CCC-0463 GASPAR-II.

1. NAME OR DESIGNATION OF PROGRAM:  GASPAR-II

3. DESCRIPTION OF PROGRAM OR FUNCTION

GASPAR implements the air release dose models of the NRC Regulatory Guide 1.109 for noble gases (semi-infinite plume only) and the radioiodine and particulate emissions.
GASPAR computes both population (ALARA-As Low As Reasonably Achievable and NEPA-National Environmental Policy Act) and individual doses. Site data, meteorological data, radionuclide release source terms, and location meteorological data for selected  individuals are specified as input data. The site data includes population data and milk, meat, and vegetation production. The meteorological data includes dispersion X/Q, X/Q decayed, X/Q decayed and depleted, and deposition. Population doses, individual doses, and cost benefit tables are calculated.

4. METHOD OF SOLUTION

There are two basic types of calculations, the  population dose calculation and the individual dose calculation; however, both may be combined in a single GASPAR execution. There are usually several source terms corresponding to several release points. As the dose is computed for each source term it is accumulated so that the dose printed for the first source term is the actual dose for that term. For all subsequent source terms the dose printed is the accumulated dose with the dose printed for the last source term, the grand total for the problem. For the cost benefit table, individual source term doses are generated. Seven pathways by which the nuclides travel to man are considered. These are plume, ground, inhalation, vegetation, cows' milk, goats' milk,  and meat. For the individual dose calculations, man is subdivided into the four age groups of infant (0 to 1 year), child (1-11 years), teenager (12-18 years) and adult (over 18 years). Each of these calculations take into account eight body organs - T. body, G.I. track, bone, liver, kidney, thyroid, lung, and skin.

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

6. TYPICAL RUNNING TIME

Each of the four sample problems required less than one second to execute, using the OS/VS2 operating system on the IBM 3033. On the VAX 8600 the sample problems took about 25 seconds each.

NEA-DB compiled and executed the three test cases included in this package on a DEC VAX 6000-510 computer. Each of the cases ran in less than 3 seconds of CPU time.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS

The IBM version of this code package contains the GASPAR source. In the VAX version no changes were made in the mathematical models, but some parameter values and  dose factors were updated. The VAX version reads dose rate conversion factors from the same data file as that used in CCC-363/LADTAP II, which contains data for data for 169 radionuclides. A summary of the changes are included in Appendix C
of NUREG/CR-4563.

10. REFERENCES

- D.M. Hamby:
Verification of the Gaspar dose assessment module used in Maxigasp    and Popgasp
  WSRC-RP--92-418

- K.F. Eckerman, F.J. Congel, A.K. Roecklein, W.J. Pasciak:
  User's Guide to GASPAR Code
  NUREG-0597 (June 1980).
- D.L. Strenge, T.J. Bander and J.K. Soldat:
  GASPAR II Technical Reference and User Guide
  NUREG/CR-4653, PNL-5907 (March 1987).
- K.F. Eckerman, F.J. Congel, A.K. Roecklein, W.J. Pasciak:
  User's Guide to GASPAR Code
  NUREG-0597 (June 1980).
- D.L. Strenge, T.J. Bander and J.K. Soldat:
  GASPAR II Technical Reference and User Guide
  NUREG/CR-4653, PNL-5907 (March 1987).

11. MACHINE REQUIREMENTS

The storage requirement is 366K and 260K to execute sample problems on the IBM 3033.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

A FORTRAN IV compiler is required for the IBM version. RSIC used the VAX VMS FORTRAN compiler (version 4.6) on the VAX 8600 to execute the sample cases.

VAX/VMS V5.4.2.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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: Office of Nuclear Reactor Regulation
              U.S. Nuclear Regulatory Commission
              Washington, D.C., USA

              Pacific Northwest Laboratory
              Richland, Washington, USA

source program   mag tapeGASPAR dose code (FORTRAN IV)              SRCTP
test-case data   mag tapeGASPAR sample prob #1 (Individual Dose)    DATTP
test-case data   mag tapeGASPAR sample prob #2 (Population Dose)    DATTP
test-case data   mag tapeGASPAR sample prob #3 (Block Data)         DATTP
test-case data   mag tapeGASPAR sample prob #4 (Gen. Dose Factors)  DATTP
test-case output mag tapeGASPAR sample output prob #1               OUTTP
test-case output mag tapeGASPAR sample output prob #2               OUTTP
test-case output mag tapeGASPAR sample output prob #3               OUTTP
test-case output mag tapeGASPAR sample output prob #4               OUTTP
test-case data   mag tapeDose Factors for Block Data from prob #4   DATTP
report                   NUREG-0597 (June 1980)                     REPPT
report                   NUREG/CR-4653, PNL-5907 (March 1987)       REPPT

File name	File description	Records
CCC0463_03.001	Information file	50
CCC0463_03.002	Command file to run problem 1	6
CCC0463_03.003	Command file to run problem 2	7
CCC0463_03.004	Command file to run problem 3	6
CCC0463_03.005	GASPAR-II FORTRAN source (1/91)	6106
CCC0463_03.006	Sample1 problem input 1	65
CCC0463_03.007	Sample1 problem input 2	74
CCC0463_03.008	Sample1 problem input 3	36
CCC0463_03.009	LSDTAP II library data	2205
CCC0463_03.010	XOQDOQ2 INPUT DATA	271
CCC0463_03.011	Sample problem output 1	2520
CCC0463_03.012	Sample problem output 2	1362
CCC0463_03.013	Sample problem output 3	3594
CCC0463_03.014	XOQDOQ2 sample output (original file)	341