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Journal Articles

Solubility of FeSe$$_{2}$$(cr) at 318 K in the presence of iron

Yoshida, Yasushi*; Kitamura, Akira; Shibutani, Sanae*

Journal of Nuclear Science and Technology, 60(8), p.900 - 910, 2023/08

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH

Ishidera, Takamitsu; Okazaki, Mitsuhiro*; Yamada, Yoshihide*; Tomura, Tsutomu*; Shibutani, Sanae*

Journal of Nuclear Science and Technology, 60(5), p.536 - 546, 2023/05

The distribution coefficient (${it K$_{d}$}$) value of radionuclides is an important parameter in the radionuclide migration analysis in the safety assessment of the geological disposal of high-level radioactive waste. The ${it K$_{d}$}$ values must be extensively evaluated especially under conditions where they might be decreased to improve the reliability of safety assessment. In this study, the pH dependence of the ${it K$_{d}$}$ values for Sn and Nb on montmorillonite was evaluated using batch sorption experiments at neutral to alkaline pH, which might be caused by the leaching of cementitious materials and the corrosion of carbon steel. The ${it K$_{d}$}$ values were determined in the range 8 $$<$$ pH $$<$$ 12 by the experiments and were found to decrease with increasing pH. A model calculation using a thermodynamic sorption model was conducted on the measured pH dependence of the ${it K$_{d}$}$ values. Two different sorption sites were required to describe the pH dependence of the ${it K$_{d}$}$ values of Sn in the model calculation, whereas one sorption site was considered predominant in the sorption of Nb.

Journal Articles

Methodology development and determination of solubility-limiting solid phases for a performance assessment of geological disposal of high-level radioactive and TRU wastes

Kitamura, Akira; Yoshida, Yasushi*; Goto, Takahiro*; Shibutani, Sanae*

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 27(2), p.58 - 71, 2020/12

Evaluation and estimation of solubility values are required for a performance assessment of geological disposal of high-level radioactive and TRU wastes. Selection of solubility-limiting solid phases (SSPs) that control the solubility of radionuclides is necessary for the evaluation and estimation of solubility values. The authors have developed a methodology for selection of the SSP through a calculation of saturation indices (SIs) using thermodynamic database to show a transparent procedure for the selection. Literature survey should be performed to confirm decision of the SSP from candidate SSPs which generally have larger SIs from realistic point of view for precipitation and solubility control. The authors have selected the SSPs for the elements of interest for the latest Japanese performance assessment in bentonite and cement porewaters after grouping various water compositions.

Journal Articles

A Systematic radionuclide migration parameter setting approach for potential siting environments in Japan

Hamamoto, Takafumi*; Ishida, Keisuke*; Shibutani, Sanae*; Fujisaki, Kiyoshi*; Tachi, Yukio; Ishiguro, Katsuhiko*; McKinley, I. G.*

Proceedings of 2019 International High-Level Radioactive Waste Management Conference (IHLRWM 2019) (USB Flash Drive), p.77 - 82, 2019/04

JAEA Reports

Investigation and evaluation of sorption and diffusion data for sedimentary rocks and cementitious materials (Report on NUMO-JAEA collaborative research in FY2016-2017) (Joint research)

Hamamoto, Takafumi*; Matsubara, Ryuta*; Shibutani, Sanae*; Suyama, Tadahiro*; Tachi, Yukio

JAEA-Data/Code 2017-014, 31 Pages, 2018/03

JAEA-Data-Code-2017-014.pdf:2.1MB
JAEA-Data-Code-2017-014-appendix(CD-ROM).zip:0.61MB

NUMO and JAEA have developed the methodology of post-closure safety assessment for the geological disposal. For this purpose, NUMO and JAEA have conducted a collaborative research project for developing the safety assessment methodology based on international state of the art knowledge. The present report focuses on investigation of sorption and diffusion data reported and their QA evaluation for updating sorption and diffusion database (SDB and DDB) as the collaborative research project between NUMO and JAEA. This report includes sorption and diffusion data for mainly sedimentary rocks and cement materials. As a result, 1,746 sorption data from 19 references and 593 diffusion data from 25 references were extracted and prepared in the datasheet of SDB and DDB.

Journal Articles

K$$_{rm d}$$ setting approaches for rocks for the performance assessment of geological disposal; Application for granitic rocks

Tachi, Yukio; Suyama, Tadahiro*; Shibutani, Sanae*

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(2), p.109 - 133, 2017/12

For performance assessment (PA), the distribution coefficient (K$$_{rm d}$$) need to be determined taking into account the specific PA conditions, including geochemical variability or uncertainty. The K$$_{rm d}$$ setting approach for rocks was developed by integrating three methods; (i) direct use of measured K$$_{rm d}$$ data extracted from the sorption database, (ii) semi-quantitative estimation by scaling differences between experimental and PA conditions, and (iii) thermodynamic sorption models. This approach was tested for granitic rock by comparing K$$_{rm d}$$ values and their uncertainties of Cs and Am. The results indicated that K$$_{rm d}$$ can be quantitatively evaluated by all approaches when adequate data and models are available. The K$$_{rm d}$$ dataset for safety-relevant 25 radionuclides was developed based on the direct use of measured data, and compared with the recent K$$_{rm d}$$ dataset in European PA projects. This K$$_{rm d}$$ setting approaches allowed to estimate the K$$_{rm d}$$ values and their uncertainties under the expected site conditions.

Journal Articles

Assessment of sorption and diffusion in the rock matrix in the NUMO safety case

Hamamoto, Takafumi*; Shibutani, Sanae*; Ishida, Keisuke*; Fujisaki, Kiyoshi*; Yamada, Motoyuki*; Tachi, Yukio

Proceedings of 6th East Asia Forum on Radwaste Management Conference (EAFORM 2017) (Internet), 6 Pages, 2017/12

NUMO has developed a generic safety case to demonstrate the feasibility and safety of geological disposal of HLW and TRU in Japan and to provide a basic structure for the safety case which will be applicable to any potential site. In this safety case, the safety assessment was carried out for the repositories tailored to site descriptive models developed for three representative rock groups (plutonic, Neogene sedimentary and Pre-Neogene sedimentary rocks). Radionuclide migration parameters in rocks, i.e. distribution coefficients (Kds) and effective diffusion coefficients (Des), were derived to allow safety analysis for a range of scenarios. In this generic stage, the values of these parameter were given as the statistical values derived from laboratory data for certain rock types. The data were extracted from the latest database, with interpretation based on radionuclide speciation derived from relevant groundwater thermodynamic modelings.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 3; Progress report on NUMO-JAEA collaborative research in FY2013 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Kitamura, Akira; Yoshikawa, Hideki; Oda, Chie; Ishidera, Takamitsu; et al.

JAEA-Research 2014-030, 457 Pages, 2015/03

JAEA-Research-2014-030.pdf:199.23MB

JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and post-closure performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, based on some examples of developing method of hydro-geological structure model, acquired knowledge are arranged using the tree diagram, and model uncertainty and its influence on the evaluation items were discussed. With regard to (2) study on scenario development, the developed approach for "defining conditions" has been reevaluated and improved from practical viewpoints. In addition, the uncertainty evaluation for the effect of use of cementitious material, as well as glass dissolution model, was conducted with analytical evaluation. With regard to (3) study on setting radionuclide migration parameters, based on survey of precedent procedures, multiple-approach for distribution coefficient of rocks was established, and the adequacy of the approach was confirmed though its application to sedimentary rock and granitic rock. Besides, an approach for solubility setting was developed including the procedure of selection of solubility limiting solid phase. The adequacy of the approach was confirmed though its application to key radionuclides.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 2; Progress report on NUMO-JAEA collaborative research in FY2012 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Hayano, Akira; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.

JAEA-Research 2013-037, 455 Pages, 2013/12

JAEA-Research-2013-037.pdf:42.0MB

Following FY2011, JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, the tree diagram of methodology of groundwater travel time has been extended for crystalline rock, in addition, tree diagram for sedimentary rock newly has been organized. With regard to (2) study on scenario development, the existing approach has been improved in terms of a practical task, and applied and tested for near field focusing on the buffer. In addition, the uncertainty of some important processes and its impact on safety functions are discussed though analysis. With regard to (3) study on setting radionuclide migration parameters, the approaches for parameter setting have been developed for sorption for rocks and solubility, and applied and tested through parameter setting exercises for key radionuclides.

JAEA Reports

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes; Selection of thermodynamic data of molybdenum

Kitamura, Akira; Kirishima, Akira*; Saito, Takumi*; Shibutani, Sanae*; Tochiyama, Osamu*

JAEA-Review 2010-010, 75 Pages, 2010/06

JAEA-Review-2010-010.pdf:1.27MB

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of molybdenum were carried out. We focused to select thermodynamic data of aquous species and compounds which could form under repository conditions for the disposal of radioactive wastes, i.e. relatively low concentration of molybdenum and from near neutral through alkaline conditions. Selection of thermodynamic data was based on the guidelines by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Extensive literature survey was performed and all the obtained articles have been carefully reviewed to select the thermodynamic data for molybdenum. Thermodynamic data at 25 $$^{circ}$$C and zero ionic strength were determined from accepted thermodynamic data which were considered to be reliable. We especially paid attention to select formation constant of molybdate ion with hydrogen ion.

JAEA Reports

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes; Selection of thermodynamic data on cobalt and nickel

Kitamura, Akira; Kirishima, Akira*; Saito, Takumi*; Shibutani, Sanae*; Tochiyama, Osamu*; Yui, Mikazu

JAEA-Research 2009-037, 91 Pages, 2009/11

JAEA-Research-2009-037.pdf:4.04MB

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU radioactive wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of cobalt and nickel have been carried out. For cobalt, extensive literature survey has been performed and all the obtained literatures have been carefully reviewed to select the thermodynamic data. Selection of thermodynamic data of nickel has been based on a thermodynamic database published by the OECD/NEA, which has been carefully reviewed by the authors, and then thermodynamic data have been selected after surveying latest literatures. Based on the similarity of chemical properties between cobalt and nickel, complementary thermodynamic data of nickel and cobalt species expected under the geological disposal condition have been selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes.

JAEA Reports

Database development of chemical thermodynamics of plutonium for performance assessment of HLW geological disposal system

Shibutani, Tomoki; Shibutani, Sanae

PNC TN8410 98-082, 97 Pages, 1998/06

PNC-TN8410-98-082.pdf:2.76MB

In the performance assessment of geological disposal system of high-evel radioactive waste(HLW), solubility and speciation of radioactive elements are important to estimate their migration behavior from vitrified HLW in engineered and natural barrier system. The solubility and speciation of radioactive elements are calculated by using thermodynamic data and geochemical code, so development of reliable thermodynamic data base is important to built confidence for performance assessment. In this report, reaction constants of plutonium oxidation/reduction, hydrolysis, complexation for carbonate, sulphate, phosphate, nitrate, fluoride and chloride are discussed and selected. For the development of the PNC-TDB, existing literature data were surveyed and realistic thermodynamic data were selected under consideration of chemical properties, chemical analogy of other actinide element and the internal consistency with the hole PNC-TDB. Solubilities of plutonium were studied by several researchers, and these measurement have been compared with geochemical calculation for validation of the PNC-TDB. Calculated results shows that the experimental results can be interpreted by geochemical calculation by using the PNC-TDB.

JAEA Reports

Database Development of Chemical Thermodynamics of Protactinium for Performance Assessment of HLW Geological Disposal System

Shibutani, Tomoki; Shibutani, Sanae; Yui, Mikazu

PNC TN8410 98-052, 18 Pages, 1998/03

PNC-TN8410-98-052.pdf:0.86MB

In the performance analysis of geological disposal system of high-level radioactive waste (HLW), solubilities of radioactive elements are estimated by thermodynamic calculation. The reliable thermodynamic database (TDB) is needed for solubility estimation. In this report, thermodynamic data for protactinium solid and aqueous species for performance assessment were selected. For the refinement of previous PNC in house thermodynamic database (PNC-TDB), existing literatures data were surveyed and reliable thermodynamic data were selected under consideration of the scientific defensibility and the consistency with the whole PNC-TDB. The estimated solubility using refined PNC-TDB was higher than measured value. We have confirmed the refined data-set of Pa to be conservative for solubility estimation of performance assessment.

Journal Articles

None

Shibutani, Sanae; Yui, Mikazu

P.57-66, (105), p.57 - 66, 1998/03

None

JAEA Reports

None

Shibutani, Sanae; Ueta, Shinzo*; Yui, Mikazu

PNC TN8410 98-035, 40 Pages, 1998/02

PNC-TN8410-98-035.pdf:1.28MB

None

Journal Articles

Solubility measurements of Sm and Nd in hydroxide and carbonate system

Shibutani, Sanae; ; Yui, Mikazu

Proceedings of Migration '97, 0 Pages, 1997/00

None

Journal Articles

Solubility measurements of Zr and Ni in bentonite-water system

Shibutani, Sanae; Yui, Mikazu

Proceedings of Migration '97, 0 Pages, 1997/00

None

JAEA Reports

None

Shibutani, Sanae; Yui, Mikazu

PNC TN8100 96-008, 376 Pages, 1996/07

PNC-TN8100-96-008.pdf:25.0MB

no abstracts in English

30 (Records 1-20 displayed on this page)