Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6680965

Liu, Y Y; Tsai, H; Billone, M C; Kramer, J M ^[1]

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1. Argonne National Lab., IL (United States)

The next step in the development of metal fuels for the integral fast reactor (IFR) is the conversion of the Experimental Breeder Reactor II (EBR-II) core to one containing the ternary U-20 Pu-10 Zr alloy clad with HT-9 cladding, i.e., the Mk-V core. This paper presents results of three hot-cell furnace simulation tests on irradiated Mk-V-type fuel elements (U-19 Pu-10 Zr/HT-9), which were performed to support the safety case for the Mk-V core. These tests were designed to envelop an umbrella (bounding) unlikely loss-of-flow (LOF) event in EBR-II during which the calculated peak cladding temperature would reach 776[degree]C for < 2 min. The principal objectives of these tests were (a) demonstration of the safety margin of the fuel element, (b) investigation of cladding breaching behavior, and (c) provision of data for validation of the FPIN2 and LIFE-METAL codes.

• OSTI ID: 6680965
• Report Number(s): CONF-921102-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
EBR-2 REACTOR
LOSS OF FLOW
FUEL ELEMENTS
PERFORMANCE TESTING
COMPUTER CODES
FUEL CANS
IFR REACTOR
LIQUID METAL FUELS
SAFETY ANALYSIS
SIMULATION
ZIRCALOY
ACCIDENTS
ALLOYS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
TESTING
ZERO POWER REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test &amp; Experimental Reactors