last modified: 24-JUL-1995 | catalog | categories | new | search |

CCC-0624 DOSE-SGTR.

DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR

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1. NAME OR DESIGNATION OF PROGRAM:  DOSE-SGTR.
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2. COMPUTERS
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Program name Package id Status Status date
DOSE-SGTR CCC-0624/01 Tested 24-JUL-1995

Machines used:

Package ID Orig. computer Test computer
CCC-0624/01 IBM PC PC-80486
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

Cumulative execution time for all the DOSE-SGTR sample problems on a Northgate 486/66 was approximately five seconds.
CCC-0624/01
NEA-DB ran the test cases on a 66MHz PC/80486. Each test case required about 3 seconds of execution time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
CCC-0624/01 24-JUL-1995 Tested at NEADB
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10. REFERENCES:
CCC-0624/01, included references:
- J.P. Adams:
  Assessment of DOSE During a SGTR
  EGG-NRE-10644 (January 1993).
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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.
CCC-0624/01
NEA-DB installed the program on a 66MHz DELL 466/L PC/80486.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0624/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

Lahey F77L 5.1 was used to create the executable included in the package.
CCC-0624/01
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.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
CCC-0624/01
The program does not require the 32-bit version of the  Lahey compiler.
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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
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16. MATERIAL AVAILABLE
CCC-0624/01
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
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • R. Environmental and Earth Sciences

Keywords: iodine, pwr reactors, radioactive release, reactor safety, ruptures, steam generators.