Post irradiation examination of uranium inclusions in inert matrices.

Neeft, E.A.C.; Bakker, K.; Buurveld, H.A.; Minkema, J.; Paardekooper, A.; Schram, R.P.C.; Sciolla, C.; Zwaagstra, O.; Beemsterboer, B.; Woittiez, J. R. W.; Vlaanderen, P. van; Tams, W.J.; Hein, H.; Conrad, R.; Veen, A. van

doi:10.1016/s0149-1970(00)00151-7

Cited by 8 publications

(2 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Such hair cracks may occur by the stress caused from a thermal expansion difference between the large YSZ fuel particles and matrices. A similar FGR behavior was reported recently by Bakker et al 27) and Neeft et al 28) They observed higher FGR for the "macro" dispersed fuels, where large fissile inclusions of diameter about 150 µm were dispersed in spinel matrix, than the "micro" dispersed ones of which typical fissile inclusion size was less than 1 µm. In order to reduce the FGR of the particle-dispersed fuels, sintering condition and procedure for the fuel fabrication must be improved to obtain fuel pellets with the optimum sintered density and with gaps between the particle and spinel matrix so that hair crack generation can be suppressed during irradiation.…”

Section: In-pile Irradiation Testsupporting

confidence: 88%

Rock-Like Oxide Fuels and Their Burning in LWRs.

Yamashita

Kuramoto

Akie

et al. 2002

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

Research on the plutonium rock-like oxide (ROX) fuels and their once-through burning in light water reactors has been performed to establish an option for utilizing and disposing effectively the excess plutonium. The ROX fuel is a sort of the inert matrix fuels and consists of mineral-like compounds such as yttria stabilized zirconia, spinel and corundum. A particle-dispersed fuel was devised to reduce damage by heavy fission fragments. Some preliminary results on swelling, fractional gas release and microstructure change for five ROX fuels were obtained from the irradiation test and successive post-irradiation examinations. Inherent disadvantages of the Pu-ROX fuel cores could be improved by adding 238 U or 232 Th as resonant materials, and all improved cores showed a nearly the same characteristics as the conventional UO 2 core during transient conditions. The threshold enthalpy of the ROX fuel rod failure was found to be comparable to the fresh UO 2 rod by pulse-irradiation tests simulating reactivity initiated accident conditions.

show abstract

Section: In-pile Irradiation Testsupporting

confidence: 88%

Rock-Like Oxide Fuels and Their Burning in LWRs.

Yamashita

Kuramoto

Akie

et al. 2002

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

show abstract

“…The thermal expansion coefficients of spinel and YSZ (containing UO 2 ) are 8.5 Â 10 À6 and 1.1 Â 10 À5 K À1 , respectively, at 298-1273 K [3]. A similar FGR behavior was observed in EFTTRA-T3 experiment [27,28]. The FGR of dispersed type fuel with large fissile inclusions (150 lm) was remarkably higher than that with small fissile inclusions (<1 lm) dispersed type fuel, and many cracks were observed in the matrix of large fissile inclusions dispersed type fuel.…”

Section: Fractional Fission-gas Releasesupporting

confidence: 72%