IAEA0873 CRITIC.

CRITIC, In-Core Fuel Management for CANDU PWR

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: 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.