Published 2000
| Version v1
Book
Elongation of the RBMK type reactor fuel elements in the process of fuel-can thermomechanical interaction
- 1. GNTs RF FEhI, Obninsk (Russian Federation)
- 2. GUP NIKIEhT, Moscow (Russian Federation)
Description
no abstract available
Additional details
Additional titles
- Original title (Russian)
- Удлинение твэлов реактора РБМК в процессе термомеханического взаимодействия «топливо — оболочка»
Publishing Information
- Publisher
- GNTs RF NIIAR
- Imprint Place
- Dimitrovgrad (Russian Federation)
- ISBN
- 5-85165-648-4
- Imprint Title
- 6. Russian conference on reactor materials science. Abstracts
- Imprint Pagination
- 312 p.
- Journal Page Range
- p. 25
Conference
- Title
- 6. Russian conference on reactor materials science
- Original Conference Title
- 6. Rossijskaya konferentsiya po reaktornomu materialovedeniyu
- Dates
- 11-15 Sep 2000
- Place
- Dimitrovgrad (Russian Federation)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 32011460
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- No Abstract, Conference
- Descriptors DEI
- ELONGATION; FUEL CANS; FUEL ELEMENTS; FUEL-CLADDING INTERACTIONS; LWGR TYPE REACTORS; NUCLEAR FUELS; PHYSICAL RADIATION EFFECTS; THERMAL EXPANSION; URANIUM DIOXIDE; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; DEFORMATION; ENERGY SOURCES; EXPANSION; FUELS; GRAPHITE MODERATED REACTORS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- Imprint:6. Rossijskaya konferentsiya po reaktornomu materialovedeniyu. Tezisy dokladov