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Journal Articles

Neutron scattering on an aqueous sodium chloride solution in the gigapascal pressure range

Yamaguchi, Toshio*; Yoshida, Koji*; Machida, Shinichi*; Hattori, Takanori

Journal of Molecular Liquids, 365, p.120181_1 - 120181_10, 2022/11

 Times Cited Count:0 Percentile:0.01(Chemistry, Physical)

Neutron scattering measurements were performed on an aqueous 3 mol/kg NaCl solution in D$$_2$$O at temperature and pressure conditions of 0.1 MPa/298K, 1 GPa/298K, 1 GPa/523K, and 4 GPa/523K. The empirical potential structure refinement method was applied to the obtained data to extract the pair correlation function, coordination number distribution, angular distribution (orientation correlation), and spatial density function (3-D structure). From those results, pressure and temperature dependence of solvation and association of ions and solvent-water structure were discussed.

Oral presentation

Surface alteration of simulated nuclear fuel debris containing Fe, Cr, and Ni in water; A Raman and M$"o$ssbauer spectroscopic study

Kumagai, Yuta; Kusaka, Ryoji; Nakada, Masami; Watanabe, Masayuki; Kirishima, Akira*; Akiyama, Daisuke*; Sato, Nobuaki*; Sasaki, Takayuki*

no journal, , 

Oral presentation

Leaching behavior of simulated fuel debris in the UO$$_{2}$$-SUS system prepared by irradiation or tracer doping method

Sasaki, Takayuki*; Tonna, Ryutaro*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki

no journal, , 

Oral presentation

Basic research on the chemical stability of nuclear fuel debris including alloy phase

Kirishima, Akira*; Akiyama, Daisuke*; Sato, Nobuaki*; Sasaki, Takayuki*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki

no journal, , 

Oral presentation

Oral presentation

Evaluation of strontium penetration behavior in concrete structural materials

Kimoto, Yuko*; Yoneyama, Kai*; Sato, Isamu*; Matsuura, Haruaki*; Suzuki, Eriko; Miwa, Shuhei

no journal, , 

In order to clarify Sr penetration behavior into concrete, the concentration and coordination structure of Sr penetrated in concrete from SrCl$$_{2}$$ and Sr(OH)$$_{2}$$ solution were analyzed using XRF and EXAFS. It was revealed by XRF results that significant amounts of Sr penetrated into concrete from both of SrCl$$_{2}$$ and Sr(OH)$$_{2}$$ solution and the penetration rate of SrCl$$_{2}$$ solution is larger than that of Sr(OH)$$_{2}$$. Further, EXAFS results showed that the Sr penetrated from SrCl$$_{2}$$ solution is not coordinated by Cl, but rather O, which is close to the nearest neighbor distance of the Sr-O structure.

Oral presentation

Radiation effects on retention property of high-viscous suspension of co-precipitates in nuclear chemical separation

Nagaishi, Ryuji; Kuwano, Ryo*; Ito, Tatsuya

no journal, , 

Coagulating sedimentation has been practically used for radioactive multi-nuclide removal in Fukushima Daiichi NPS, emitting radioactive wastes of high-viscous suspension of co-precipitates. The suspension of carbonate slurry has been found out to retain hydrogen molecules (H$$_{2}$$) formed in water radiolysis in the previous studies for overflow of water from HIC. However, radiation effects on the H$$_{2}$$ retention property have not been elucidated microscopically. In this study, the physical and viscosity properties of simulated slurry were measured before and after the EB and $$gamma$$-ray irradiation, and then the radiation effects were discussed. Hydrophilic nature of magnesium hydroxide (Mg(OH)$$_{2}$$) in suspended solids (SS) is closely related to the viscosity appearance of slurry. It was estimated in a SS particle that water molecules equivalent to Mg or more were bound to Mg(OH)$$_{2}$$. In the irradiation experiments, the destruction of SS and the irreversible lowering of viscosity in the slurry were observed to repress the H$$_{2}$$ retention.

Oral presentation

Decontamination of alkali chloride baths containing nuclear material by precipitation and distillation techniques

Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*

no journal, , 

Since waste salt generated from pyro-reprocessing test which contains uranium can easily capture moisture and corrode equipment, further treatment technology for decontamination. Oxides are added as oxygen donor in the melts, and then uranium is separated from the salt as precipitates. In the next step, melt bath components are evaporated by a vacuum distillation. First, LiCl-KCl eutectic and NaCl-2CsCl salts were used as melt baths, lithium oxide was used as a precipitant, and cerium chloride was used as uranium surrogate for testing the precipitation process. Next, a distillation line has been constructed and the best condition for distillation has been searched. Amount of the precipitates increased with increasing the amount of oxide, and recovery ratio of cerium must potentially depend on solubility of oxychloride into the bath salts. It is considered that oxychloride was formed by the similarity in EXAFS oscillation and X-ray diffraction patterns.

Oral presentation

Selective uranium adsorption from liquid waste using zeolites

Matsuura, Haruaki*; Aso, Hiroki*; Toyosaki, Ayaka*; Asanuma, Noriko*; Takahatake, Yoko; Hoshino, Takanori; Watanabe, So; Watanabe, Masayuki

no journal, , 

Oral presentation

Feasible study for the production of At-211 using Liquid Bismuth Target System

Watanabe, Shigeki*; Kondo, Hiroo*; Koka, Masashi*; Takai, Toshihide; Okubo, Nariaki; Furukawa, Tomohiro; Ishioka, Noriko*

no journal, , 

Astatine-211, one of the promising alpha-emitting radionuclides for the targeted alpha therapy, is mainly produced via the $$^{209}$$Bi(alpha, 2n)$$^{211}$$At reaction. High beam current will be required to produce enough radioactivity on the order of GBq to ship to multiple hospitals for clinical applications. However, melting of target Bi induced by alpha-beam irradiation occurs and it is difficult with even low beam current due to its low melting point. We are thus developing the "Liquid Bismuth Target System" by incorporating liquid metal technologies used for such as fast reactors and fusion reactors, and we have performed alpha-beam irradiation to a prototype system as a feasible study. Produced radioactivity of $$^{211}$$At was estimated to be 367 MBq, which was identical to that estimated from produced radioactivity when using a solid Bi target under the same condition.

Oral presentation

Machine learning potentials for cement and clay minerals

Okumura, Masahiko; Kobayashi, Keita; Nakamura, Hiroki; Yamaguchi, Akiko; Itakura, Mitsuhiro; Machida, Masahiko

no journal, , 

no abstracts in English

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