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AbstractAbstract
[en] The Loss-of-Fluid Test (LOFT) facility, operated by EG and G Idaho, Inc., for the US Nuclear Regulatory Commission, is designed as an integral test facility to study the behavior of commercial pressurized water reactors (PWRs) during a loss-of-coolant accident (LOCA). For this mission, six nuclear and one nonnuclear test series have been proposed to provide data on PWR transient behavior, but plans must be recognized as tentative and subject to change for a number of reasons. The Nonnuclear Test Series, completed in April 1978, consisted of six loss-of-coolant experiments (LOCEs) performed with isothermal primary coolant temperatures. The Power Ascension Test Series, Series L2, proposes five LOCEs, simulating double-ended cold leg breaks (DECLB), to provide a controlled power escalation to a peak power of 52.49 kW/m. The Small and Intermediate Breaks Test Series, Series L3, will consist of three LOCEs designed to study the effects of smaller primary coolant system ruptures. These tests will be initiated by cold leg ruptures ranging from scaled 6.4-cm pipe ruptures to scaled 0.05-m2 pipe cracks. Five LOCEs are proposed for the Alternate Emergency Core Cooling Systems (ECCS) Test Series, designated Series L4. These DECLBs will be used to study systems such as lower plenum emergency core coolant injection, hot leg injection, and combined hot and cold leg injection. Also included in the L4 series is a test involving upper plenum-downcomer pressure equalization valves. The Hot Leg Rupture Test Series, Series L5, will study PWR behavior during a double-ended hot leg rupture
Primary Subject
Source
1979; 13 p; International colloquium on irradiation for reactor safety programmes; Petten, Netherlands; 25 - 28 Jun 1979; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference
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