Lifetime assessment of selected components of WWER-440 units
Description
A detailed analysis is made of factors which affect the life of the main components of nuclear power plants with WWER-440 reactors: of the pressure vessel, primary circuit pipes, steam generator and pressurizer. As such factors which are given by the choice of construction materials, dimensions of assemblies, etc., cannot be influenced for existing equipment, attention is centred on operating factors which are given by the loading method, impact of radiation embrittlement, corrosion, aging, fatigue processes, etc., and factors which are given by the possibilities and abilities to return the installation its ability to perform its function. It is stated that so far there is not enough experience and knowledge to be able to assess the possibilities and conditions which will be decisive for extending the life of the main components of nuclear power plants. Information should therefore be consistently collected on the state of the major nuclear power plant assemblies; it will also be necessary to optimally control non-steady state operating processes and to cope with maintenance and repair requirements. (Z.M.). 4 refs
Additional details
Additional titles
- Original title (Slovak)
- Posudenie zivotnosti vybranych komponentov blokov VVER 440
Publishing Information
- Journal Title
- Jaderna Energie
- Journal Volume
- 34
- Journal Issue
- 11
- Series
- Jad. Energ.
- Journal Page Range
- 439-442
- ISSN
- 0448-116X
- CODEN
- JADEA
Conference
- Title
- 2. national conference on cooperation of sources in electric power system.
- Original Conference Title
- II. celostatna konferencia o spolupraci zdrojov v elektrizacnej sustave
- Dates
- 26-30 Sep 1988.
- Place
- Tatranska Lomnica (Czechoslovakia).
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Serbia and Montenegro
- INIS RN
- 20027042
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; EMBRITTLEMENT; FATIGUE; LIFETIME; PHYSICAL RADIATION EFFECTS; PIPES; PRESSURE VESSELS; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; REPAIR; RETROFITTING; STEAM GENERATORS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CONTAINERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia at US$ 10 per page.