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

Technical Report · Sat Jan 01 00:00:00 EST 1983

DOI:https://doi.org/10.2172/5701417· OSTI ID:5701417

Tylka, J P; Bauer, T H; Wright, A E; Davies, A L; Herbert, R; Woods, W J

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.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5701417
• Report Number(s): CONF-831047-30; ON: DE83014678
• Resource Relation: Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

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
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