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Title: Loss-of-coolant accident test series test LOC 5 experiment operating specification. [PWR]

Abstract

The Loss of Coolant Accident (LOCA) Program is part of the Department of Energy Fuel Behavior Program sponsored by the Nuclear Regulatory Commission, and is directed towards providing a detailed understanding of the response of nuclear fuel rods to off-normal accident conditions. This is one of several programs being conducted in the Power Burst Facility (PBF) that will provide data for development and assessment of fuel behavior computer models used to predict the response of light water reactor (LWR) fuel under hypothesized accident conditions. The LOCA tests simulate accidents resulting from a break in the cold-leg inlet or hot-leg outlet of a pressurized water reactor (PWR) core. During a LOCA the coolant conditions are characterized by a rapid core depressurization and drastic changes in both coolant mass flow and quality. Depending on the size and location of the break in the cold- or hot-leg, system depressurizaion will be completed within approximately 30 seconds. Cooling of the fuel rods will degrade during the accident. The fuel rod cladding will heat up and may balloon and rupture. The purpose of the document is to specify the experiment operating procedure for Test LOC-5. The test will be performed using four, separately shrouded fuelmore » rods of PWR 15 x 15 design. Two rods have been previously irradiated and two rods will be unirradiated. One unirradiated and one irradiated rod will be backfilled with helium to a pressure typical of beginning-of-life PWR fuel rods, and the other rods will be backfilled to a pressure typical of fuel rods at the end-of-operational life.« less

Authors:
Publication Date:
Research Org.:
Idaho National Engineering Lab., Idaho Falls (USA)
OSTI Identifier:
6179149
Report Number(s):
TFBP-TR-309
TRN: 79-009068
DOE Contract Number:  
EY-76-C-07-1570
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; SIMULATION; PWR TYPE REACTORS; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENT FAILURE; PBF REACTOR; ACCIDENTS; PULSED REACTORS; REACTOR ACCIDENTS; REACTORS; TANK TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Yackle, T.R. Loss-of-coolant accident test series test LOC 5 experiment operating specification. [PWR]. United States: N. p., 1979. Web.
Yackle, T.R. Loss-of-coolant accident test series test LOC 5 experiment operating specification. [PWR]. United States.
Yackle, T.R. Thu . "Loss-of-coolant accident test series test LOC 5 experiment operating specification. [PWR]". United States.
@article{osti_6179149,
title = {Loss-of-coolant accident test series test LOC 5 experiment operating specification. [PWR]},
author = {Yackle, T.R.},
abstractNote = {The Loss of Coolant Accident (LOCA) Program is part of the Department of Energy Fuel Behavior Program sponsored by the Nuclear Regulatory Commission, and is directed towards providing a detailed understanding of the response of nuclear fuel rods to off-normal accident conditions. This is one of several programs being conducted in the Power Burst Facility (PBF) that will provide data for development and assessment of fuel behavior computer models used to predict the response of light water reactor (LWR) fuel under hypothesized accident conditions. The LOCA tests simulate accidents resulting from a break in the cold-leg inlet or hot-leg outlet of a pressurized water reactor (PWR) core. During a LOCA the coolant conditions are characterized by a rapid core depressurization and drastic changes in both coolant mass flow and quality. Depending on the size and location of the break in the cold- or hot-leg, system depressurizaion will be completed within approximately 30 seconds. Cooling of the fuel rods will degrade during the accident. The fuel rod cladding will heat up and may balloon and rupture. The purpose of the document is to specify the experiment operating procedure for Test LOC-5. The test will be performed using four, separately shrouded fuel rods of PWR 15 x 15 design. Two rods have been previously irradiated and two rods will be unirradiated. One unirradiated and one irradiated rod will be backfilled with helium to a pressure typical of beginning-of-life PWR fuel rods, and the other rods will be backfilled to a pressure typical of fuel rods at the end-of-operational life.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {2}
}

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