last modified: 01-APR-1979 | catalog | categories | new | search |

NEA-0470 ANSCLAD-1.

ANSCLAD-1, Creep Strain in Fuel Pin Zircaloy Clad During Temperature Transient

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1. NAME OR DESIGNATION OF PROGRAM:  ANSCLAD-1.
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2. COMPUTERS
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Program name Package id Status Status date
ANSCLAD-1 NEA-0470/01 Tested 01-APR-1979

Machines used:

Package ID Orig. computer Test computer
NEA-0470/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The calculation of creep strain in the zircaloy cladding of a fuel pin during a temperature transient, for a given fixed internal pressure and external pressure transient. The model assumes ductile behaviour of the material and does not predict rupture.
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4. METHOD OF SOLUTION

The transient is divided into a series of small  time steps during which the strain rate equations are integrated.
The size of time steps is generated by the program to minimise any error in the integration.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The equations used have not been validated above temperatures of 1300 degrees C. The transient data is limited to 100 data points.
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6. TYPICAL RUNNING TIME

For a typical water reactor transient during a LOCA, lasting 5 minutes, the program will find the total strain in approximately 20 seconds. When finding a value of pin internal pressure to give a set value of strain, the case will take apprximately 1.2 minutes.
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7. UNUSUAL FEATURES OF THE PROGRAM

The model used will calculate strain in both inert and in steam conditions surrounding the tube for any temperature range (but see 5. Restrictions). The program will also find the pin internal pressure to give a fixed value of strain.
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0470/01 01-APR-1979 Tested at NEADB
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10. REFERENCES
NEA-0470/01, included references:
- B.A. Keen:
  ANSCLAD1 - A Program for Calculating Strain in Zircaloy Fuel Pins
  During a Temperature Excursion
  ANS Report No. 122 (July 1976, Rev. 1, November 1976).
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11. MACHINE REQUIREMENTS:  Core size required is 7.5 k.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0470/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  Standard
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

    B.A. Keen
    Associated Nuclear Services
    123 High Street
    Epsom, Surrey U.K.
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16. MATERIAL AVAILABLE
NEA-0470/01
File name File description Records
NEA0470_01.002 SOURCE PROGRAM (F4,EBCDIC) 1773
NEA0470_01.003 JCL 32
NEA0470_01.004 SAMPLE PROBLEM INPUT DATA 34
NEA0470_01.005 SAMPLE PROBLEM PRINTED OUTPUT 300
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17. CATEGORIES
  • I. Deformation and Stress Distributions, Structural Analysis and Engineering Design Studies

Keywords: cladding, creep, fuel elements, pressure, strains, stress analysis, temperature, transients, zircaloy.