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Journal Articles

Studies of the setting of engineered barrier configuration utilized in geologic disposal, 1; Dissolution life-time of vitrified waste glass

Oe, Toshiaki*; Wakasugi, Keiichiro

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(1), p.27 - 32, 2017/06

The report estimates the life-time of the waste glass dissolution in the geologic disposal environment. The overall safety report on the geologic disposal in Japan showed very short life-time of approximately 70,000 years under pessimistic assumptions ignoring the temperature decrease due to radioactive decay and dissolution rate reduction due to surface shrinkage. These factors are physically established phenomena and may not be excluded. The dissolution models including these factors of temperature and surface area decreases are discussed and used for re-evaluation. Three fracture models are presented for evaluating the surface area decreases; a single plate, monotonic spheres, spheres having power-law distribution. All models have the same initial volume as the waste glass block for mass conservation and the total surface areas are 10 times higher than the initial pristine block because of the fracture development during production. The results indicate the retention time of 50% of initial mass exceed 100,000 years even by different fracture models and the dissolution life-times are expected for 260,000$$sim$$700,000 years depending on models. These results imply more strong isolation capability of the waste glass than that estimated in the overall safety report.

Journal Articles

Burning of MOX fuels in LWRs; Fuel history effects on thermal properties of hull and end piece wastes and the repository performance

Hirano, Fumio; Sato, Seichi*; Kozaki, Tamotsu*; Inagaki, Yaohiro*; Iwasaki, Tomohiko*; Oe, Toshiaki*; Kato, Kazuyuki*; Kitayama, Kazumi*; Nagasaki, Shinya*; Niibori, Yuichi*

Journal of Nuclear Science and Technology, 49(3), p.310 - 319, 2012/03

AA2011-0278.pdf:0.56MB

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

The thermal impacts of hull and end piece wastes from the reprocessing of MOX spent fuels burned in LWRs on repository performance were investigated. The heat generation rates in MOX spent fuels and the resulting heat generation rates in hull and end piece wastes change depending on the fuel histories including the burn-up of UO$$_{2}$$ spent fuels, the cooling period before reprocessing, the storage period of fresh MOX fuels. The heat generation rates of hull and end piece wastes from the reprocessing of MOX spent fuels with any of those histories are significantly larger than those from UO$$_{2}$$ spent fuels with burn-ups of 45 GWd/THM. If a temperature below 80$$^{circ}$$C is specified for cement-based materials used in waste packages after disposal, the allowable number of canisters containing compacted hull and end pieces in a package for 45 GWd-MOX needs to be limited to a value of 0.7 to 1.6, which is significantly lower than the value of 4.0 for 45 GWd-UO$$_{2}$$.

JAEA Reports

Announced document collection of the 1st Information Exchange Meeting on Radioactive Waste Disposal Research Network (Joint research)

Nakayama, Shinichi; Nagasaki, Shinya*; Inagaki, Yaohiro*; Oe, Toshiaki*; Sasaki, Takayuki*; Sato, Seichi*; Sato, Tsutomu*; Tanaka, Satoru*; Tochiyama, Osamu*; Nagao, Seiya*; et al.

JAEA-Conf 2007-003, 120 Pages, 2007/03

JAEA-Conf-2007-003.pdf:53.18MB

The 1st information exchange meeting on Radioactive Waste Disposal Research Network was held in Nuclear Science Research Institute of Japan Atomic Energy Agency on August 4, 2006. Radioactive Waste Disposal Research Network was established by under Interorganization Atomic Energy Research Program of Japan Atomic Energy Agency, and the objective is to bring both research infrastructures and human expertise in Japan to an adequate performance level, thereby contributing to the development of the fundamental research area in the field of radioactive waste disposal. This lecture material is a collection of research presentations and discussions during the information exchange meeting.

Journal Articles

6th International Conference on Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere (Migration '97)

Oe, Toshiaki*; Yamaguchi, Tetsuji

Nippon Genshiryoku Gakkai-Shi, 40(1), p.47 - 49, 1998/01

no abstracts in English

Journal Articles

Mass yield curves in low-energy proton-induced fission of $$^{233}$$U, $$^{235}$$U, $$^{236}$$U, $$^{237}$$Np, $$^{239}$$Pu, $$^{242}$$Pu, $$^{244}$$Pu, $$^{241}$$Am and $$^{243}$$Am

Otsuki, Tsutomu*; Nagame, Yuichiro; Tsukada, Kazuaki*; Shinohara, Nobuo; *; Hashimoto, Kazuyuki; *; Sueki, Keisuke*; ; ; et al.

Physical Review C, 44(4), p.1405 - 1423, 1991/10

 Times Cited Count:34 Percentile:13.78(Physics, Nuclear)

no abstracts in English

Journal Articles

Symmetric mass division process in the reactions $$^{37}$$Cl + $$^{68}$$Zn and $$^{16}$$O + $$^{89}$$Y

Nagame, Yuichiro; Ikezoe, Hiroshi; Otsuki, Tsutomu*; Yokoyama, Akihiko*; ; *; ; Sekine, Toshiaki; Ideno, K.

Physics Letters B, 249(1), p.13 - 17, 1990/10

 Times Cited Count:3 Percentile:72.7(Astronomy & Astrophysics)

no abstracts in English

JAEA Reports

Cost Estimation for the Geological Disposal System of High Level Radioactive Waste (for 1989); The Improvement of Cost Integration System

Yoshiki, Nobuya*; Oe, Toshiaki*; Tsukamoto, Masaki*; Tanaka, Hiroshi*

JNC-TJ1400 2005-003, 149 Pages, 1990/03

JNC-TJ1400-2005-003.pdf:4.97MB

None

Journal Articles

Statistical emission of complex fragments produced in the reaction $$^{37}$$Cl + $$^{68}$$Zn

Nagame, Yuichiro; Ikezoe, Hiroshi; *; ; Sekine, Toshiaki; ; *; Ideno, K.; Yokoyama, Akihiko*; ; et al.

Nuclear Physics A, 510, p.518 - 532, 1990/00

no abstracts in English

Journal Articles

Symmetric and asymmetric mass divisions of the compound nucleus $$^{105}$$Ag

Nagame, Yuichiro; Ikezoe, Hiroshi; ; ; Sekine, Toshiaki; ; Ideno, K.; Yokoyama, Akihiko*; *; Otsuki, Tsutomu*

Heavy-Ion Reaction Dynamics in Tandem Energy Region, p.265 - 274, 1988/00

no abstracts in English

Oral presentation

A Study of evaluation of influence of long term topographic perturbations on groundwater flow conditions

Saegusa, Hiromitsu; Onoe, Hironori; Kinoshita, Hirohisa*; Sasao, Eiji; Kosaka, Hiroshi*; Tokusu, Mitsuhiro*; Yoden, Toshiaki*

no journal, , 

no abstracts in English

Oral presentation

Development of database for long-term safety assessment of radioactive waste disposal

Sekioka, Yasushi; Takeda, Seiji; Kimura, Hideo; Yamaguchi, Tetsuji; Oe, Toshiaki*; Nagasaki, Shinya*; Sasaki, Takayuki*; Kozaki, Tamotsu*; Inagaki, Yaohiro*

no journal, , 

no abstracts in English

Oral presentation

Analysis of data perturbation found in the sorption database; Explanation by adopting mechanistic sorption models

Oe, Toshiaki*; Nagasaki, Shinya*; Kimura, Hideo; Takeda, Seiji; Sekioka, Yasushi; Kato, Hiroyasu*; Akahori, Kuniaki*

no journal, , 

no abstracts in English

Oral presentation

Development of micro-chemical probe for geological environment diagnosis, 15; Application of micro-chemical probe to Mizunami Undergoround Research Laboratory Project

Uchida, Masahiro; Amano, Kenji; Hama, Katsuhiro; Takeuchi, Ryuji; Yoshida, Takuma*; Noshita, Kenji*; Futakuchi, Katsuhito*; Oe, Toshiaki*; Nagasaki, Shinya*

no journal, , 

no abstracts in English

Oral presentation

Moderation of uncertainty in a database of sorption coefficients; Analysis of Np(V) data by adopting surface complexation model

Oe, Toshiaki*; Nagasaki, Shinya*; Kimura, Hideo; Takeda, Seiji; Sekioka, Yasushi; Kato, Hiroyasu*

no journal, , 

no abstracts in English

Oral presentation

Development of micro-chemical probe for characterization of geological environment

Hama, Katsuhiro; Uchida, Masahiro; Amano, Kenji; Takeuchi, Ryuji; Hagiwara, Hiroki; Yoshida, Takuma*; Noshita, Kenji*; Nagasaki, Shinya*; Oe, Toshiaki*; Futakuchi, Katsuhito*

no journal, , 

The micro-chemical probe for characterization of geological environment has been developed. The performance test shows that this equipment can be applicable for the in-situ experiment.

Oral presentation

Physico-chemical properties of pore water in compacted bentonite; Pore water condition measured by osmotic pressure

Oe, Toshiaki*; Suzuki, Masashi*; Tachi, Yukio; Kato, Hiroyasu*

no journal, , 

Physico-chemical properties of pore water in water saturated compacted bentonite was investigated by the osmotic pressure measurement. Osmotic pressure reached the peak value at dry density of 1.2 g/cm$$^{3}$$, implying that physico-chemical properties change drastically at this desity.

Oral presentation

Solvent extraction of heavy actinides (III) with HDEHP

Takayama, Reona*; Oe, Kazuhiro*; Komori, Yukiko*; Fujisawa, Hiroyuki*; Kuriyama, Ai*; Kikutani, Yuki*; Kikunaga, Hidetoshi*; Kasamatsu, Yoshitaka*; Yoshimura, Takashi*; Takahashi, Naruto*; et al.

no journal, , 

The extraction behavior of trivalent actinides (Am, Cm, Cf, Es, and Fm) into di(2-ethylhexyl)phosphoric acid, HDEHP, in benzene from HNO$$_{3}$$ was studied together with lanthanides. The extraction constants, $$it K$$$$_{ex}$$ values, of lanthanides, Am, Cm, Cf, and Es were determined by a batch method using stable lanthanide isotopes and radiotracers of $$^{241}$$Am, $$^{243}$$Cm, $$^{249}$$Cf, and $$^{253}$$Es, respectively, while that of Fm was measured with $$^{250}$$Fm which was produced in the $$^{238}$$U($$^{16}$$O,4n) reaction and was on-line supplied by a gas-jet method at the AVF cyclotron of RCNP, Osaka University. The $$it K$$$$_{ex}$$ values were determined by the slope analysis for the variation of the distribution ratio as a function of the concentration of HDEHP. We found that the $$it K$$$$_{ex}$$of Fm is smaller than that of Dy in spite of the similar ionic radii while those of other actinides are almost the same as those of each lanthanide with a similar ionic radius.

Oral presentation

Preparation of an information basis for development of practical performance assessment models on waste glass corrosion in geological disposal

Mitsui, Seiichiro; Oe, Toshiaki*; Inagaki, Yaohiro*; Okubo, Takahiro*; Kurosawa, Susumu*; Goto, Takahiro*; Inagaki, Manabu*; Ishiguro, Katsuhiko*; Takase, Hiroyasu*; Takahashi, Hirokazu*

no journal, , 

In order to develop robust performance assessment models, we have been preparing an information basis regarding glass properties and glass dissolution/alteration processes under disposal conditions as a part of NUMO-JAEA joint project. Our iterative working process for the preparation of the information basis comprises five steps: (1) integration of current knowledge; (2) development of glass dissolution scenarios based on current knowledge; (3) development of conceptual model; (4) sensitivity analyses to evaluate relative importance of relevant processes and associated uncertainties; and (5) identification of future R&D issues towards further improvement of the information basis. The current status will be presented in this talk.

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