling Water Reactors (BWR-GALE Code)," NUREG-0016, Revision 1 (January 1979).
"Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)," NUREG-0017 (April 1976).
M.J. Bell, "ORIGEN, The ORNL Isotope Generation and Depletion Code," ORNL-4628 (May 1973).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents in (10.a) and one DS/HD diskette which includes the Fortran source, sample problem input and output, and an executable for the PC version.
12. DATE OF ABSTRACT
September 2000, revised January 2001.
KEYWORDS: ENVIRONMENTAL DOSE; FISSION PRODUCT INVENTORY; NUCLIDE TRANSPORT; RADIOLOGICAL SAFETY; RADIOACTIVITY RELEASE