Published 1980
| Version v1
Book
Life prediction of pipe components
Creators
- 1. Sigma, Prague (Czechoslovakia). Vyzkumny Ustav Cerpacich Zarizeni, Potrubi a Armatur
Description
Results presented in this work deal with primary circuit piping components of the V 1 nuclear power station in Jaslovske Bohunice, as well as other primary piping components for type VVER 440 MW (PWR) nuclear power stations. The work covers the assessment of pipe components during the fatigue damage initiation stage, and evaluation in the stage of fatigue crack propagation. (author)
Additional details
Publishing Information
- Publisher
- Pergamon.
- Imprint Place
- Oxford
- ISBN
- 0 08 024739 3
- Imprint Title
- Mechanical behaviour of materials
- Imprint Pagination
- 1774 p.
- Journal Page Range
- v. 2 p. 91-100.
Conference
- Title
- 3. international conference on mechanical behaviour of materials (ICM3).
- Dates
- 20 - 24 Aug 1979.
- Place
- Cambridge, UK.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 11571402
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOHUNICE V-1 REACTOR; CRACKS; FATIGUE; PIPE JOINTS; PIPELINES; PIPES; PRIMARY COOLANT CIRCUITS; STRESS ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; JOINTS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:In 3 volumes.