Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.021 seconds
Na, Sang Ho; Kang, K. H.; Park, C. J.; Kim, Y. H.; Joo, Y. J.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
AbstractAbstract
[en] Fission products, which were created in a UO2 matrix during irradiation, depend on burnup, power, average neutron energy, irradiation time and cooling period, etc. According to their physical and chemical characteristics, fission products divide three groups, that is, soluble in UO2(solid formation), insoluble in UO2(precipitate) and volatile fission gases. Simfuels(simulated fuel) are fabricated to duplicate an irradiated nuclear fuel. There are abundant studies on some characteristics and fabrication of simfuel due to the non-active material. In this report, three different contents of (U,SS)O2 pellet were fabricated. SS is a mixture of 7 soluble oxides -SrO, Y2O3, ZrO2, TeO2, La2O3, CeO2 and Nd2O3- in UO2 matrix. SS-1 have a 1.63wt%, SS-2 have a 3.25wt% and SS-4 have a 6.51wt% of soluble oxides in UO2 matrix. Steady-state reep strain rate, transition stress, stress exponent and creep activation energy of these contents of (U,SS)O2 pellets were investigated
Primary Subject
Source
Dec 2009; 40 p; Also available from KAERI; 6 refs, 16 figs, 6 tabs
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue