XAFS measurement of simulated waste glass samples (Borosilicate glass including vanadium)

Nagai, Takayuki; Kobayashi, Hidekazu; Sasage, Kenichi; Ayame, Yasuo; Okamoto, Yoshihiro; Shiwaku, Hideaki; Matsuura, Haruaki*; Uchiyama, Takafumi*; Okada, Yukiko*; Nezu, Atsushi*; et al.

JAEA-Research 2016-015, 52 Pages, 2016/11

JAEA-Research-2016-015.pdf:37.48MB

The local structure of waste elements in simulated waste glasses including V was estimated by using synchrotron XAFS measurement in this study. The results are as follows. (1) V has a high possibility which exists in the glass phase in the case of frit, and V can regard both samples as stable 4 coordination structure. (2) Zn, Ce, Nd, Zr, and Mo exist in the glass phase, and the difference is admitted by the percentage of Ce(III) and Ce(IV) by the composition. (3) Ru is separated from the glass phase as RuO crystalline, both of metal and oxide exist in Rh, and Pd is separated out as metal. (4) It was confirmed that the regularity of the local structure of Zr and Mo in the molten glasses retreats as a result of the XAFS measurement at high temperature. (5) The XAFS measurement of molten glasses were performed at 1200C, so it would be possible to acquire excellent data by improving the shapes of the sample cell.

An Investigation into dissolution rate of spent nuclear fuel in aqueous reprocessing

Mineo, Hideaki; Isogai, Hikaru; Morita, Yasuji; Uchiyama, Gunzo*

Journal of Nuclear Science and Technology, 41(2), p.126 - 134, 2004/02

https://doi.org/10.3327/jnst.41.126

A simple equation was proposed for the dissolution rate of spent LWR fuel, of which the change in the dissolution area was estimated by taking into account of the area of the cracks occurring due to thermal shrinkage of the pellets during irradiation. The applicability of proposed equation was examined using LWR fuel dissolution test results in the present study as well as the results obtained by other workers. The equation showed good agreements with the dissolution test results obtained from spent fuel pellets and pulverized spent fuel. It was indicated that the proposed equation was simple and would be useful for the prediction of dissolution of spent LWR fuels. However, the initial effective dissolution area, the parameter of the equation, was found to depend on the temperature, which could not be explained by the proposed equation. Further studies on the role of other factors affecting dissolution rate, such as nitrous acid, in the dissolution of spent fuel was required.

Long-lived nuclide separation for advancing back-end fuel cycle process

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Iizuka, Masaru*; Fujisaki, Susumu; Isogai, Hikaru; Ito, Yoshinori*; Sato, Makoto; Hosoya, Noriaki

Journal of Nuclear Science and Technology, 39(Suppl.3), p.925 - 928, 2002/11

http://www.tandfonline.com/doi/abs/10.1080/00223131.2002.10875620

no abstracts in English

A Simple model predicting iodine profile in a packed bed of silica-gel impregnated with silver nitrate

Mineo, Hideaki; Goto, Minoru; Iizuka, Masaru*; Fujisaki, Susumu; Uchiyama, Gunzo

Journal of Nuclear Science and Technology, 39(3), p.241 - 247, 2002/03

https://doi.org/10.3327/jnst.39.241

no abstracts in English

Study on gaseous effluent treatment for dissolution step of spent nuclear fuel reprocessing

Mineo, Hideaki; Iizuka, Masaru*; Fujisaki, Susumu; Hotoku, Shinobu; Asakura, Toshihide; Uchiyama, Gunzo

Proceeding of International Waste Management Symposium 2002 (WM '02) (CD-ROM), 9 Pages, 2002/00

no abstracts in English

The Washing tests of degraded solvent by butylamine compounds

Kamei, Kazushige; Ito, Yoshinori*; Hotoku, Shinobu; Asakura, Toshihide; Watanabe, Makio; Mineo, Hideaki; Uchiyama, Gunzo

JAERI-Research 2001-026, 27 Pages, 2001/03

JAERI-Research-2001-026.pdf:1.18MB

no abstracts in English

PARC process for an advanced PUREX process

Uchiyama, Gunzo; Mineo, Hideaki; Hotoku, Shinobu; Asakura, Toshihide; Kamei, Kazushige; Watanabe, Makio; Nakano, Yuji*; Kimura, Shigeru; Fujine, Sachio

Progress in Nuclear Energy, 37(1-4), p.151 - 156, 2000/12

https://doi.org/10.1016/S0149-1970(00)00040-8

no abstracts in English

Management of minor long-lived nuclides in nuclear fuel reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.531 - 538, 2000/00

no abstracts in English

Dissolution tests of spent fuel in the NUCEF cell including dissolver off-gas treatment

Mineo, Hideaki; Kihara, Takehiro; ; Kimura, Shigeru; ; ; Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; ; et al.

JAERI-Conf 99-004, p.498 - 507, 1999/03

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-99-004-Part1.pdf

no abstracts in English

Development of treatment technology for carbon-14 in dissolver off-gas of spent fuel

Mineo, Hideaki; ; ; Uchiyama, Gunzo; Fujine, Sachio

Proc. of 7th Int. Conf. on Radioactive Waste Mamagement and Environmental Remediation (ICEM '99)(CD-ROM), 3 Pages, 1999/00

no abstracts in English