CCC-0624 DOSE-SGTR.

1. NAME OR DESIGNATION OF PROGRAM:  DOSE-SGTR.

3. DESCRIPTION OF PROGRAM OR FUNCTION

The Nuclear Regulatory Commission requires utilities to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the iodine concentration in the reactor coolant system (RCS) due to iodine spikes, primary flashing  and bypass fractions, and iodine partitioning in the secondary coolant system (SCS). Experimental and analytical investigations have recently been completed wherein these assumptions were tested to determine whether and to what degree they were conservative (that is, whether they result in a calculated iodine source term/dose that is at least as large or larger than that expected during an actual event). The current study has the objective to assess the overall effects of the results of these investigations on the calculated iodine dose to the environment during an SGTR. DOSE-SGTR was written to assist in this study.

4. METHOD OF SOLUTION

DOSE-SGTR uses a simple, non-mechanistic model  to calculate the iodine source term to the environment during a steam generator tube rupture as a function of water mass inventories and flow rates and iodine concentrations in the reactor coolant system and secondary coolant system.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.

6. TYPICAL RUNNING TIME

Cumulative execution time for all the DOSE-SGTR sample problems on a Northgate 486/66 was approximately five seconds.

NEA-DB ran the test cases on a 66MHz PC/80486. Each test case required about 3 seconds of execution time.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:

10. REFERENCES:

- J.P. Adams:
  Assessment of DOSE During a SGTR
  EGG-NRE-10644 (January 1993).

11. MACHINE REQUIREMENTS

The system runs on an IBM PC or compatible equipped with a math co-processor running MS DOS 3.1 or higher. A
hard disk is not required.

NEA-DB installed the program on a 66MHz DELL 466/L PC/80486.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

Lahey F77L 5.1 was used to create the executable included in the package.

NEA-DB tested the program under MS-DOS 6.20. The source program was compiled using the Lahey Extended Memory Compiler F77L-EM/32 Version 5.20.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

The program does not require the 32-bit version of the  Lahey compiler.

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:
                Idaho National Engineering Laboratory
                Idaho Falls, Idaho, USA

File name	File description	Records
CCC0624_01.001	information file	120
CCC0624_01.002	DOSE-SGTR source file	118
CCC0624_01.003	to compile and link DOSE-SGTR	15
CCC0624_01.004	DOSE-SGTR executable	0
CCC0624_01.005	Lahey compiler run-time error messages	0
CCC0624_01.006	to run all seven sample problems "TESTxA"	21
CCC0624_01.007	sample input	14
CCC0624_01.008	sample input problem 1A	14
CCC0624_01.009	sample input problem 2A	14
CCC0624_01.010	sample input problem 3A	14
CCC0624_01.011	sample input problem 4A	14
CCC0624_01.012	sample input problem 5A	14
CCC0624_01.013	sample input problem 6A	14
CCC0624_01.014	sample input problem 7A	14
CCC0624_01.015	sample output	14
CCC0624_01.016	sample output problem 1A	14
CCC0624_01.017	sample output problem 2A	14
CCC0624_01.018	sample output problem 3A	14
CCC0624_01.019	sample output problem 4A	14
CCC0624_01.020	sample output problem 5A	15
CCC0624_01.021	sample output problem 6A	14
CCC0624_01.022	sample output problem 7A	14
CCC0624_01.023	DOS file-names	22