Published 1985 | Version v1
Miscellaneous

Heat transfer crisis investigation on 19-rod cluster with high peaking factor of power density

Creators

Description

Experimental data on the heat transfer crisis in a 19-tubes bundle with the radial power density nonuniformity coefficient of 1.828 are presented. The tubes with 9 mm outer diameter were arranged in staggered order with 12.2 mm pitch. The bundle heated length was 2.5 m. The averaged values of the calculated/experimental critical heat flux density ratio for unidimensional approximation were found to be 1.545, 1.067 and 0.87 in case of the optimistic estimate, the mean estimate for an imaginary 'hot' bundle and the mean estimate for a 'hot' subchannel respectively. These results have been obtained when calculating the critical thermal loads with the use of the steam consent in the critical cross-section. When calculating was based on the experimental values of the coolant inlet subcooling those ratios were 1.340, 1.035 and 0.94 respectively. The obtained calculation data has shown both unidimensional mean estimates to provide satisfactory results. The critical heat flux density calculations were performed on VEVERKA code. The average calculated/experimental critical heat flux density ratio was found to be 0.9

Additional details

Additional titles

Original title (Russian)
Исследование кризиса теплоотдачи в 19-трубном пучке с большой радиальной неравномерностью тепловыделения

Publishing Information

Imprint Title
Thermal physics 84. Thermal aspects of WWER nuclear reactor safety. V. 2
Journal Page Range
p. 158-165.
Report number
INIS-mf--11564

Conference

Title
Thermal physics 84. Thermal aspects of WWER nuclear reactor safety.
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
20085823
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENCH-SCALE EXPERIMENTS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; HOT CHANNEL FACTOR; NUMERICAL DATA; WWER TYPE REACTORS
Descriptors DEC
DATA; ENRICHED URANIUM REACTORS; EVALUATION; FUEL ASSEMBLIES; HEAT FLUX; INFORMATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs.; 1 tab.; 2 figs. Imprint:Teplofizika 84. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov VVEhR. Tom 2.;Sbornik dokladov seminara SEhV, Varna, NRB, Oktyabr' 1984 g.