Published June 1989 | Version v1
Miscellaneous

Study into heat transfer in modeling the emergency cooling of a reactor core

  • 1. Skoda, Plzen (Czechoslovakia). Zavod Energeticke Strojirenstvi

Description

Some results are given of experimental work in the field of heat transfer, obtained by processing data measured during the modeling of emergency cooling of WWER reactor cores. The experiments were made on the circular and semicircular channels of an equipment simulating core re-flooding after an accident associated with major loss of coolant. The heated lengths of the measurement segments were 2500 and 3500 mm. A small number of parameters were examined, viz. pressure, mass flow rate, steam content and wall temperature, whereas the effect of time-independent variables was not studied. Nevertheless, the results enable not only a qualitative but also a quantitative description of the process. (Z.M.)

Part of:
Results of R+D of nuclear power plants with WWER-1000 type light-water reactors. Part 1

Additional details

Additional titles

Original title (Czech)
Vyzkum prestupu tepla pri modelovani havarijniho chlazeni aktivni zony

Publishing Information

ISBN
80-02-99342-X
Imprint Title
Results of R+D of nuclear power plants with WWER-1000 type light-water reactors. Part 1
Imprint Pagination
274 p.
Journal Page Range
p. 103-107.
Report number
INIS-mf--12780

Conference

Title
Seminar on the results of R+D of nuclear power plants with WWER-1000 type light-water reactors.
Original Conference Title
Celostatni konference ''Vysledky vyzkumnych a vyvojovych praci pro jaderne elektrarny s lehkovodnimi reaktory typu VVER 1000''
Dates
6-9 Jun 1989.
Place
Karlovy Vary (Czechoslovakia).

INIS

Optional Information

Notes
Imprint:Vysledky vyzkumnych a vyvojovych praci pro jaderne elektrarny s lehkovodnimi reaktory typu VVER 1000. I. dil.