Published 1984 | Version v1
Book Metadata-only

Problems of two-phase flows in water cooled and moderated reactors

Creators

Description

Heat exchange in two-phase flows of coolant in loss of coolant accidents in PWR and BWR reactors has been investigated. Three main stages of accident history are considered: blowdown, reflooding using emergency core cooling system and rewetting. Factors, determining the rate of coolant leakage and the rate of temperature increase in fuel cladding during blowdown, processes of vapour during reflooding and liquid priming by vapour during rewetting, are discussed

Additional details

Additional titles

Subtitle (English)
Chapter 1
Original title (Russian)
Проблемы двухфазных потоков применительно к водо-водяным реакторам
Original subtitle (Russian)
Glava 1.

Publishing Information

Publisher
Ehnergoatomizdat.
Imprint Place
Moskva (USSR)
Imprint Title
Thermohydraulics of two-phase systems for industrial desion and nuclear engineering
Journal Page Range
p. 10-16.

INIS

Country of Publication
USSR
Country of Input or Organization
USSR
INIS RN
16086047
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; COOLANTS; DEPRESSURIZATION; FUEL CANS; HEAT TRANSFER; LOSS OF COOLANT; MAXIMUM CREDIBLE ACCIDENT; PWR TYPE REACTORS; REWETTING; STEAM; TIME DEPENDENCE; TWO-PHASE FLOW; VERY HIGH TEMPERATURE; WATER
Descriptors DEC
ACCIDENTS; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Translation from English. Imprint:Teploobmen i gidrodinamika dvukhfaznykh potokov v atomnoj i teolovoj ehnergetike.