Published 1982 | Version v1
Journal article Metadata-only

Research and development of sodium-cooled fast power reactors

Creators

Description

The principal trends are given of research and development of the sodium cooled fast reactor in the USSR and experience is presented gained with the operation of Soviet experimental fast reactors. The principal current problem is the development of fuel elements and steam generators, and reactor safety. The tasks are listed in whose solution Czechoslovakia is involved in the research of fast reactors within the programme of the Council of Mutual Economic Assistance. (M.D.)

Additional details

Publishing Information

Journal Title
Skoda Rev.
Journal Issue
no.1
Series
Skoda Rev.
ISSN
0374-4523

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Serbia and Montenegro
INIS RN
14764852
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMECON; COORDINATED RESEARCH PROGRAMS; CZECHOSLOVAKIA; FUEL ELEMENTS; LMFBR TYPE REACTORS; PLANNING; REACTOR SAFETY; REVIEWS; SODIUM COOLED REACTORS; STEAM GENERATORS
Descriptors DEC
BOILERS; BREEDER REACTORS; DEVELOPING COUNTRIES; DOCUMENT TYPES; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; INTERNATIONAL ORGANIZATIONS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH PROGRAMS; SAFETY; VAPOR GENERATORS