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Kato, Masato; Komeno, Akira; Uno, Hiroki*; Sugata, Hiromasa*; Nakae, Nobuo; Konashi, Kenji*; Kashimura, Motoaki
Journal of Nuclear Materials, 393(1), p.134 - 140, 2009/08
Times Cited Count：41 Percentile：92.56(Materials Science, Multidisciplinary)In plutonium compounds, the lattice parameter increases due to self-radiation damage by 
-decay of plutonium isotopes. The lattice parameter change and its thermal recovery in plutonium and uranium mixed dioxide (MOX) were studied. The lattice parameter for samples of MOX powders and pellets that had been left in the air for up to 32 years was measured. The lattice parameter increased and was saturated at about 0.29%. The change in lattice parameter was formulated as a function of self-radiation dose. Three stages in the thermal recovery of the damage were observed in temperature ranges of below 673K, 673-1073K and above 1073K. The activation energies in each recovery stage were estimated to be 0.12 eV, 0.73 eV and 1.2 eV, respectively, and the corresponding mechanism for each stage was considered to be the recovery of the anion Frenkel defect, the cation Frenkel defect and a defect connected with helium, respectively.
Pu
)O
and (U
Pu
)O based on point defect chemistryKato, Masato; Konashi, Kenji*; Nakae, Nobuo
Journal of Nuclear Materials, 389(1), p.164 - 169, 2009/05
Times Cited Count：25 Percentile：83.26(Materials Science, Multidisciplinary)Stoichiometries in (UPu)O and (UPu)O were analyzed from the experimental data of oxygen potential based on point defect chemistry. The relation between the deviation x from stoichimetric composition and oxygen partial pressure were evaluated. The concentrations of the point defects in MOX were estimated from the measured data of oxygen potential as functions of temperature and using Kr
ger-Vink diagram. The analysis results showed that x was proportional to near stoichiometric region of both (UPu)O and (UPu)O, which suggested that intrinsic ionization was dominant defect. The model to calculate oxygen potential was derived and represented the experimental data with precision, and thermodynamic data.
JNC TN8410 2003-020, 33 Pages, 2004/03
JNC-TN8410-2003-020.pdf:4.12MB
It is speculated that many people know the fact that research and development on Fast Breeder Reactor and the related Nuclear Fuel Cycle is performed in Japan. However, it is not well understood the exact status of R&D on FBR cycle system after the sodium leak accident that occurred in Monju. A very few specialist of FBR seems to know that FBR cycle system was closed. Thus, the way how the FBR cycle system was closed and the continuous R&D activities up to now are introduced in this report from the technical point of view. The FBR cycle system is considered to be the fission energy utilization system having the capabilities such as high uranium utilization, the relief of the impact on environment due to annihilation of fission products and minor actinides in the FBR core, and the high resistance for proliferation. The FBR cycle system has many important advantages shown above. If the enhancement of FBR cycle characteristics in economical and safety aspect might be possible, the system considered to be the ideal system for fission energy utilization. Therefore, the important information about R&D on FBR cycle system is introduced here together with the private concept on the items and the procedure of R&D related FBR cycle system demonstration.
Nakae, Nobuo
PNC TN1102 97-015, 27 Pages, 1997/12
None
; Sugiyama, Kenji; ; ; ; Ojima, Hisao;
PNC TN1430 97-005, 229 Pages, 1997/11
no abstracts in English
; Nagai, Shuichiro
Proceedings of 3rd International Conference on Nuclear Engineering (ICONE-3), 0 Pages, 1995/00
None
Hayashi, Hideyuki; Shikakura, Sakae; ; ; Otani, Tetsuo; *
PNC TN9410 94-078, 58 Pages, 1994/03
This report summarizes the results of the study on fuel design specifications for a large scale LMFBR in the fiscal year 1993. The items contained in the report are as follows; (1)Study on the power flattening of a 1600MWt-class large FBR core (2)Study on the irradiation behavior of the DFBR driver fuel
; ;
Technical Committee Meeting on Reacent Development on Post-Irradiation Examination Technigues for Wa, 0 Pages, 1994/00
None
Hayashi, Hideyuki; Shikakura, Sakae; ; ; ; Otani, Tetsuo
PNC TN9410 93-066, 47 Pages, 1993/03
This report summarizes the results of the study on fuel design specifications for a large scale LMFBR in the fiscal year 1992. The items contained in the report are as follows; (1)Present status of the fuel development in PNC (2)R&Ds on the deformation of fuel subassemblies in PNC (3)Sufficiency of the strength data of PNC1520-steel in high temperature region
; *; ; ; ; Matsumoto, Mitsuo
PNC TN8410 92-187, 21 Pages, 1992/05
Computer code for fuel temperature evaluation of LMFBR at early burnup has been developed. On fule temperature evaluation, especially at early burnup, the fuel restructuring model and the gap conductance medel are important. These models which are installed in the temperature evaluation code, were verified based on the results of irradiation tests using the foreign fast reactor and "JOYO". This paper describes the essential parts of the models and the functions of the code (DIRAD) which is used for the fuel temperature evaluation at early burnup of LMFBR such as the prototype fast breeder reactor "MONJU".
; Shikakura, Sakae; Nagai, Shuichiro; ;
PNC TN9410 92-052, 56 Pages, 1992/02
This report summarizes the results of the study on fuel design specifications for a large scale LMFBR in the fiscal 1992. Discussed items in the present study are as follows; (1)Annular pellet (2)Steady state and transient fuel pin performance (3)Physical properties of core materials for design study.
Komoda, S.; Nakae, Nobuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.319 - 322, 1992/00
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)Abe, Tomiyuki; Nakae, Nobuo; Kodato, Kazuo; Matsumoto, Mitsuo
Journal of Nuclear Materials, 188, p.154 - 161, 1992/00
Times Cited Count：6 Percentile：53.17(Materials Science, Multidisciplinary); Shikakura, Sakae; ;
PNC TN9410 91-031, 25 Pages, 1991/01
This report summarizes the results of the study on fuel design specifications for a large scale LMFBR in the fiscal 1990. Discussed items in the present study are as follows; (1)Physical properties of core materials for design study (2)Irradiation behavior of a large diameter fuel pin
Nakae, Nobuo; ;
Donen Giho, (70), p.77 - 81, 1989/06
