Published 1987
| Version v1
Book
Advanced human reliability analysis methodology and applications
Creators
- 1. Imatran Voima Oy, Helsinki (Finland)
- 2. Imatran Voima Oy, Loviisa (Finland)
Description
The human reliability analysis is an integral part of the probabilistic safety assessment for Loviisa 1 NPS. Up to date techniques are used for the three main categories of human failures: pre-accident, post-accident and transient initiating errors. Advancements and plant specific modifications have been made to some state of the art techniques applied in previous PSA studies. The basic error probability of pre-accident errors is modified by error dependency and recovery factors. The probability of diagnosis error is evaluated using an asymmetric confusion matrix and plant specific time-reliability curves. Plant specific human reliability data have been collected and utilized in human error identification and quantification. (orig.)
Additional details
Publishing Information
- Publisher
- Verl. TUEV Rheinland.
- Imprint Place
- Koeln (Germany, F.R.)
- ISBN
- 3-88585-417-1
- Imprint Title
- Probabilistic safety assessment and risk management PSA '87. Vol. 1
- Imprint Pagination
- 424 p.
- Series
- Risk and safety.
- Journal Page Range
- p. 104-109.
Conference
- Title
- International topical conference on probabilistic safety assessment and risk management (PSA '87).
- Dates
- 31 Aug - 4 Sep 1987.
- Place
- Zurich (Switzerland).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 20061160
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA; HUMAN FACTORS; LOVIISA-1 REACTOR; MAN-MACHINE SYSTEMS; PROBABILISTIC ESTIMATION; PROBABILITY; REACTOR OPERATORS; RELIABILITY; RISK ASSESSMENT; SYSTEMS ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; INFORMATION; PERSONNEL; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS