Published 1991
| Version v1
Miscellaneous
LBB technology application on the primary piping system of the NPP V1 Jaslovske Bohunice
Description
An upgrading programme is well underway for the NPP Jaslovske Bohunice and will be completed in 1992. The leak before break technology (LBB) plays an important part and a detailed project was set up for application to all the safety related piping. The first results are presented included a seismic margin assessment, detailed evaluation of stress state in critical sections, fracture and corrosion database. Full scale experiments with through-wall cracks in critical heterogeneous welds and T-type welds in elbow are well underway. The scope and initial results of these experiments are presented. (orig.)
Additional details
Additional titles
- Original title (English)
- Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik. Vortraege. Bd. 1.
Publishing Information
- Imprint Title
- Safety and reliability of plant technology with special emphasis on nuclear technology. Papers. Vol. 1
- Imprint Pagination
- 600 p.
- Journal Page Range
- p. 29.1-29.16.
Conference
- Title
- Safety and reliability of plant technology with special emphasis on nuclear technology - ageing mechanisms and potential for energy absorption in piping systems.
- Original Conference Title
- 17. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik - Rissausloesende Faktoren und Potential fuer Energieaufnahme in Rohrleitungssystemen
- Acronym
- 17. MPA-seminar
- Dates
- 10-11 Oct 1991.
- Place
- Stuttgart (Germany).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 26011316
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOHUNICE V-1 REACTOR; CRACK PROPAGATION; LEAKS; LOSS OF COOLANT; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY EXPERIMENTS; SAFETY STANDARDS; STRESSES; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STANDARDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik. Vortraege. Bd. 1.