Experimental data processing technique for nonstationary heat transfer on fuel rod simulators
Creators
Description
Non-stationary heat-transfer data processing is considered in connection with experimental studies of the emergency cooling whereat fuel rod imitators both with direct and indirect shell heating were used. The objective of data processing was obtaining the temperature distribution within the imitator, the heat flux removed by the coolant and the shell-coolant heat-transfer coefficient. The special attention was paid to the temperature distribution calculation at the data processing during the reflooding experiments. In this case two factors are assumed to be known: the time dependency of temperature variation at a certain point within the imitator cross-section and the heat flux at some point of the same cross-section. The initial data preparation for calculations, employing the procedure of smoothing by cubic spline functions, is considered as well, with application of an algorithm reported in the literature, which is efficient for the given functional dependency wherein the deviation in each point is known
Additional details
Additional titles
- Original title (Russian)
- Методика обработки опытных данных по нестационарному теплообмену на имитаторах твэлов
Publishing Information
- Imprint Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety. V.1
- Journal Page Range
- p. 233-240.
- Report number
- INIS-mf--9439
Conference
- Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety.
- Dates
- 4-6 May 1982.
- Place
- Karlovy Vary (Czechoslovakia).
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
- 15070293
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA PROCESSING; ECCS; FUEL ELEMENTS; HEAT TRANSFER; LOSS OF COOLANT; REACTOR SAFETY; REWETTING; SIMULATION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs. Imprint:Teplofizika 82. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov WWER. Tom 1.;Sbornik dokladov iz seminara SEhV g. Karlovy Vary, ChSSR, Maj 1982 g.