IAEA0882 STAR.

STAR, Fuel Management of BWR

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES

[ top ]

1. NAME OR DESIGNATION OF PROGRAM: STAR.

[ top ]

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
STAR	IAEA0882/01	Tested	08-MAR-1985

Machines used:

Package ID	Orig. computer	Test computer
IAEA0882/01	CDC CYBER 730	CDC CYBER 740

[ top ]

3. DESCRIPTION OF PROGRAM OR FUNCTION

STAR is a one-group three- dimensional (x,y,z) coarse-mesh neutron diffusion theory code. It has a realistic thermal hydraulic model. The neutronic model of the code contains a kernel derived from a finite difference form of the coarse-mesh diffusion equation. Equations are written in terms of fission neutron sources rather than fluxes. One-group lattice parameters required are k-infinite and migration area as a function of burnup and steam void fraction.

The code is useful for working out control rod patterns and performing reload pattern studies for boiling water reactors (BWR). The code computes the eigenvalue (k-eff) and the power distribution using an iterative procedure.

[ top ]

4. METHOD OF SOLUTION: Coarse-mesh finite difference method.

[ top ]

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The code is written with variable dimensioning. About 20K of memory is required for the program instructions. A problem having 1700 mesh points requires about 22K for its major array size.

[ top ]

6. TYPICAL RUNNING TIME

About 45 seconds for a problem having 1700 mesh points for one converged power distribution evaluation (66 innermost iterations).

IAEA0882/01

NEA-DB executed the test case included in the package on CDC CYBER 740 in 121 CPU seconds.

[ top ]

7. UNUSUAL FEATURES OF THE PROGRAM:

[ top ]

8. RELATED AND AUXILIARY PROGRAMS:

[ top ]

9. STATUS

Package ID	Status date	Status
IAEA0882/01	08-MAR-1985	Tested at NEADB

[ top ]

10. REFERENCES:

IAEA0882/01, included references:

- R.P. Jain and V. Jagannathan:
  A Guide for the Use of Computer Code 'STAR'.
  Th.P.D./Note/302  (1984)
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)

[ top ]

11. MACHINE REQUIREMENTS

The code uses only fast memory except for basic input data.

IAEA0882/01

Main storage requirements on CDC CYBER 740 are 131,374 (octal) words.

[ top ]

12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
IAEA0882/01	FORTRAN-IV

[ top ]

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

IAEA0882/01

The test case was executed on CDC CYBER 740 under NOS 1.4-531.

[ top ]

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

This program will be released to the NEA Data Bank in the framework of the IAEA CRP on in-core fuel management programs.

[ top ]

15. NAME AND ESTABLISHMENT OF AUTHORS

This code system has been included in the Coordinated Research Programme (CRP) on "Codes Adaptable to Small and Medium-Size Com- puters Available in Developing Countries for In-Core Fuel Manage- ment" of the International Atomic Energy Agency.

          R.P. Jain
          Bhabha Atomic Research Centre
          TROMBAY, Bombay - 400 085
          India

[ top ]

16. MATERIAL AVAILABLE

IAEA0882/01

File name	File description	Records
IAEA0882_01.003	INFORMATION FILE	35
IAEA0882_01.004	SOURCE PROGRAM (FORTRAN)	1300
IAEA0882_01.005	JCL TO RUN THE TEST CASE	24
IAEA0882_01.006	TEST CASE INPUT DATA	11
IAEA0882_01.007	INPUT DATA ON UNIT 1	131
IAEA0882_01.008	INPUT DATA ON UNIT 2	18
IAEA0882_01.009	INPUT DATA ON UNIT 3	852
IAEA0882_01.010	TEST CASE PRINTED OUTPUT	540

[ top ]

17. CATEGORIES

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

Keywords: BWR reactors, diffusion equations, fuel management, one-group, power distribution, voids.