Published 1975
| Version v1
Report
Availability analysis of a heat transport pump configuration using Markov models
Creators
- 1. Saskatchewan Univ., Group Power System Research, Saskatoon, SK (Canada). Dept. of Electrical Engineering
Description
This paper illustrates a systematic approach of reliability modelling and calculation using the Markov approach, with respect to a practical subsystem application, a heat transport pump configuration in the Bruce Generating Station of Ontario Hydro. This paper considers two possible classifications of pump failures: pump failures grouped into a single permanent failure mode; pump failures grouped into permanent and temporary failure mode. The basic Markov technique has been applied in each case. The reliability indices as computed in this paper are long term, steady state values; they can be determined from the set of linear simultaneous equations derived form the state space model
Additional details
Publishing Information
- Imprint Title
- Proceedings of the specialist meeting on the development and application of reliability techniques to nuclear plant
- Imprint Pagination
- 795 p.
- Journal Page Range
- p. 137-159
- Report number
- NEA-CSNI-R--1975-3
Conference
- Title
- Specialist meeting on the development and application of reliability techniques to nuclear plant
- Dates
- 8-10 Apr 1974
- Place
- Liverpool (United Kingdom)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 41041043
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRUCE SITE; CALCULATION METHODS; FAILURE MODE ANALYSIS; MARKOV PROCESS; NEA; PHWR TYPE REACTORS; PROBABILISTIC ESTIMATION; PUMPS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; EQUIPMENT; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTERNATIONAL ORGANIZATIONS; OECD; REACTOR COMPONENTS; REACTOR SITES; REACTORS; SAFETY; STOCHASTIC PROCESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Notes
- 8 refs.