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Title: In-pile loss-of-flow TREAT test L05 with prototype fast reactor fuel

Technical Report ·
DOI:https://doi.org/10.2172/7143046· OSTI ID:7143046

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. The UK manufactured fuel was preirradiated in the PFR to an axial peak burn-up of 4.2 a/o.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States); UKAEA Atomic Energy Research Establishment, Harwell
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
7143046
Report Number(s):
CONF-840614-1; ON: DE84004017
Resource Relation:
Conference: Annual meeting of the American Nuclear Society, New Orleans, LA, USA, 3 Jun 1984
Country of Publication:
United States
Language:
English