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Uwaba, Tomoyuki; Yokoyama, Keisuke; Nemoto, Junichi*; Ishitani, Ikuo*; Ito, Masahiro*; Pelletier, M.*
Nuclear Engineering and Design, 359, p.110448_1 - 110448_7, 2020/04
Times Cited Count：1 Percentile：11.8(Nuclear Science & Technology)Coupled computer code analyses of irradiation performance of axially heterogeneous mixed oxide (MOX) fuel elements with high burnup in a fast reactor were conducted. Post-irradiation experiments revealed local concentration of Cs near the interfaces between MOX fuel and blanket columns including the internal blanket of the fuel elements as well as an increase in their cladding diameters. The analyses indicated that the local Cs concentration occurred as a result of Cs axial migration from the MOX fuels toward the blanket pellets near the interfaces. Swelling of the blanket pellets induced by the formation of low-density Cs-U-O compound was not sufficient to cause pellet-to-cladding mechanical interaction (PCMI). The PCMI analyzed in the MOX fuel column regions was insignificant, and the cladding diameter increases were caused mainly by void swelling in cladding and irradiation creep due to fission gas pressure.
Ohgama, Kazuya; Oki, Shigeo; Kitada, Takanori*; Takeda, Toshikazu*
Proceedings of 21st Pacific Basin Nuclear Conference (PBNC 2018) (USB Flash Drive), p.942 - 947, 2018/09
Takahashi, Satoshi*; Okuno, Hiroshi; Miyoshi, Yoshinori
JAERI-Tech 2005-056, 51 Pages, 2005/09
JAERI-Tech-2005-056.pdf:2.92MB
In the heterogeneous system of the mixed oxide fuel of uranium and plutonium, hereafter, MOX fuel, it was investigated whether the system could be modeled as a homogeneous system on the conditions which dealt with the MOX fuel of particle diameter 0.02mm or less in MOX fuel fabrication facilities in Japan. The infinite multiplication factor of the homogeneous system of the MOX fuel was first calculated, and the optimum moderation condition over the each ratio of PuO
was determined. It was verified that carried out critical calculation for the heterogeneous system of the MOX fuel in which the spherical fuel diameter in a cube unit cell increased, and an atomic number ratio of hydrogen to heavy metal fixed conditions, and the probability for neutrons to escape resonance by a spherical fuel diameter no less than 0.1mm, and analyzed critical conditions etc. using a contiguous energy Monte Carlo code MVPII and JENDL3.3. The details of these calculations are reported. These results are expected to be quoted in a revised edition of "Nuclear Criticality Safety Handbook."
Arai, Yasuo; Pillon, S.*
Proceedings of International Conference ATALANTE 2004 Advances for Future Nuclear Fuel Cycles (CD-ROM), 9 Pages, 2004/06
no abstracts in English
Sono, Hiroki; Fukaya, Yuji; Yanagisawa, Hiroshi; Miyoshi, Yoshinori
JAERI-Tech 2003-065, 61 Pages, 2003/07
JAERI-Tech-2003-065.pdf:3.11MB
A series of critical experiments using a heterogeneous core of the Static Experiment Critical Facility (STACY) in the Japan Atomic Energy Research Institute is planned in F.Y. 2003. In the experiment, the core is composed of uranyl nitrate solution (
U enrichment 6 wt%) and 333 pins of uranium dioxide (U enrichment 5 wt%) loaded in lattice-pitch of 1.5 cm. Prior to the experiment, neutronic characteristics are analyzed to evaluate neutronic safety and criticality limitations of the core. The analyzed items are the parameters on criticality, reactivity and reactor shutdown margins. In the analyses, a Monte Carlo code, MVP, and a neutronics code system, SRAC, have been used with an evaluated nuclear data library, JENDL-3.3. By using the calculated characteristics, simplified equations to interpolate these values and criticality limitations of the core are evaluated. It has been also confirmed that the reactor shutdown margins will comply with safety criteria under all fuel conditions in the experiments.
; Sato, Wakaei*;
JNC TN9400 2000-037, 87 Pages, 2000/03
JNC-TN9400-2000-037.pdf:3.48MB
ln order to compare the nuclear characteristics of water-cooled bleeder cores with that of LMFBR, MOX fuel cell models are established for boiling and non-boiling LWR, non-boiling HWR and sodium-cooled reactor. Frst, the comarison is made between the heterogeneous cell calculation results by SRAC and those by SLAROM. The results show some differences as for neutron energy spectrum, one-grouped cross section and conversion ratio due to the different grouped cross section library (both are based on JENDL-3.2, though) used for each code, however, the difference is acceptably small for grasping the basic characteristics of the above-mentioned cores. Second, using the SLAROM code, main core parameters such as mean neutron energy, ratio of fast neutron and 
-value, are analyzed. The comparison between the cores show that softened neutron spectrum by the scattering effect of hydrogen or heavy hydrogen increase the contribution of nuclear reaction (especially for neutron capture reaction rather than fission reaction) in lower energy region comparing with LMFBR. ln order to overcome the effect, tighter lattice than LMFBR is necessary for water-cooled cores to realize the breeding of fissile nuclides. Third, effects of Pu isotopic composition on the breeding ratio are evaluated using SRAC burnup calculation. From the results, it is confirmed that degraded Pu (larger ratio of Pu-240) show the larger breeding ratio. At last, sensitivity analyses are made for k-effective and main reaction ratios. As for k-effective, using a temporary covariance data of JENDL-3.2, uncertainty resulting from the cross sections' error is analyzed for a boiling LWR and a sodium-cooled reactor. The boiling LWR core shows larger sensitivity in lower energy region than the sodium-cooled reactor (especially for the energy region lower than 1kev), And, 18-group analysis that is considered acceptably good for LMFBR analysis, should not be enough for accurate sensitivity estimation of ...
Oigawa, Hiroyuki
JAERI-Research 98-061, 22 Pages, 1998/11
JAERI-Research-98-061.pdf:0.76MB
no abstracts in English
Arai, Yasuo
Purutoniumu Nenryo Kogaku; Nihon Genshiryoku Gakkai "Jisedai Nenryo" Kenkyu Semmon Iinkai, p.330 - 338, 1998/00
no abstracts in English
; Nakano, Yoshihiro; Yamane, Yoshihiro*; *;
JAERI-Research 95-059, 83 Pages, 1995/09
JAERI-Research-95-059.pdf:2.24MB
no abstracts in English
Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Kuroda, Toshimasa*; S.Zimin*
JAERI-M 92-093, 53 Pages, 1992/07
no abstracts in English
; Okumura, Keisuke; ; *; *
JAERI-M 92-030, 68 Pages, 1992/03
no abstracts in English
; ; Oku, Tatsuo*; H.Schiffers*; W.Delle*
Journal of Nuclear Science and Technology, 28(8), p.713 - 720, 1991/08
no abstracts in English
*; Takatsu, Hideyuki; Kuroda, Toshimasa*; Seki, Yasushi; Nakamura, Tomoo; Mori, Seiji*; *
JAERI-M 91-046, 163 Pages, 1991/03
no abstracts in English
Takeda, Toshikazu*; Ito, Noboru*; Kugo, Teruhiko*; Takamoto, Masanori*; Aoki, Shigeaki*; Kawagoe, Yoshihiro*; Sengoku, Katsuhisa*; Tanaka, Motonari*; Yoshimura, Akira*; Tamitani, Masashi*; et al.
PNC TJ2605 89-001, 251 Pages, 1989/03
no abstracts in English
Iijima, Susumu; Okajima, Shigeaki; Obu, Makoto; Osugi, Toshitaka; ; ; *
Journal of Nuclear Science and Technology, 26(2), p.221 - 230, 1989/02
no abstracts in English
Iijima, Susumu; Obu, Makoto; *; Ono, Akio; ; Okajima, Shigeaki
Nuclear Science and Engineering, 100, p.496 - 506, 1988/12
Times Cited Count：2 Percentile：31.31(Nuclear Science & Technology)no abstracts in English
Ono, Akio; ;
Journal of Nuclear Science and Technology, 25(1), p.32 - 44, 1988/01
no abstracts in English
-Scanning Method; Ono, Akio; ; *
JAERI-M 86-191, 76 Pages, 1987/01
no abstracts in English
; ; *; ; ; *; ; Ono, Akio; ; *; et al.
JAERI-M 86-065, 126 Pages, 1986/03
no abstracts in English
