Published 2014 | Version v1
Miscellaneous Metadata-only

Experimental results of in-vessel melt pool behaviour with surface insulation and surface cooling condition from LIVE-3D and LIVE-2D facilities

Creators

  • 1. Karlsruhe Inst. of Tech. (KIT) (Germany)

Description

LIVE programme investigates late in-vessel debris and melt pool behavior during loss of coolant accidents in light water reactor lower head. Similar test series have been performed in a hemispheric LIVE-3D facility and in a semi-circular LIVE-2D facility. The simulant materials were water and non-eutectic nitrate salt. The heat flux distribution of an externally cooled melt pool either with top insulation or top cooling condition are characterized and compared with other studies. The upwards and downwards Nusselt number are determined. The test results indicates stronger upwards heat transfer in LIVE tests with top cooling condition than other well-known predictions. The upwards heat transfer in 2D geometry is even stronger than in 3D geometry. (author)

Part of:
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-16-2
Imprint Title
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Imprint Pagination
270 Megabytes
Journal Page Range
[19 p.]

Conference

Title
19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Dates
24-28 Aug 2014
Place
Vancouver, British Columbia (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49016274
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
HEAT FLUX; HEAT TRANSFER; LOSS OF COOLANT; MELTDOWN; REACTOR ACCIDENTS; TEST FACILITIES; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SEVERE ACCIDENTS

Optional Information

Notes
Paper PBNC2014-082. 20 refs., 5 tabs., 14 figs.