Published September 1, 1976 | Version v1
Miscellaneous

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

  • 1. Savannah River Laboratory, E. I. duPont de Nemours and Company, Inc., Aiken, South Carolina 29801 (United States)

Description

1 - 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. 2 - 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. 3 - 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

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/nesc0590.html

Additional details

Publishing Information

Imprint Pagination
[html]

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41043004
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Computer Program Description, Non-conventional Literature
Descriptors DEI
COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; FAILURES; I CODES; INSPECTION; MAINTENANCE; MARKOV PROCESS; MATRICES; NUCLEAR POWER PLANTS; PERSONNEL; PROBABILITY; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY; SAFETY ANALYSIS; WEBSITES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DOCUMENT TYPES; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; SAFETY; SIMULATION; STOCHASTIC PROCESSES; THERMAL POWER PLANTS

Optional Information

Notes
1 ref.