Published 2002
| Version v1
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Methodological approaches to assessment of reactor pressure vessel integrity of Kozloduy NPP units 5 and 6
Description
The Russian legislative framework for evaluation of the reactor vessel service life includes documents on the design stages and operational stages. The methodology MRK-SKhR-2000 for calculation of breaking embrittlement strength - postulated defects, toughness breaking strength curve and strength criteria - is presented in the paper
Availability note (English)
Available from INIS in electronic formFiles
33070690.pdf
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Additional details
Additional titles
- Original title (Russian)
- Методические подходы к оценке целостности корпусов реакторов блоков 5 и 6 АЭС «Козлодуй»
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-BG--0440
Conference
- Title
- Options, Challenges and Future'
- Acronym
- International Nuclear Forum 'Nuclear Power in Eastern Europe
- Dates
- 28-30 Jun 2002
- Place
- Varna (Bulgaria)
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 33070690
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EMBRITTLEMENT; FRACTURE PROPERTIES; MATHEMATICAL MODELS; REACTOR VESSELS; SERVICE LIFE; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; LIFETIME; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs.