Use of bayesian method for NPP equipment components reliability parameters estimation
Description
This articles is representing the development of modified method of NPP components reliability parameters Bayesian estimation. The necessity of such a development consists in questionable accuracy of Bayesian estimation used in Zaporizhzha unit 5 ISA. An old approach to Bayesian analysis converts the continuous probability distribution into a truncated discrete probability distribution (this is called the 'DPD approach'). In contrast, using the modified method based on numerical integration methods one can obtain specified accuracy. The correspondent software has been developed for on-line calculation of reliability parameters via Internet. The results, obtained by modified Bayesian estimation, have been compared with ZISA reliability parameters calculation results. The considerable difference in some significant failure rates has been obtained. Such a difference can lead to significant change of PRA final result: core damage frequency
Additional details
Additional titles
- Original title (Ukrainian)
- Zastosuvannya Bajjesyivs'kogo pyidkhodu dlya otsyinki parametryiv nadyijnostyi elementyiv obladnannya AES
Publishing Information
- Journal Title
- Yadernaya i Radiatsionnaya Bezopasnost'
- Journal Volume
- 7
- Journal Issue
- 2
- Journal Page Range
- p. 94-97
- ISSN
- 1608-2214
Conference
- Title
- Conference of the Ukrainian Nuclear Society 'Youth to Nuclear Power'
- Original Conference Title
- Konferentsiya UYaO 'Molodezh' - yadernoj ehnergetike'
- Dates
- 1-3 Jul 2004
- Place
- Sevastopol' (Ukraine)
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 36086750
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DATA PROCESSING; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RELIABILITY; SAFETY ANALYSIS; SYSTEM FAILURE ANALYSIS; ZAPOROZHE-5 REACTOR
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PROCESSING; PWR TYPE REACTORS; REACTORS; SAFETY; SIMULATION; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS