Published 2000
| Version v1
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New approaches for evaluation of brittle strength of reactor pressure vessels
- 1. TsNII KM Prometej, Sankt-Peterburg (Russian Federation)
- 2. NIKIEhT, Moscow (Russian Federation)
Description
no abstract available
Files
32018001.pdf
Files
(61.4 kB)
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Additional details
Additional titles
- Original title (English)
- Novye podkhody k raschetu khrupkoj prochnosti korpusov reactorov
Publishing Information
- Imprint Place
- St. Petersburg (Russian Federation)
- Imprint Title
- Sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Collection of abstracts
- Imprint Pagination
- 165 p.
- Journal Page Range
- p. 32-33
- Report number
- INIS-RU--445
Conference
- Title
- 6. international conference on material issues in design, manufacturing and operation of nuclear power plants equipment
- Dates
- 19-23 Jun 2000
- Place
- St. Petersburg (Russian Federation)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 32018001
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- No Abstract, Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; BRITTLENESS; CRACKS; FRACTURE PROPERTIES; PRESSURE VESSELS; TEMPERATURE DEPENDENCE; THICKNESS; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINERS; DIMENSIONS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS