TY - GEN
T1 - Fast flux test facility experience relevant to advanced reactor enhanced risk monitoring
AU - Wootan, D. W.
AU - Ramuhalli, P.
AU - Coles, G. A.
AU - Hirt, E. H.
AU - Brass, M. F.
PY - 2015
Y1 - 2015
N2 - An initial methodology for enhanced risk monitors (ERMs) integrates real-time information about equipment condition and probability of failure into risk monitors to provide an assessment of dynamic risk as plant equipment ages. An important aspect of ERM is the inclusion of uncertainty within the ERM framework. Several sources of uncertainty exist when estimating the probability of failure, including uncertainty regarding the specific condition of the component, uncertainty in the probability of failure, and uncertainty in the time-to-failure. One way to address these sources of ERM uncertainty is through evaluation of real plant data. The Fast Flux Test Facility (FFTF) was the most recent Liquid Metal Reactor (LMR) to operate in the United States. The FFTF is located on the U.S. Government's Department of Energy Hanford Site near Richland, Washington, and was operated successfully from 1982 to 1992. Safe, reliable, and economic operation of the FFTF was achieved through administrative controls, technical specifications, and operating procedures, even with a demanding test schedule as a liquid metal irradiation test reactor. The high level of operating efficiency of FFTF is a potential source of vital data on the performance of liquid sodium as a safe and efficient heat transport medium that confirm the reliability of many of its large-scale components. The ten years of successful operation of the FFTF provided a very useful framework that could potentially be used for determining the reliability of LMR technology components. A potential advantage of raw data sources like FFTF is the ability to track component reliability over time. FFTF sources of reliability data are being compiled and evaluated for applicability. Processed component failure rate information has been utilized in developing the simplified ERM framework model. FFTF component reliability data is being evaluated as a way to validate the proposed methodology for ERM.
AB - An initial methodology for enhanced risk monitors (ERMs) integrates real-time information about equipment condition and probability of failure into risk monitors to provide an assessment of dynamic risk as plant equipment ages. An important aspect of ERM is the inclusion of uncertainty within the ERM framework. Several sources of uncertainty exist when estimating the probability of failure, including uncertainty regarding the specific condition of the component, uncertainty in the probability of failure, and uncertainty in the time-to-failure. One way to address these sources of ERM uncertainty is through evaluation of real plant data. The Fast Flux Test Facility (FFTF) was the most recent Liquid Metal Reactor (LMR) to operate in the United States. The FFTF is located on the U.S. Government's Department of Energy Hanford Site near Richland, Washington, and was operated successfully from 1982 to 1992. Safe, reliable, and economic operation of the FFTF was achieved through administrative controls, technical specifications, and operating procedures, even with a demanding test schedule as a liquid metal irradiation test reactor. The high level of operating efficiency of FFTF is a potential source of vital data on the performance of liquid sodium as a safe and efficient heat transport medium that confirm the reliability of many of its large-scale components. The ten years of successful operation of the FFTF provided a very useful framework that could potentially be used for determining the reliability of LMR technology components. A potential advantage of raw data sources like FFTF is the ability to track component reliability over time. FFTF sources of reliability data are being compiled and evaluated for applicability. Processed component failure rate information has been utilized in developing the simplified ERM framework model. FFTF component reliability data is being evaluated as a way to validate the proposed methodology for ERM.
KW - Advanced small modular reactors
KW - Enhanced Risk Monitors
KW - Fast Flux Test Facility
UR - http://www.scopus.com/inward/record.url?scp=84946198208&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84946198208
T3 - 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015
SP - 714
EP - 721
BT - 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015
PB - American Nuclear Society
T2 - 9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015
Y2 - 22 February 2015 through 26 February 2015
ER -