U.S. Department of EnergyOffice of Scientific and Technical Information
Results from the PFR/TREAT Test LO3. [LMFBR]
Abstract
TREAT experiment LO3 is a multi-pin transient over-power test in the current PFR/TREAT program. The objectives of the test were to simulate reactor conditions expected in a slow transient overpower accident in an LMFBR, and to study the resulting post-failure fuel motion. In this accident, clad failure was expected to be through internal pressurization of the fuel pin before coolant boiling had been initiated. The fuel sample consisted of seven pins, with an active fuel column 91 cm long, pre-irradiated in PFR to about 4 a/o burn-up. The test was conducted in a Mk-III integral loop with flowing sodium as the coolant. The coolant flowrate of 5.4 m/s was chosen to give a prototypical coolant temperature increase across the fuel bundle. The TREAT power transient was designed to be as slow as possible within the constraint of failing the fuel cladding at or before peak power, and within the reactivity limits of TREAT.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (USA)
- OSTI Identifier:
- 5866962
- Report Number(s):
- CONF-831047-32
ON: DE83014576
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Conference
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ELEMENT FAILURE; LMFBR TYPE REACTORS; TRANSIENT OVERPOWER ACCIDENTS; FLOW RATE; FUEL CANS; FUEL PINS; IN PILE LOOPS; REACTOR SAFETY; TREAT REACTOR; ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors
Citation Formats
Page, R J, Stanford, G S, Bauer, T H, Froehle, P H, Bowen, G R, Davies, A L, Herbert, R, and Woods, W J. Results from the PFR/TREAT Test LO3. [LMFBR]. United States: N. p., 1983.
Web.
Page, R J, Stanford, G S, Bauer, T H, Froehle, P H, Bowen, G R, Davies, A L, Herbert, R, & Woods, W J. Results from the PFR/TREAT Test LO3. [LMFBR]. United States.
Page, R J, Stanford, G S, Bauer, T H, Froehle, P H, Bowen, G R, Davies, A L, Herbert, R, and Woods, W J. 1983.
"Results from the PFR/TREAT Test LO3. [LMFBR]". United States. https://www.osti.gov/servlets/purl/5866962.
@article{osti_5866962,
title = {Results from the PFR/TREAT Test LO3. [LMFBR]},
author = {Page, R J and Stanford, G S and Bauer, T H and Froehle, P H and Bowen, G R and Davies, A L and Herbert, R and Woods, W J},
abstractNote = {TREAT experiment LO3 is a multi-pin transient over-power test in the current PFR/TREAT program. The objectives of the test were to simulate reactor conditions expected in a slow transient overpower accident in an LMFBR, and to study the resulting post-failure fuel motion. In this accident, clad failure was expected to be through internal pressurization of the fuel pin before coolant boiling had been initiated. The fuel sample consisted of seven pins, with an active fuel column 91 cm long, pre-irradiated in PFR to about 4 a/o burn-up. The test was conducted in a Mk-III integral loop with flowing sodium as the coolant. The coolant flowrate of 5.4 m/s was chosen to give a prototypical coolant temperature increase across the fuel bundle. The TREAT power transient was designed to be as slow as possible within the constraint of failing the fuel cladding at or before peak power, and within the reactivity limits of TREAT.},
doi = {},
url = {https://www.osti.gov/biblio/5866962},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 1983},
month = {Sat Jan 01 00:00:00 EST 1983}
}