Published 2000
| Version v1
Miscellaneous
Methodological efficiency of reactor pressure vessel control samples programs and reliability of WWER vessels at the Ukraine NPP
Description
An analysis is made for the programs with the use of check specimens (CS) for reactor vessel (RV) control which is considered as the only method for estimating embrittlement in RV material and its operational capability. Advantages and disadvantages of the programs are noted. Other methods are developed and improved to estimate properties of RV metal and welded joints. It is shown that the most valid information about RV metal state can be obtained only by testing specimens prepared from templets cut directly from a RV wall in the region of reactor core. Ukrainian researchers designed the equipment and performed successful tests on templet cutting from the surface of the metal to study mechanical properties of critical pipelines
Abstract (Russian)
Проанализированы программы образцов-свидетелей (ОС) корпуса реактора (КР), считающихся единственным способом оценки степени охрупчивания материала КР и определения его работоспособности. Отмечены их преимущества и недостатки. Разрабатываются и совершенствуются альтернативные методики оценки свойств металла КР и сварных соединений. Показано, что наиболее достоверную информацию о состоянии металла КР могут дать только испытания образцов, изготовленных из темплетов, взятых непосредственно из стенки КР в районе активной зоны. Исследовательскими коллективами Украины разработано оборудование и проведены успешные испытания по отработке методики вырезки темплетов с поверхности металла для исследований механических свойств ответственных трубопроводовAdditional details
Additional titles
- Original title (Russian)
- Metodologicheskaya ratsional'nost' programm OS KR i nadezhnost' korpusov VVEhR na AEhS Ukrainy
Publishing Information
- Imprint Place
- St. Petersburg (Russian Federation)
- Imprint Title
- Proceedings of the sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Volume 2
- Imprint Pagination
- 402 p.
- Journal Page Range
- p. 355-360
- Report number
- INIS-RU--453
Conference
- Title
- 6. international conference on material issues in design, manufacturing and operation of nuclear power plants equipment
- Original Conference Title
- Shestaya mezhdunarodnaya konferentsiya: Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS
- 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
- 33004646
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- EMBRITTLEMENT; MATERIALS TESTING; MECHANICAL PROPERTIES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; REACTOR CORES; RELIABILITY; STEELS; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 2 tabs. Imprint:Trudy shestoj mezhdunarodnoj konferentsii. Problemy materialovedeniya pri proektirovanii, izgotovlenii i ehkspluatatsii oborudovaniya AEhS. Tom 2