Posttest examination results of recent treat tests on metal fuel

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:7124731

Holland, J W; Wright, A E; Bauer, T H; Goldman, A J; Klickman, A E; Sevy, R H

A series of in-reactor transient tests is underway to study the characteristics of metal-alloy fuel during transient-overpower-without-scam conditions. The initial tests focused on determining the margin to cladding breach and the axial fuel motions that would mitigate the power excursion. The tests were conducted in flowing-sodium loops with uranium - 5% fissium EBR-II Mark-II driver fuel elements in the TREAT facility. Posttest examination of the tests evaluated fuel elongation in intact pins and postfailure fuel motion. Microscopic examination of the intact pins studied the nature and extent of fuel/cladding interaction, fuel melt fraction and mass distribution, and distribution of porosity. Eutectic penetration and failure of the cladding were also examined in the failed pins.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7124731
• Report Number(s): CONF-860931-12; ON: DE87004998
• Resource Relation: Conference: International conference on reliable fuels for liquid metal reactors, Tucson, AZ, USA, 7 Sep 1986; Other Information: Microfiche only, copy does not permit paper copy reproduction
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
TREAT REACTOR
MATERIALS TESTING
FUEL CANS
FUEL PINS
NUCLEAR FUELS
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
ACCIDENTS
AIR COOLED REACTORS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FUEL ELEMENTS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding
420500 - Engineering- Materials Testing