last modified: 20-MAY-1985 | catalog | categories | new | search |

IAEA0873 CRITIC.

CRITIC, In-Core Fuel Management for CANDU PWR

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1. NAME OR DESIGNATION OF PROGRAM:  CRITIC.
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2. COMPUTERS
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Program name Package id Status Status date
CRITIC IAEA0873/01 Tested 20-MAY-1985

Machines used:

Package ID Orig. computer Test computer
IAEA0873/01 CDC CYBER 730 CDC CYBER 740
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3. DESCRIPTION OF PROBLEM OR FUNCTION

CRITIC is a one-dimensional (cylindrical r-geometry) fuel management code. It solves the two-group diffusion theory equations using a finite difference method. Apart from calculating the eigenvalue keff, it has options to determine the extrapolated height or the burnup of a particular region. For the latter option lattice parameters as a function of burnup are needed.
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4. METHOD OF SOLUTION

Finite difference method for solving the two- group diffusion equations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

            Number of mesh points            200
            Number of regions                 10
            Number of burnup steps for
            lattice parameter tabulations     80
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6. TYPICAL RUNNING TIME

About 50 seconds for the calculation of the eigenvalue for a problem having about 100 mesh points.
IAEA0873/01
NEA-DB executed the test case included in the package on CDC CYBER 740 in 168 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
IAEA0873/01 20-MAY-1985 Tested at NEADB
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10. REFERENCES:
IAEA0873/01, included references:
- K.R. Srinivasan and H.K. Bhatia:
  A Brief Writeup of the Computer Code CRITIC.
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
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11. MACHINE REQUIREMENTS:  32K of main storage.
IAEA0873/01
The test case has been executed on CDC CYBER 740 in 41,600 words (octal) of main storage (CM).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0873/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  NOS (CYBER-170).
IAEA0873/01
The test case was run on CDC CYBER 740 under NOS 1.4- 531.
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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
Computers Available in Developing Countries for In-Core Fuel
Management" of the International Atomic Energy Agency.

       P.D. Krishnani
       Bhabha Atomic Research Centre
       Theoretical Reactor Physics Section
       5th floor, Central Complex
       Trombay
       Bombay-400 085, India
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16. MATERIAL AVAILABLE
IAEA0873/01
File name File description Records
IAEA0873_01.003 INFORMATION FILE 31
IAEA0873_01.004 JOB CONTROL INFORMATION 13
IAEA0873_01.005 CRITIC SOURCE PROGRAM (FORTRAN) 634
IAEA0873_01.006 CRITIC TEST CASE INPUT DATA 27
IAEA0873_01.007 CRITIC TEST CASE PRINTED OUTPUT 485
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, diffusion, fuel management, heavy water reactor, pwr reactors.