Published 1979 | Version v1
Report Open

Fuel rod response during LOFT Test L2-2

Description

The Loss-of-Fluid Test (LOFT) Facility is providing unique data on the response of a nuclear reactor to a loss-of-coolant accident (LOCA). The data are being used to assess the accuracy of the computer codes used in reactor safety analysis. The first LOFT nuclear test, Test L2-2, was a cold leg break LOCA at a peak linear power of 26.25 kW/m. The paper briefly describes the LOFT core, discusses fuel rod response during Test L2-2, and compares the data with the test prediction

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Publishing Information

Imprint Pagination
4 p.
Report number
CONF-790602--22

Conference

Title
ANS annual meeting.
Dates
3 - 8 Jun 1979.
Place
Atlanta, GA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10488195
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LOFT REACTOR; LOSS OF COOLANT; REACTOR EXPERIMENTAL FACILITIE; REACTOR OPERATION; SIMULATION
Descriptors DEC
ACCIDENTS; OPERATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS