Published February 1986 | Version v1
Report Metadata-only

Technical research centre of Finland use of RELAP5/MOD2

Creators

  • 1. Technical Research Centre of Finland

Description

Reactor safety research in Finland is first described in a general way. Then VTT's computer code system for thermal hydraulic accident analysis is introduced. Finally the role of RELAP5/MOD2 together with the current experiences and plans for future use is being discussed. According to the plans RELAP5/MOD2 will be the main tool in the analyses of LBLOCA-, SBLOCA- and some other transients together with self-developed faster computer codes. So far the limited experiences with RELAP5/MOD2 have been promising, although not completely without problems

Additional details

Publishing Information

Imprint Title
Thirteenth water reactor safety research information meeting: proceedings. Volume 5
Journal Page Range
p. 191-200.
Report number
NUREG/CP--0072-Vol.5

Conference

Title
13. water reactor safety research information meeting.
Dates
22-25 Oct 1985.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18002559
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; FINLAND; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; RESEARCH PROGRAMS; TRANSIENTS
Descriptors DEC
ACCIDENTS; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; POWER REACTORS; REACTORS; SAFETY; SCANDINAVIA; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS