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NESC0590 INTEG/INSPEC

INTEG INSPEC, Accident Frequencies and Safety Analysis for Nuclear Power Plant

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1. NAME OR DESIGNATION OF PROGRAM:  INTEG/INSPEC
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2. COMPUTERS
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Program name Package id Status Status date
INTEG NESC0590/01 Tested 01-SEP-1976

Machines used:

Package ID Orig. computer Test computer
NESC0590/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

These programs analyze the characteristics of a general model developed to represent the safety aspects of an operating nuclear reactor. These characteristics are the frequencies of incidents that are departures from the expected behavior of the reactor. Each incident is assumed to be preceded by  a sequence of events starting at some initiating event. At each member in this sequence there may be functions such as safety circuits, and personnel operations that stop the sequence at that member. When mechanical devices fail they are assumed to remain inoperative until repaired. The model accounts for scheduled inspection and maintenance of all equipment in the system.
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4. METHOD OF SOLUTION

In INTEG, the discontinuous density function is integrated by the trapezoidal rule from time equals zero to time equals t. INSPEC is based on the simulation of reactor operation as  a Markov process. A vector of probabilities is successively multiplied by a transition matrix.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

INSPEC is limited to subsystems with no more than 7 safety circuits. The transition matrix can be made up as desired so that any intercorrelations between failures of circuits can be accommodated. In INTEG, failure rates of safety circuits are restricted to independence.
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6. TYPICAL RUNNING TIME

The INTEG sample problem containing five problems, each with 3,000 steps of trapezoidal integration and with  an average of 4.6 safety circuits, requires a total CPU time of 2 seconds on an IBM360/195, while the INSPEC sample problem with three safety circuits runs for 500 transitions with an indicated CPU time  less than 2 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
NESC0590/01 01-SEP-1976 Tested at NEADB
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10. REFERENCE

L. M. Arnett, Quantitative Analysis of Reactor Safety,
DP-1168, November 1968.
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0590/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:   OS/360.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

                 L. M. Arnett
                 Savannah River Laboratory
                 E. I. duPont de Nemours and Company, Inc.
                 Aiken, South Carolina  29801
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16. MATERIAL AVAILABLE
NESC0590/01
File name File description Records
NESC0590_01.001 INTEG SOURCE PROGRAM (F4) EBCDIC 143
NESC0590_01.002 INTEG SAMPLE PROBLEM INPUT DATA 28
NESC0590_01.003 INTEG SAMPLE PROBLEM PRITED OUTPUT 627
NESC0590_01.004 INSPEC SOURCE PROGRAM (F4) EBCDIC 159
NESC0590_01.005 INSPEC SAMPLE PROBLEM INPUT DATA 10
NESC0590_01.006 INSPEC SAMPLE PROBLEM PRINTED OUTPUT 46
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: Markov process, reactor operation, reactor safety, simulation.