Published 1982 | Version v1
Miscellaneous

Experimental data processing technique for nonstationary heat transfer on fuel rod simulators

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.