Published 2015
| Version v1
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Additional research results of radiation creep of WWER fuel pellets with grain size more than 25 μm in temperature range of 650–1050 °C
Creators
- 1. JSC "VNIINM", Moscow (Russian Federation)
- 2. MEPhI, Moscow (Russian Federation)
- 3. JSC "SSC RIAR", Dimitrovgrad (Russian Federation)
Description
The objective of present work was an additional experimentation according to earlier developed methods and experimental devices in reactor irradiation conditions.With these experiments at four different temperatures, we have managed to plot appropriate diagrams and determine rates of the steady-state radiation creep of the modified uranium dioxide with a grain size not less than 25 μm in the stress range of 10–40 MPa. Creep rate of the modified uranium dioxide with a grain size of 25 μm turned out higher than for the standard fuel at temperature above 850 °C, while at temperature below 850 °C comply with it. (author)
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47082473.pdf
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Additional details
Publishing Information
- Publisher
- Institute for Nuclear Research and Nuclear Energy
- Imprint Place
- Sofia (Bulgaria)
- Imprint Title
- 11. International conference on WWER fuel performance, modelling and experimental support. Proceedings
- Imprint Pagination
- 712 p.
- Journal Page Range
- p. 366-369
- ISSN
- 1313-4531
- Report number
- INIS-BG--2493
Conference
- Title
- 11. International conference on WWER fuel performance, modelling and experimental support
- Dates
- 26 Sep - 3 Oct 2015
- Place
- Varna (Bulgaria)
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 47082473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; FUEL PELLETS; GRAIN SIZE; IRRADIATION; NUCLEAR FUELS; STEADY-STATE CONDITIONS; TEMPERATURE RANGE; URANIUM DIOXIDE; WWER TYPE REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; MECHANICAL PROPERTIES; MICROSTRUCTURE; OXIDES; OXYGEN COMPOUNDS; PELLETS; POWER REACTORS; PWR TYPE REACTORS; REACTOR MATERIALS; REACTORS; SIZE; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 8 refs.
- Secondary number(s)
- INIS-BG--2402