Influence of initial conditions on rod behaviour during boiling crisis phase following a reactivity initiated accident

Georgenthum, V.*; Sugiyama, Tomoyuki

Proceedings of OECD/NEA Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents (CD-ROM), 9 Pages, 2009/09

Fracture mechanics approach for failure mode analysis in CABRI and NSRR RIA tests

Georgenthum, V.*; Sugiyama, Tomoyuki; Udagawa, Yutaka; Fuketa, Toyoshi; Desquines, J.*

Proceedings of Water Reactor Fuel Performance Meeting 2008 (WRFPM 2008) (CD-ROM), 8 Pages, 2008/10

Analysis of CIP0-1 and VA-2 tests

Georgenthum, V.*

no journal, , 

Two fuel rods with same specification, Zirlo alloy cladded UO, were submitted to RIA tests VA-2 and CIP0-1 in NSRR and CABRI reactors, respectively. Both rods were irradiated simultaneously in Spanish PWR Vandellos till a burnup of 80 GWd/tM and presented a significant clad oxide thickness (80 m) and hydrogen content (1000 ppm). While VA-2 rod failed at a fuel enthalpy of 55 cal/g, CIP0-1 rod survived an enthalpy of 92 cal/g. Post test examinations showed VA-2 clad had some signs of brittleness due to hydride precipitation in the half outer part while in CIP0-1 clad brittleness is only observed in the outer hydride rim (50 m). The different clad behaviour could be explained by the difference of the thermal history during the tests as exhibited by SCANAIR code calculations: while CIP0-1 clad outer temperature reached 400 C and an important quantity of hydride was dissolved, VA-2 clad remained at low temperature and was significantly brittle.