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

IAEA0872 TACHY.

TACHY, BWR Fuel Management by 2-D Coarse Mesh Neutron Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  TACHY.
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2. COMPUTERS
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Program name Package id Status Status date
TACHY IAEA0872/01 Tested 08-MAR-1985

Machines used:

Package ID Orig. computer Test computer
IAEA0872/01 CDC CYBER 730 CDC CYBER 740
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3. DESCRIPTION OF PROBLEM OR FUNCTION

TACHY solves the one-group two-dimensional coarse-mesh neutron diffusion equation. Average void fraction for each channel is obtain through power-void correlations  which need to be obtained only once for a particular BWR by performing a few three-dimensional simulations.

The code has been developed for rapid analysis of reload patterns for BWRs which are analyzed using Haling's principle.
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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 useful only for analyzing reload patterns and assumes all control rods to be out.
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6. TYPICAL RUNNING TIME

About 3 seconds for analyzing one reload pattern considering 70 mesh points.
IAEA0872/01
NEA-DB executed the test case included in the package on CDC CYBER 740 in 11.22 seconds of CPU time.
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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
IAEA0872/01 08-MAR-1985 Tested at NEADB
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10. REFERENCES:
IAEA0872/01, included references:
- R.P. Jain and V. Jagannathan:
  A Two Dimensional BWR Simulation Model for Rapid Reload Pattern
  Studies.  B.A.R.C./I-718  (1982)
- R.P. Jain and V. Jagannathan:
  Manager's Manual cum Guide for the Use of Computer Code 'TACHY'.
  T.R.P.S./Note/297  (May 1982)
- 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.
IAEA0872/01
To run the test case on CDC CYBER 740, 60,500 (octal) words of main storage (CM) were required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0872/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NOS 1.4 L-552/552.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

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
       Theoretical Reactor Physics Section
       Trombay
       Bombay-400 085, India
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16. MATERIAL AVAILABLE
IAEA0872/01
File name File description Records
IAEA0872_01.003 INFORMATION FILE 32
IAEA0872_01.004 JCL TO RUN THE TEST CASE 14
IAEA0872_01.005 TACHY SOURCE PROGRAM (FORTRAN-4) 654
IAEA0872_01.006 TACHY TEST CASE INPUT DATA FROM UNIT 5 14
IAEA0872_01.007 TACHY TEST CASE INPUT DATA FROM UNIT 9 44
IAEA0872_01.008 TACHY TEST CASE PRINTED OUTPUT 657
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: BWR reactors, coarse mesh, diffusion equations, fuel management, power distribution, two-dimensional, voids.