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Title: In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident

Abstract

Test L04 in the PFR/TREAT series is the first multi-pin, in-pile simulation of a LMFBR transient undercooling/overpower (TUCOP) accident using full length prototypic fuel irradiated in a fast reactor. L04 is a gridded 7-pin bundle test performed in the ANL Mk-III integral loop in a flowing sodium environment and uses prototypic, bottom plenum, UK reactor fuel, preirradiated in the PFR to an axial peak burn-up of 4.2 a/o. The objective of L04 was the study, by simulation, of coolant voiding and fuel motion during the initiating phase of a hypothetical TUCOP accident in a large LMFBR. Test L04 is intended to study the behavior of a centrally located, lead subassembly with the highest power-to-flow ratio.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
OSTI Identifier:
5701417
Report Number(s):
CONF-831047-30
ON: DE83014678
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
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; LMFBR TYPE REACTORS; LOSS OF COOLANT; HEAT TRANSFER; HYDRAULICS; TREAT REACTOR; IN PILE LOOPS; EXPERIMENTAL DATA; FLOW RATE; PRESSURE GRADIENTS; REACTOR SAFETY; TEMPERATURE GRADIENTS; ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; MECHANICS; NUMERICAL DATA; 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

Citation Formats

Tylka, J P, Bauer, T H, Wright, A E, Davies, A L, Herbert, R, and Woods, W J. In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident. United States: N. p., 1983. Web. doi:10.2172/5701417.
Tylka, J P, Bauer, T H, Wright, A E, Davies, A L, Herbert, R, & Woods, W J. In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident. United States. https://doi.org/10.2172/5701417
Tylka, J P, Bauer, T H, Wright, A E, Davies, A L, Herbert, R, and Woods, W J. Sat . "In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident". United States. https://doi.org/10.2172/5701417. https://www.osti.gov/servlets/purl/5701417.
@article{osti_5701417,
title = {In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident},
author = {Tylka, J P and Bauer, T H and Wright, A E and Davies, A L and Herbert, R and Woods, W J},
abstractNote = {Test L04 in the PFR/TREAT series is the first multi-pin, in-pile simulation of a LMFBR transient undercooling/overpower (TUCOP) accident using full length prototypic fuel irradiated in a fast reactor. L04 is a gridded 7-pin bundle test performed in the ANL Mk-III integral loop in a flowing sodium environment and uses prototypic, bottom plenum, UK reactor fuel, preirradiated in the PFR to an axial peak burn-up of 4.2 a/o. The objective of L04 was the study, by simulation, of coolant voiding and fuel motion during the initiating phase of a hypothetical TUCOP accident in a large LMFBR. Test L04 is intended to study the behavior of a centrally located, lead subassembly with the highest power-to-flow ratio.},
doi = {10.2172/5701417},
url = {https://www.osti.gov/biblio/5701417}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {1}
}