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Journal Articles

Homogeneity of (U, $$M$$)O$$_2$$ ($$M$$ = Th, Np) prepared by supercritical hydrothermal synthesis

Shirasaki, Kenji*; Tabata, Chihiro*; Sunaga, Ayaki*; Sakai, Hironori; Li, D.*; Konaka, Mariko*; Yamamura, Tomoo*

Journal of Nuclear Materials, 563, p.153608_1 - 153608_11, 2022/05

 Times Cited Count:2 Percentile:53.91(Materials Science, Multidisciplinary)

We focused on the direct synthesis of (U, $$M$$)O$$_2$$ solid solution ($$M$$=Th, Np) by extending our recent progress in hydrothermal synthesis with additives. The homogeneity of the (U, $$M$$)O$$_2$$ ($$M$$ = Th, Np) systems prepared by supercritical hydrothermal reactions was investigated through crystallographic analysis based on Vegard's law, and the $$^{23}$$Na nuclear magnetic resonance (NMR) measurement of (U, Np, Na)O$$_2$$ solid solutions. Our experimental and analytical results revealed that (i) an optimal additive is ammonium carbonate and starting uranium valence is IV in the case of (U, Th)O$$_{2+x}$$, and (ii) an optimal additive is ethanol and starting uranium valence is VI in the case of (U, Np)O$$_{2+x}$$, for producing the homogeneous solid solutions by hydrothermal synthesis.

Journal Articles

Crystal structure of U$$_{1-y}$$Ln$$_{y}$$O$$_{2-x}$$ (Ln = Gd, Er) solid solution

Pham, V. M.*; Arima, Tatsumi*; Inagaki, Yaohiro*; Idemitsu, Kazuya*; Akiyama, Daisuke*; Nagai, Takayuki; Okamoto, Yoshihiro

Journal of Nuclear Materials, 556, p.153189_1 - 153189_9, 2021/12

 Times Cited Count:1 Percentile:16.35(Materials Science, Multidisciplinary)

The crystal structure change was evaluated for (1-x)UO$$_{2}$$-xLnO$$_{1.5}$$ (Ln=Gd or Er; x = 0 to 0.4) samples sintered at 1973 K for 8 h under Ar and Ar-10%H$$_{2}$$ atmospheres. The effect of LnO$$_{1.5}$$ doping on the crystal structure of UO$$_{2}$$ was investigated by X-ray diffraction (XRD) and X-ray absorption fine structure (XAFS). LnO$$_{1.5}$$ doping into UO$$_{2}$$ reduced the lattice parameter of UO$$_{2}$$-LnO$$_{1.5}$$ solid solutions up to 40mol% LnO$$_{1.5}$$. The lattice parameters of these samples were comparable to those of stoichiometric (U,Ln)O$$_{2.00}$$ solid solutions, that is, the O/M ratios were close to 2.00. The U L$$_{3}$$-edge XANES analysis showed that higher U oxidation states of +5 or +6 formed, in addition to + 4. The EXAFS analysis indicated that the interatomic distances of U-O and Gd-O decreased with increasing x, whereas those of Er-O may not decrease monotonically.

Journal Articles

Phase study and thermal expansion of yttria stabilized zirconia doped with PuO$$_{2-x}$$

Yamashita, Toshiyuki; Yamazaki, Satoshi*; Sato, Tsuyoshi*; Matsui, Tsuneo*

Journal of Nuclear Science and Technology, 39(Suppl.3), p.656 - 659, 2002/11

no abstracts in English

Journal Articles

X-ray diffraction and $$^{151}$$Eu-M$"o$ssbauer spectroscopic study of the Hf$$_{1-x}$$Eu$$_{x}$$O($$_{2-x/2}$$)(0$$leq$$x$$leq$$1.0) system

Harada, Daijitsu*; Hinatsu, Yukio*; Masaki, Nobuyuki; Nakamura, Akio

Journal of the American Ceramic Society, 85(3), p.647 - 652, 2002/03

no abstracts in English

JAEA Reports

None

Yamanaka, Shinsuke*; Uno, Masayoshi*; Kurosaki, Ken*; ; Namekawa, Takashi

JNC TY9400 2000-011, 41 Pages, 2000/03

JNC-TY9400-2000-011.pdf:1.28MB

no abstracts in English

JAEA Reports

Development of optimized advanced austenic steels (II); Evaluation of out-of-pile testing results of the fabricated fuel claddings

Uwaba, Tomoyuki; Mizuta, Shunji;

JNC TN9400 2000-028, 41 Pages, 2000/03

JNC-TN9400-2000-028.pdf:2.52MB

14Cr-25Ni optimized advanced austenic steels have been developed to improve the swelling resistance of 15Cr-20Ni austenic stainless steels used for FBR fuel cladding. ln this improvement, Ti,Nb,V and P were dissolved into 14Cr-25Ni marix by means of the high-temperature solution treatment to make finely distributed and stabilized precipitates in the operation. Furthermore, at the final stage of cold-working, cold-working level increased and residual stress was reduced. ln this study, as fablicated microstructure observation, solubility of alloying elements and grain size test in the manufacturing process were evaluated. Following results were obtained. (1)Spherical precipitates were observed in the grain. Most of them were identified as conjugated carbo-nitride [Ti,Nb(C,N)] by EDX analysis. (2)The dissolved percentages of Ti and Ni in the matrix were about 70% and 30% respectively. Undissoved Ti and Nb may react with undissolved carbon and precipitate as MC carbides. (3)High-temperature solution treatment is effective for the sufficient solubility of alloying elements, but it is likely to induce very large grains, which is the cause of defective signal in the ultrasonic alloy testing. The results of the grain size test showed that the large grain size is reduced in low Nb (0.1wt%) alloy compared with the standard alloy (0.2wt%Nb), and the effectiveness for the grain size control by reducing the Nb content was confirmed. Also, it was suggested that the intermediate heat treatment and cold work conditions would possibly avoid the occurrence of the large grain at the final heat treatment.

Journal Articles

$$^{151}$$Eu-M$"o$ssbauer spectroscopic study of the fluorite-type oxide solid solutions, Eu$$_{y}$$M$$_{1-y}$$O$$_{2-y/2}$$ (M=Zr,Ce)(0$$leq$$y$$leq$$1.0)

Masaki, Nobuyuki; Guillermo, N. R. D.; Otobe, Haruyoshi; Nakamura, Akio; Izumiyama, Yuki*; Hinatsu, Yukio*

Advances in Science and Technology, 29, p.1233 - 1240, 2000/00

no abstracts in English

Journal Articles

Thermal conductivity of actinide mononitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa; Suzuki, Yasufumi

Journal of Alloys and Compounds, 271-273, p.602 - 605, 1998/00

 Times Cited Count:16 Percentile:68.02(Chemistry, Physical)

no abstracts in English

Journal Articles

Crystal chemistry and microstructures of uranyl phosphates

*; Murakami, Takashi*; Kogure, Toshihiro*; Isobe, Hiroshi; Sato, Tsutomu

Mat. Res. Soc. Symp. Proc., 506, p.839 - 846, 1998/00

no abstracts in English

Journal Articles

Thermodynamic study of U$$_{1-y}$$Gd$$_{y}$$O$$_{2+x}$$ by solid state EMF measurements

Nakamura, Akio

Zeitschrift f$"u$r Physikalische Chemie, 207, p.223 - 243, 1998/00

no abstracts in English

Journal Articles

Thermal expansion of neptunium-uranium mixed oxides

Yamashita, Toshiyuki; Shirasu, Noriko; Tsuji, Toshihide*; Kato, Tetsuya*

Journal of Nuclear Materials, 247, p.90 - 93, 1997/00

 Times Cited Count:51 Percentile:94.73(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Properties of neptunium-plutonium mixed nitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa;

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.347 - 357, 1997/00

no abstracts in English

Journal Articles

Recent progress of nitride fuel development in JAERI; Fuel property, irradiation behavior and application to dry reprocessing

Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa; Suzuki, Yasufumi

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.664 - 669, 1997/00

no abstracts in English

JAEA Reports

None

*

PNC TJ1211 95-003, 38 Pages, 1995/02

PNC-TJ1211-95-003.pdf:0.95MB

None

Journal Articles

Equilibrium hydrogen pressure on the solid solutions of ZrCo-HfCo intermetallic compounds

Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji

Journal of Nuclear Materials, 223, p.300 - 304, 1995/00

 Times Cited Count:22 Percentile:87.04(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Improvements in ZrCo based tritium storage media

Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji

Fusion Technology, 26(3), p.668 - 672, 1994/11

no abstracts in English

Journal Articles

Literature review; Heterogeneity of smectite: Monomineralic solid-solutions or multiphase mixtures?

Sato, Tsutomu

SMECTITE, 4(1), p.48 - 51, 1994/05

no abstracts in English

JAEA Reports

None

*

PNC TJ1211 94-005, 55 Pages, 1994/02

PNC-TJ1211-94-005.pdf:1.11MB

None

Journal Articles

Magnetic properties of uranium complex oxides

Hinatsu, Yukio

Nihon Genshiryoku Gakkai-Shi, 36(8), p.714 - 726, 1994/00

 Times Cited Count:1 Percentile:17.88(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

*

PNC TJ1211 93-010, 56 Pages, 1993/02

PNC-TJ1211-93-010.pdf:0.93MB

None

55 (Records 1-20 displayed on this page)