RSICC CODE PACKAGE CCC-163
1. NAME AND TITLE
FISSP & CLOUD: Fission Product Inventory, Release, Transport and Dose Calculation.
AUXILIARY ROUTINES
FISSP: Fission Product Inventory Calculation.
DELTA T: Input Data Generator.
CLOUD: Kernel Integration, Atmospheric Transport and Dose Calculation.
2. CONTRIBUTOR
Sandia National Laboratories, Albuquerque, New Mexico.
3. CODING LANGUAGE AND COMPUTERS
Fortran IV; CDC 6600; IBM 360; and IBM PC (C00163MNYCP01).
4. NATURE OF PROBLEM SOLVED
FISSP calculates the fission product inventory in a (235U fueled) reactor for a specified power history. In addition, following the specified power history, FISSP computes an instantaneous point (puff) release of the fission products to the atmosphere, and continues to calculate the radioactivity history of each released fission product.
CLOUD calculates the external gamma and beta dose, and the internal dose to the lung, thyroid, gastro-intestine, bone, and whole body resulting from inhalation of the passing radioactive cloud.
5. METHOD OF SOLUTION
FISSP-CLOUD is a system of linked codes.
The method of linear chain resolution by England is used in FISSP to calculate the fission product atom density of 326 separate nuclides and metastable states for a specified series of (stepwise) power histories. The same equations are solved for zero power following the instantaneous release to the atmosphere of specified fractions of the noble gases, halogens, high temperature volatiles, and other fission products.
In CLOUD, the released nuclides are allowed to drift downwind at the average wind speed while diffusing in three dimensions as determined by the appropriate coefficients in the Sutton atmospheric diffusion equation. The external gamma and beta dose received at the dose point during cloud passage is taken to be (after Eckert) proportional to the activity concentration of each nuclide integrated over the effective exposure time and summed over all nuclides. The inhalation dose to the lung, thyroid, gastro-intestine, bone, and whole body is calculated by assuming a modified exponential body model. In this method (after Valentine) the dose to an internal organ from each nuclide is taken to be proportional to the time integral of the organ burden due to inhalation. Total organ dose is obtained by summing over-all nuclides.
6. RESTRICTIONS OR LIMITATIONS
FISSP may be used separately to calculate fission product inventories, but CLOUD requires the released nuclide radioactivity history generated by FISSP.
FISSP is restricted to 20 or less stepwise power histories by dimension statements.
Care should be taken in setting up the time base origin between FISSP and CLOUD. CLOUD requires 360 properly located values of the fission product activities from FISSP to correctly calculate the doses. Thus it is important to specify the correct final power history in FISSP.
7. TYPICAL RUNNING TIME
FISSP running time on the CDC-6600 for 3 power histories and 360 print intervals is 700 seconds. CLOUD running time on the CDC-6600 is 175 seconds.
Estimated running times of the packaged sample problems in CCC-163B, GO STEP: FISSP, 2 minutes and CLOUD, 4 minutes. The included FISSP and CLOUD test cases ran in a few seconds on a Pentium III in a DOS window of WindowsNT.
8. COMPUTER HARDWARE REQUIREMENTS
CCC-163A/FISSP-CLOUD were written for the CDC-6600, and use one tape unit (or disc). FISSP requires an 80 K (octal) memory. CLOUD requires a 65 K (octal) memory.
Version B is operable on the IBM 360/75/91 hardware configuration. This conversion was made by RSIC. Core size used: FISSP, 140 K and CLOUD, 126 K.
Version C runs in a personal computer. All three versions are distributed on a single diskette.
9. COMPUTER SOFTWARE REQUIREMENTS
Version A requires a CDC Fortran IV compiler. For Version B, the codes are operable on the IBM-360/75/91 Operating System using OS-360 Fortran H Compiler. Standard input, output and logical unit 7 tape assignments are used. The included PC executables were created at RSICC on a Pentium III running Windows98 with the Digital Visual Fortran 5 compiler. No additional software is required to run the PC version.
10. REFERENCES
a. Included in package:
FISSP Update Statement, Sandia National Laboratories (May 1972).
Errata to SC-RR-70-338, Sandia National Laboratories (May 1972).
Helpful Hints on Operation of FISSP and CLOUD.
L. L. Bonzon and J. B. Rivard, "Computational Method for Calculation of Radiological Dose Resulting from Hypothetical Fission Product Release," SC-RR-70-338 (July 1970) and supplementary material.
b. Background information:
T. R. England, "Cinder - A One Point Depletion and Fission Product Program, U. W. Version," Bettis Atomic Power Laboratory, WAPD-TM-334 (1962, revised 1968).
T. R. England, "An Investigation of Fission Product Behavior and Decay Heating in Nuclear Reactors," Ph.D. Thesis, University of Wisconsin (1969).
O. G. Sutton, Micrometeorology, New York, McGraw-Hill Book Co., Inc. (1953).
R. J. Eckert, "A Fortran Program for the Calculation of the Potential Hazards from an Accidental Fission-Product Release - MO142," Bettis Atomic Power Laboratory, WAPD-TM-348 (1964).
D. R. Connors, H. J. Litke, and D. S. Rampolla, "Identification of Important Fission Product Nuclides for Radiological Dose Calculations Following a Uranium 235 - Fueled Reactor Accident," Bettis Atomic Power Laboratory, WAPD-TM-599 (1967).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document (10.a) and one DS/HD diskette which contains the source codes, PC executables and sample problem input and output written in compressed, self-extracting Windows files.
12. DATE OF ABSTRACT
June 1972; revised December 1984; September 1991, and July 2001.
KEYWORDS: FISSION PRODUCTS; KERNEL; GAMMA-RAY; AIRBORNE