last modified: 08-MAR-1985 | catalog | categories | new | search |

IAEA0882 STAR.

STAR, Fuel Management of BWR

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1. NAME OR DESIGNATION OF PROGRAM:  STAR.
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2. COMPUTERS
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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
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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.
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4. METHOD OF SOLUTION:  Coarse-mesh finite difference method.
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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.
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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.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
IAEA0882/01 08-MAR-1985 Tested at NEADB
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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)
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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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0882/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
IAEA0882/01
The test case was executed on CDC CYBER 740 under NOS 1.4-531.
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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.
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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
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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
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

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