Integral fast reactor safety tests M2 and M3 in TREAT

Conference · Fri Nov 01 04:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5464760

Robinson, W R; Lo, R K; Wright, A E; Bauer, T H; Stanford, G S; Morman, J A

Transient Reactor Test Facility (TREAT) tests M2 and M3 were performed to obtain information on two key fuel behavior characteristics of transient overpower conditions in metal-fueled fast reactors: the margin to cladding breach and the axial self-extrusion of fuel within intact cladding. Cladding breach depends on penetration of a fuel/cladding eutectic into the cladding as well as on internal pin pressure. Driving forces for fuel extrusion are fission gas, liquid sodium, and volatile fission products trapped within the fuel. Significant fuel extrusion prior to cladding breach would be an important factor in the case for benign termination of unprotected overpower events in a fast reactor. These preliminary tests in the Integral Fast Reactor (IFR) program were done on uranium-5% fissium Experimental Breeder Reactor II Mark-II driver fuel pins having an active fuel column length of 34 cm.

• Research Organization: Argonne National Lab., IL
• OSTI ID: 5464760
• Report Number(s): CONF-851115-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
• Country of Publication: United States
• Language: English

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