Abstract
For the probabilistic approach to reactor safety assessment by the use of event tree and fault tree techniques it is essential to be able to estimate the probabilities of failure of the various engineered safety features provided to mitigate the effects of postulated accident sequences. The PREP, KITT and SAMPLE computer codes, which incorporate Kinetic Tree Theory, perform these calculations and have been used extensively to evaluate the reliability characteristics of engineered safety features of American nuclear reactors. Working versions of these computer codes are now available in SRD, and this report explains the merits, capabilities and ease of application of the PREP, KITT, and SAMPLE programs for the solution of system reliability problems.
Citation Formats
Shaw, P, and White, R F.
Appraisal of the PREP, KITT, and SAMPLE computer codes for the evaluation of the reliability characteristics of engineered systems.
United Kingdom: N. p.,
1976.
Web.
Shaw, P, & White, R F.
Appraisal of the PREP, KITT, and SAMPLE computer codes for the evaluation of the reliability characteristics of engineered systems.
United Kingdom.
Shaw, P, and White, R F.
1976.
"Appraisal of the PREP, KITT, and SAMPLE computer codes for the evaluation of the reliability characteristics of engineered systems."
United Kingdom.
@misc{etde_8187419,
title = {Appraisal of the PREP, KITT, and SAMPLE computer codes for the evaluation of the reliability characteristics of engineered systems}
author = {Shaw, P, and White, R F}
abstractNote = {For the probabilistic approach to reactor safety assessment by the use of event tree and fault tree techniques it is essential to be able to estimate the probabilities of failure of the various engineered safety features provided to mitigate the effects of postulated accident sequences. The PREP, KITT and SAMPLE computer codes, which incorporate Kinetic Tree Theory, perform these calculations and have been used extensively to evaluate the reliability characteristics of engineered safety features of American nuclear reactors. Working versions of these computer codes are now available in SRD, and this report explains the merits, capabilities and ease of application of the PREP, KITT, and SAMPLE programs for the solution of system reliability problems.}
place = {United Kingdom}
year = {1976}
month = {Jan}
}
title = {Appraisal of the PREP, KITT, and SAMPLE computer codes for the evaluation of the reliability characteristics of engineered systems}
author = {Shaw, P, and White, R F}
abstractNote = {For the probabilistic approach to reactor safety assessment by the use of event tree and fault tree techniques it is essential to be able to estimate the probabilities of failure of the various engineered safety features provided to mitigate the effects of postulated accident sequences. The PREP, KITT and SAMPLE computer codes, which incorporate Kinetic Tree Theory, perform these calculations and have been used extensively to evaluate the reliability characteristics of engineered safety features of American nuclear reactors. Working versions of these computer codes are now available in SRD, and this report explains the merits, capabilities and ease of application of the PREP, KITT, and SAMPLE programs for the solution of system reliability problems.}
place = {United Kingdom}
year = {1976}
month = {Jan}
}