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

doi:https://doi.org/10.2172/5701417

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

Full Record
Other Related Research

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

Publication Date:: 1983-01-01

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.

Copy to clipboard


                    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

Copy to clipboard


                    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.

Copy to clipboard


                    
@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}

}

Copy to clipboard

Technical Report:

View Technical Report (0.10 MB)

https://doi.org/10.2172/5701417

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions

Conference Bauer, T H ; Tylka, J P ; Fink, C L ; ...

Test L06, closely following L04 in the PFR/TREAT series, was a multi-pin simulation of a LMFBR transient under cooling/overpower (TUCOP) accident using full-length prototypic UK fast reactor fuel. In L04 the test fuel had been pre-irradiated to effect some fuel restructuring and fission gas retention. By contrast, in L06 the test fuel ws fresh. The pre-failure test fuel power and coolant flow histories in L04 were duplicated as closely as possible in L06 to make the L04/L06 pair a direct comparison of the performance of fresh versus irradiated fuel under TUCOP conditions. Identical 7-pin gridded test bundles in identically outfittedmore »« less
Full Text Available
Comparison of L04, L05, and L07: three irradiated 7-pin bundle TUCOP tests. [LMFBR]

Conference Wright, A E ; Robinson, W R ; Bauer, T H ; ...

Four transient-undercooling-driven overpower (TUCOP) tests on seven-pin bundles have been performed in the PFR/TREAT program. All were on full-length, bottom-plenum UK-design fuel. Three of them (tests L04, L05, and L07) tested sibling fuel elements having had the same preirradiation in PFR; one (L06) tested fresh fuel. The three tests on preirradiated fuel were designed to determine the differences in the motions of reactor-core materials that would result from the variation in power-to-flow mismatch conditions across the core of a commercial-size reactor during a hypothetical TUCOP accident. By initiating the overpower bursts at different fuel-coolant thermal-hydraulic states, the three tests yieldedmore »« less
Full Text Available
In-pile loss-of-flow TREAT test L05 with prototype fast reactor fuel

Technical Report Robinson, W R ; Bauer, T H ; Stanford, G S ; ...

In assessing the safety of liquid metal fast breeder reactors, various extremely-low-probability hypothetical core-disruptive accidents, with postulated events that might challenge containment and lead to release of radioactive material, are considered. Test L05, conducted in Argonne National Laboratory's Transient Reactor Test Facility (TREAT) with UK Prototype Fast Reactor (PFR) fuel, simulated one such accident. L05 was an in-pile, transient-undercooling-driven overpower (TUCOP) test within the PFR/TREAT collaborative program between the USDOE and the UKAEA. Seven grid-spaced full length, bottom-plenum fuel pins containing annular pellets of mixed oxide were tested to destruction in a Mark-IIIC integral loop with a flowing sodium environment.more »« less
https://doi.org/10.2172/7143046

Full Text Available
TUCOP failure threshold test CO6R

Conference Culley, G.E., Ferrell, P.C. ; Herbert, R ; Woods, W J

The C06R test was the sixth single-pin test in the collaborative US/UK PFR/TREAT transient testing program. It was designed to study the mechanism, time and location of cladding failure and first fuel escape in an intermediate channel transient undercooling - overpower accident (TUCOP). It complements the LO5/sup 2/ and LO7/sup 3/ tests which studied post failure fuel dispersal in a similar hypothetical accident. The test fuel was a single irradiated driver fuel pin taken from the UK's Prototype Fast Reactor (PFR) after approx.4% peak burnup. The C06R test has produced evidence that both pre and post failure internal fuel motionsmore »« less
Full Text Available
Fuel motion induced by a sharp burst TUCOP: PFR/TREAT test L07

Conference Robinson, W R ; Doerner, R C ; Morman, J A ; ...

In the transient-undercooling-driven overpower (TUCOP) accident scenario for moderate-to-high-sodium-void-worth-LMFBR cores, some computer codes predict large reactivity increases caused by compactive in-pin fuel motion in low power subassemblies during a power burst resulting from sodium voiding in the lead fuel subassemblies. In this hypothetical scenario, the low power subassemblies are predicted to experience midplane failure with relatively cold cladding, which inhibits radial dispersal and results in a momentary accumulation of fuel around the midplane failure site. A major objective of PFR/TREAT Test L07 was to simulate such low-power-subassembly TUCOP conditions, measure the associated fuel motion and evaluate the fuel-motion predictions.
Full Text Available

Similar Records