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CCC-0761 RSAC-7.

RSAC-7, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release

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1. NAME OR DESIGNATION OF PROGRAM:  RSAC-7 (RSAC 7.0.3)
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2. COMPUTERS
To submit a request for this package, please contact the liaison officer in your institution. Rules for requesters are available here.
Program name Package id Status Status date
RSAC-7 CCC-0761/01 Arrived 21-APR-2010

Machines used:

Package ID Orig. computer Test computer
CCC-0761/01 PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. RSAC-7 calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. It can model the downwind dispersion of the activity; and calculate doses to downwind individuals.
   
Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. More information is available on the developers' website http://www.inl.gov/rsac/.
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4. METHODS

A fission product inventory can be calculated from reactor operating history and can be used to simulate a nuclear criticality accident. Radionuclide inventories can also be directly input into RSAC-7 if desired. Source term modeling allows for complete progeny ingrowth and decay during all accident phases. RSAC-7 release scenario modeling allows fractionation of the inventory by chemical group or element.  RSAC-7 also models the effects of high-efficiency particulate air (HEPA) filters or other cleanup systems. RSAC-7's meteorological capabilities include Gaussian plume diffusion for Pasquill-Gifford, Hilsmeier-Gifford, and Markee models. RSAC-7 possesses the unique ability to model Class F fumigation conditions. Optionally, users can      supply plume standard deviations (ss) or atmospheric diffusion (./Qs) to the code as input data. RSAC-7 also includes corrections for deposition (wet and dry) plume rise (jet and buoyant), resuspension, and release in a room and building wake. Doses are calculated through inhalation, immersion, ground surface, and ingestion pathways, and cloud gamma dose from semi-infinite plume model and finite plume model.
  
RSAC 7 calculates internal dose using the dose conversion factors and methodology from both ICRP 26/30 and ICRP 60/68/72. In addition to the calculation of lifetime dose, RSAC 7 calculates the acute 24 hour dose from radiological sabotage events. RSAC 7 is an excellent tool to evaluate accident conditions in emergency response scenarios and to evaluate of safety basis accident conditions.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

RSAC-7 calculates inventories for fission products only. The nuclear data library contains selected activation products, actinides, and the daughters of actinides in addition to the fission products.
  
Inventories for activation products and actinides are not calculated by RSAC-7; however, they can be added to the inventory by using the radionuclide direct input section of the program. Subsequent sections of the program calculate the radioactive decay and doses from these additional radionuclides.
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6. TYPICAL RUNNING TIME

The running time for RSAC-7 is dependent on the complexity of the run and the speed of the personal computer used.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0761/01 21-APR-2010 Masterfiled Arrived
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10. REFERENCES
CCC-0761/01, included references:
- B. J. Schrader:
Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users' Manual,
INL/EXT-09-15275, Revision 0 (March 2009)
- "DOE STANDARD, Hazard Categorization and Accident Analyses Techniques for
Compliznce with DOE Order 5480.23, Nuclear Safety Analysis Reports,"
DOE-STD-1027-92 (December 1992), Change Notice No. 1 (September 1997)
- "DOE STANDARD, Preparation Guide for U.S.Department of Energy Nonreactor
Nuclear Facility Documented Safety Analyses," DOE-STD-3009-94 (July 1994),
Change Notice No. 1 (January 2000), Change Notice No. 2 (April 2002)
- "DOE HANDBOOK - Airborne Release Fractions/Rates and Respirable Fractions for
Nonreactor Nuclear Facilities, Volume I - Analysis of Experimental Data,"
DOE-HDBK-3010-94 (December 1994)
- "DOE HANDBOOK - Airborne Release Fractions/Rates and Respirable Fractions for
Nonreactor Nuclear Facilities, Volume I - Analysis of Experimental Data,"
DOE-HDBK-3010-94 (December 1994), Change Notice No. 1 (March 2000)
- "DOE HANDBOOK Airborne Release Fractions/Rates and Respirable Fractions for
Nonreactor Nuclear Facilities, Volume II - Appendices" DOE-HDBK-3010-94
(December 1994)
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11. HARDWARE REQUIREMENTS

RSAC-7 runs on Pentium computers under Windows operating systems. It was tested at RSICC on a Pentium 4 running Windows XP sp3.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0761/01 FORTRAN-77, VISUAL BASIC
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13. SOFTWARE REQUIREMENTS

RSAC-7 is programmed in Fortran 77 using the Lahey compiler. The source files are not included in this distribution. Only binary copies of RSAC-7 and its libraries are issued to users to prevent user changes to the program that would invalidate the extensive validation and verification. Each page of output contains the program version number, the program serial number, and the date and time the run was made. RSAC was validated for the Windows XP platform.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Shielding Information Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Idaho National Laboratory, Idaho Falls, Idaho, U. S. A.
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16. MATERIAL AVAILABLE
CCC-0761/01
RSAC-7 executable files
test cases
electronic documentation
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: airborne, dose rates, earth atmosphere, fission products, internal dose, kernels, radioactivity, radiological safety.