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Fuketa, Toyoshi; Sugiyama, Tomoyuki; Sasajima, Hideo; Nagase, Fumihisa
Proceedings of 2005 Water Reactor Fuel Performance Meeting (CD-ROM), p.633 - 645, 2005/10
LWR fuel behaviors during a reactivity initiated accident (RIA) are being studied in the NSRR program. Results from recent NSRR experiments, no failures in Tests OI-10 and -12 and the higher failure enthalpy in Test OI-11, reflect the better performance of the new cladding materials in terms of corrosion during PWR operations. Accordingly, these rods with improved corrosion resistance have larger safety margin than conventional Zircaloy-4 rods. In addition, the smaller inventory of inter-granular gas in the large grain pellet could reduce the fission gas release in RIA as observed in the OI-10. Test VA-1 was conducted with an MDA sheathed 78 MWd/kgU PWR fuel rod. Despite of the higher burnup and thicker oxide layer of 
81
m, the enthalpy at failure remained in a same level as those for rods with of 40m-oxide at 50 - 60 MWd/kgU. This result suggests high burnup structure (rim structure) in pellet periphery does not have strong effect on the failure enthalpy reduction because the PCMI load is produced primarily by solid thermal expansion of the pellet.
Aihara, Jun; Sawa, Kazuhiro; Furuya, Yoshio*; Hojo, Tomohiro*; Furuno, Shigemi*; Yamamoto, Hiroyuki; Hojo, Kiichi; Ishihara, Masahiro
Journal of the American Ceramic Society, 88(8), p.2319 - 2321, 2005/08
Times Cited Count：0 Percentile：0.02(Materials Science, Ceramics)no abstracts in English
Igawa, Naoki; Ishii, Yoshinobu; Hoshikawa, Akinori; Yamauchi, Hiroki; Shimoyama, Tomotaka
JAERI-Tech 2004-067, 23 Pages, 2004/11
JAERI-Tech-2004-067.pdf:5.88MB
We synthesized methane hydrate using fine grain ice. The amount of released-gas volume was the same as calculated one for ideal methane hydrate within experimental precision. The neutron diffraction measurement was conducted by means of a high-resolution powder diffractometer (HRPD) installed at JRR-3. No reflection line from the impurities and ice was found in the diffraction pattern. Therefore, the synthesized methane hydrate proved to be very high quality. We also showed the scattering density map of this sample using Rietveld analysis and the maximum entropy method (MEM).
Suzuki, Motoe
Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.131 - 140, 2001/06
no abstracts in English
Maebara, Sunao
JAERI-Research 2000-061, 104 Pages, 2001/01
JAERI-Research-2000-061.pdf:9.71MB
no abstracts in English
Maebara, Sunao; Goniche, M.*; Kazarian, F.*; Seki, Masami; Ikeda, Yoshitaka; Imai, Tsuyoshi; Bibet, P.*; Froissard, P.*; Rey, G.*
Fusion Engineering and Design, 49-50, p.269 - 273, 2000/11
Times Cited Count：4 Percentile：32.52(Nuclear Science & Technology)no abstracts in English
; ; ; Matsumoto, Shinichiro
JNC TN9410 2000-009, 65 Pages, 2000/09
JNC-TN9410-2000-009.pdf:4.36MB
In order to evaluate irradiation behavior of(U, Pu) C and (U, Pu) N fuel using fast reactor, (U, Pu) C and (U, Pu) N fuel pins were irradiated in JOYO for the fist time in Japan. In this study, one (U, Pu) C fuel pin and two (U, Pu) N fuel pins were irradiated to maximum burn up about 40GWd/t. Post irradiation examination of (U, Pu) C and (U, Pu) N fuel pins started in Fuel Monitoring Facility (FMF) at JNC from October 1999, and it ended in March, 2000. The results of non-destructive post irradiation examination reported in this document. Main results are shown in the following. (1)The soundness of all (U,Pu) C and (U,Pu) N fuel pins were confirmed from the non-destructive examination result. (2)The fuel stack elongation of (U,Pu) C and (U,Pu) N is bigger than it of the MOX fuel for fast reactor. (3)The singular behavior from the gamma ray scanning measurement in the stack area was not confirmed. The migration of Cs137 to lower insulator pellet and outside of the pellet was confirmed in (U,Pu) N B9NO2 pin. In (U,Pu) C fuel, the migration of Cs137 was not confirmed. (4)In (U,Pu) C B9CO1 pin and (U,Pu) N B9NO2 pin in which the gap width was small, diameter of cladding increase around 50 m in the stack area which originates for FCMI was confirmed. In (U,Pu) N B9NO1 pin in which the gap width was wide, the ovality which originates from the relocation of the pellet was confirmed. (5)Fission gas release rate of (U,Pu) N were 3.3% and 5.2%, and the low value compared to the MOX fuel was shown.
Mine, Tatsuya*; Mihara, Morihiro;
JNC TN8430 2000-010, 27 Pages, 2000/07
JNC-TN8430-2000-010.pdf:0.72MB
In the geological disposal system of the radioactive wastes, gas generation by microorganism could be significant for the assessment of this system, because organic material included in groundwater, buffer material and wastes might serve as carbon sources for microorganisms. In this study, gas generation tests using microorganisms were carried out under anaerobic condition. The amount of methane and carbon dioxide that were generated by activity of Methane Producing Bacteria (MPB) were measured with humic acid, acetic acid and cellulose as carbon sources. The results showed that methane was not generated from humic acid by activity of MPB. However, in the case of using acetic acid and cellulose, methane was generated, but at high pH condition (pH=10), the amount of generated methane was lower than at low pH (pH=7). It was not clear whether the pH would affect the amount of generated carbon dioxide.
Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Kikuchi, Keiichi*
Journal of Nuclear Science and Technology, 37(5), p.455 - 464, 2000/05
no abstracts in English
Oishi, Tetsuya; Yoshida, Makoto
Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 4 Pages, 2000/05
no abstracts in English
; ;
JNC TN9400 2000-041, 29 Pages, 2000/03
JNC-TN9400-2000-041.pdf:1.18MB
Irradiation behavior and performance models were investigated in order to apply for nitride fuel options in feasibility study on fast breeder reactor and related recycle systems. (1)MechanicaI design of nitride fuel pin: The behaviors of fission gas release (increase of internal Pressure) and fuel-to-cladding chemical interaction (decrease of cladding thickness) are needed to evaluate cumulative damage fraction in case of fuel pin mechanical design. The behaviors of fission gas release and fuel-to-cladding chemical interaction were investigated from the past studies up to high burnuP, since the lower fission gas release in nitride fuel than in oxide fuel could contribute to reduce the plenum volume and result in the shortening of fuel Pin length. (2)Fuel pin smear density: The higher fuel smear density is preferred for the higher fissile density to improve the core characteristic. The behaviors of fuel pellet swelling were investigated from the past studies up to higher burnup, since the larger fuel pellet swelling in nitride fuel than in oxide fuel would restrict high burunp capability due to fuel-cladding mechanical interaction. (3)Compatibility of nitride fuel with high Temperature water: Compatibility of nitride fuel with high temperature water were investigated from the past studies to contribute water cooled fast breeder reactor options.
;
JNC TN9400 2000-031, 15 Pages, 2000/03
JNC-TN9400-2000-031.pdf:0.53MB
For the irradiation performance of metallic fuel, many of the analyses were conducted in USA using EBR-l and EBR-II. ln this study, based on the published data and papers on the above results, the appropriate methods to the evaluation of the irradiation performance of FBR metallic fuel for the design study were considered, as the fbasibility study for FBR. The followings are the targets in this work; (1)deformation of cladding (2)deformation of fuel slug (3)FP gas release (4)fluctuation of the bonding Na level in the fuel pin (5)FCCI
Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*
JAERI-Research 99-060, p.62 - 0, 2000/03
JAERI-Research-99-060.pdf:12.05MB
no abstracts in English
Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Kimura, Yasuhiko; Nagashima, Hisao; Sekita, Noriaki; Arai, Yasuo
JAERI-Research 2000-010, p.110 - 0, 2000/03
JAERI-Research-2000-010.pdf:20.61MB
no abstracts in English
*; *; *; Hino, Tomoaki*; Ogiwara, Norio; Yagyu, Junichi; Saido, Masahiro
Vacuum, 53(1-2), p.309 - 312, 1999/00
Times Cited Count：3 Percentile：18.87(Materials Science, Multidisciplinary)no abstracts in English
Maebara, Sunao; ; Seki, Masami; Suganuma, Kazuaki; Ikeda, Yoshitaka; Imai, Tsuyoshi; Goniche, M.*; J.Brossaud*; V.Cano*; F.Kazarian-Vibert*; et al.
JAERI-Research 97-086, 29 Pages, 1997/11
JAERI-Research-97-086.pdf:1.33MB
no abstracts in English
Iwai, Takashi; Nakajima, Kunihisa; Arai, Yasuo;
IAEA-TECDOC-970, 0, p.137 - 153, 1997/10
no abstracts in English
Suzuki, Yasufumi; Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa
Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.522 - 527, 1997/00
no abstracts in English
