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Ishii, Tetsuya; Hirosawa, Takashi
PNC TN9410 97-075, 20 Pages, 1997/08
Fuel melting temperature is one of the major thermodynamical properties that is used for determining the design criteria on fuel temperature during irradiation in FBR. In general, it is necessary to evaluate the correlation of fuel melting temperature to confirm that the fuel temperature must be kept below the fuel melting temperature during irradiation at any conditions. The correlations of the melting temperature of uranium-plutonium mixed oxide (MOX) fuel, typical FBR fuel, used to be estimated and formulized based on the measured values reported in 1960's and has been applied to the design. At present, some experiments have been accumulated with improved experimental techniques. And it reveals that the recent measured melting temperatures does not agree well to the data reported in 1960's and that some of the 1960's data should be modified by taking into account of the recent measurements. In this study, the experience of melting temperature up to now are summarized and evaluated in order to make the fuel pin design more reliable. The effect of plutonium content, oxygen to metal ratio and burnup on MOX fuel melting was examined based on the recent data under the UO
- PuO - PuO
ideal solution model, and then formulized. The correlation obtained in this work is as-follows; T = T
+ 
T
+ T
+ T
----(A) T = 3120 T = -5.7537
PU + 1.363110
PU
+ 1.795210
PU
T = -1.41 PU (2.00 - OP)/0.39 OP : OP = 
/(0.01PU) T = -5.0BU/10000 where T is the melting temperature (degree of K), PU is the weight fraction of PuO in the mixed oxide fuel, OM is the oxygen to metal ratio, and BU is the burnup in the unit of MWd/MTM. respectively. T (plutonium content), T (O/M Ratio), 
...
; Nemoto, Takeshi; Numata, Koji; *; *; Hanawa, Eiji*; *
PNC TN8440 94-011, 19 Pages, 1994/04
None
Sakurai, Satoshi; Usuda, Shigekazu; ; Hirata, Masaru; ; Tachimori, Shoichi
Nihon Genshiryoku Gakkai-Shi, 35(2), p.147 - 154, 1993/02
no abstracts in English
Sakurai, Satoshi; Tachimori, Shoichi; Akatsu, Jokun; Kimura, Takaumi; Yoshida, Zenko; ; Yamashita, Toshiyuki; Ouchi, Kinji
Nihon Genshiryoku Gakkai-Shi, 31(11), p.1243 - 1250, 1989/11
Times Cited Count：3 Percentile：41.84(Nuclear Science & Technology)no abstracts in English
; ;
J.Less-Common Met., 121, p.631 - 636, 1986/00
Times Cited Count：13 Percentile：80.28(Chemistry, Physical)no abstracts in English
; ;
Journal of Nuclear Science and Technology, 22(4), p.329 - 330, 1985/00
Times Cited Count：3 Percentile：53.49(Nuclear Science & Technology)no abstracts in English
; ;
Journal of Nuclear Materials, 115, p.331 - 333, 1983/00
Times Cited Count：5 Percentile：85.28(Materials Science, Multidisciplinary)no abstracts in English
to(U,Pu)C; ; ;
Journal of Nuclear Science and Technology, 20(10), p.874 - 876, 1983/00
Times Cited Count：1 Percentile：27.09(Nuclear Science & Technology)no abstracts in English
; ; *
JAERI-M 9201, 51 Pages, 1980/11
no abstracts in English
*; *; ; ; ; Tagawa, Hiroaki
Journal of Nuclear Materials, 95, p.181 - 184, 1980/00
Times Cited Count：13 Percentile：77.12(Materials Science, Multidisciplinary)no abstracts in English
-RuO mixture and recovery of plutonium by thermal decomposition; ;
Journal of Nuclear Science and Technology, 11(2), p.74 - 76, 1974/02
Times Cited Count：3no abstracts in English
