Published 1985
| Version v1
Miscellaneous
Impact of the initial gas gap pressure level on the fuel rod temperature regime
Creators
- 1. Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Description
Thermomechanical analysis of the fuel rod behaviour with respect to initial pressure in the gas gap has been carried out taking into account the fuel burnup. The maximum fuel rod core temperature, gas gap thermal conductivity and stresses and strains in the fuel cladding have been considered as functions of the gas gap pressure. Increase of the initial pressure for WWER type reactor fuel rod from 0.1 to 1 MPa results in greater thermal conductivity, lower maximum fuel rod core temperature, decreased rate of gaseous fission products concentration in the gap and slower gap closing. With further pressure growth from 1 to 5 MPa the maximum fuel rod core temperature reduction is not so noticeable
Additional details
Additional titles
- Original title (Russian)
- Анализ влияния исходной величины давления газа в зазоре на температурный режим твел
Publishing Information
- Imprint Title
- Thermal physics 84. Thermal aspects of WWER nuclear reactor safety. V. 3
- Imprint Pagination
- 250 p.
- Journal Page Range
- p. 95-104.
- Report number
- INIS-mf--12602
Conference
- Title
- Thermal physics 84. Thermal aspects of WWER nuclear reactor safety.
- Original Conference Title
- Teplofizika 84. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov VVEhR
- Dates
- Oct 1984.
- Place
- Varna (Bulgaria).
INIS
- Country of Publication
- International Centre for Scientific and Technical Information (ICSTI)
- Country of Input or Organization
- International Centre for Scientific and Technical Information (ICSTI)
- INIS RN
- 21050126
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BULGARIA; BURNUP; FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; STRESS ANALYSIS; STRESSES; TEMPERATURE DISTRIBUTION; THEORETICAL DATA; THERMAL CONDUCTION; WWER TYPE REACTORS
- Descriptors DEC
- DATA; DEVELOPING COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.; 6 figs. Imprint:Teplofizika 84. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov VVEhR. Tom 3.;Sbornik dokladov seminara SEhV, Varna, NRB, oktyabr' 1984 g.