CCC-0382 RIBD-IRT.

RIBD-IRT, Isotope Buildup and Isotope Decay from Fission Source

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: RIBD-IRT.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
RIBD-IRT	CCC-0382/01	Tested	23-JAN-1990

Machines used:

Package ID	Orig. computer	Test computer
CCC-0382/01	UNIVAC 1100	CDC CYBER 830

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3. DESCRIPTION OF PROBLEM OR FUNCTION

RIBD-IRT calculates isotopic concentrations resulting from two fission sources with normal down- chain decay by beta emission and isomeric transfers and inter-chain coupling resulting from (n,gamma) reactions. Calculations can be made to follow an irradiation history through an unlimited number of step changes of unrestricted duration and variability including shutdown periods, restarts at different power levels and/or any other level changes. In addition, the program permits to track and modify the concentration of individual elements as they decay with time following reactor shutdown. Tracking individual elements en- ables one to estimate time-dependent source terms for a hypothetical LOCA based on known or postulated fission product release mecha- nisms.

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4. METHOD OF SOLUTION

RIBD-IRT is a grid processor. It organizes the various members described by the fission product library data into a grid with the various linkages established from chain branching data, yield data, and neutron capture cross sections with their branching ratios. Radioactive decay includes not only the simple member-to-member cascade but also the more complex forms where branching may be partiallly or completely skip one or two interven- ing members.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME:

CCC-0382/01

NEA-DB ran the test cases included in this package on a CDC CYBER 830 computer. CPU times required were: 18 secs (case 1); 46 secs (case 2).

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS

ZIP converts an ASCII ENDFB/IV tape to binary form compatible with RIBD-IRT.

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9. STATUS

Package ID	Status date	Status
CCC-0382/01	23-JAN-1990	Tested at NEADB

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10. REFERENCES

- N.A. Lurie, D.H. Houston, J.A. Naber:
  Definition of Loss-of-Coolant Accidnet Radiation Source: Summary
  and Conclusions
  IRT 8167-004, SAND78-0091 (March 1978)

CCC-0382/01, included references:

- D.D. Thayer and N.A. Lurie:
  A User's Manual for Computer Code RIBD/IRT.
  IRT 6406-003  (January 1982)
- D.R. Marr:
  A User's Manual for Computer Code RIBD-II, A Fission Product
  Inventory Code.  HEDL-TME-75-26  (January 1975)

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11. MACHINE REQUIREMENTS:

CCC-0382/01

174,600 (octal) words of CDC CYBER 830 main storage.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
CCC-0382/01	FORTRAN-IV

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

CCC-0382/01

NOS2.5.1 (CDC CYBER830) with compiler FTN 4.8.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Three working files are required:
Logical Unit 29: Reads unformatted fission product library
27: Scratch file
28: Scratch file

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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by:  Radiation Safety Information Computational Center
                 Oak Ridge National Laboratory
                 Oak Ridge, Tennessee, U.S.A.
Developed by:    IRT Corporation, San Diego, California
                 Sandia National Laboratories, Albuquerque, New Mexico.

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16. MATERIAL AVAILABLE

CCC-0382/01

File name	File description	Records
CCC0382_01.001	Information file	59
CCC0382_01.002	JCL and control information	16
CCC0382_01.003	ZIP FORTRAN source	37
CCC0382_01.004	RIBD Nuclear Data Library	4094
CCC0382_01.005	RIBD-IRT FORTRAN source	1870
CCC0382_01.006	RIBD-IRT sample problem input 1	14
CCC0382_01.007	RIBD-IRT sample problem input 2	13
CCC0382_01.008	RIBD-IRT sample problem output 1	502
CCC0382_01.009	RIBD-IRT sample problem output 2	5177

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17. CATEGORIES

D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: buildup, decay, fission products, irradiation, isotope production, loss-of-coolant accident, reactor operation.