Parker, J. D.*; Harada, Masahide; Hayashida, Hirotoshi*; Hiroi, Kosuke; Kai, Tetsuya; Matsumoto, Yoshihiro*; Nakatani, Takeshi; Oikawa, Kenichi; Segawa, Mariko; Shinohara, Takenao; et al.
Materials Research Proceedings, Vol.15, p.102 - 107, 2020/05
Oba, Yojiro; Ito, Daisuke*; Saito, Yasushi*; Onodera, Yohei*; Parker, J. D.*; Shinohara, Takenao; Oikawa, Kenichi
Materials Research Proceedings, Vol.15, p.160 - 164, 2020/02
Lead Bismuth eutectic (LBE) is a promising candidate of the coolant for accelerator driven system (ADS) and fast breeder reactor. Neutron transmission imaging is a powerful technique to investigate the LBE in flow channel. However, previous studies have focused on the analysis of the neutron transmission spectra due to Bragg diffraction (Bragg edge transmission) from the solid phase of the LBE. If the neutron transmission spectra due to the diffraction from a liquid phase can be observed, it is useful to study the behavior of the molten LBE in the flow channel. Therefore, the energy-resolved neutron transmission imaging measurements of the molten LBE was carried out. The observed neutron transmission spectra can be explained by those calculated from the scattering profiles of the molten LBE. This indicates that the structure of the molten LBE can be characterized and mapped using the neutron transmission imaging.
Oikawa, Kenichi; Kiyanagi, Yoshiaki*; Sato, Hirotaka*; Omae, Kazuma*; Pham, A.*; Watanabe, Kenichi*; Matsumoto, Yoshihiro*; Shinohara, Takenao; Kai, Tetsuya; Harjo, S.; et al.
Materials Research Proceedings, Vol.15, p.207 - 213, 2020/02
Kai, Tetsuya; Hiroi, Kosuke; Su, Y. H.; Segawa, Mariko; Shinohara, Takenao; Matsumoto, Yoshihiro*; Parker, J. D.*; Hayashida, Hirotoshi*; Oikawa, Kenichi
Materials Research Proceedings, Vol.15, p.149 - 153, 2020/02
Miyahara, Kaname; Tokizawa, Takayuki; Nakayama, Shinichi
Materials Research Society Symposium Proceedings, Vol.1518, p.245 - 256, 2013/10
After the Fukushima Dai-ichi accident, Japan Atomic Energy Agency (JAEA) was chosen by the Government to conduct decontamination model projects at selected sites. Despite tight boundary conditions in terms of timescale and resources, the decontamination model projects provide a good basis for developing recommendations on how to assure clean-up efficiency and reduce time, cost, subsequent waste management and environmental impact. This can be summarised in terms of site characterisation and data interpretation, clean-up and waste minimisation and storage.
Kobayashi, Taishi*; Sasaki, Takayuki*; Ueda, Kenyo*; Kitamura, Akira
Materials Research Society Symposium Proceedings, Vol.1518, p.231 - 236, 2013/10
For the nuclear waste management of TRU waste, it is necessary to assess the impact of nitrate salts contained in the waste. In the present study, the sorption behavior of Ni and Pd on the pumice tuff was investigated in the presence of NH(aq)/NH. Under different NH(aq)/NH concentration, pH and ionic strength conditions, distribution coefficient () of Ni and Pd on the pumice tuff was determined by batch experiment. For Ni system, the values showed no significant dependence on the initial NH concentration in neutral pH region, agrees with the prediction from thermodynamic data. For Pd system, the values decreased with an increase of [NH]ini, suggesting the formation of stable ammine complex (Pd(NH) (: 1 - 4)). The obtained values for Ni and Pd were analyzed using the surface complexation model. By taking complexes predicted by thermodynamic data into account, the sorption behavior of Ni and Pd in the presence of NH(aq)/NH were well explained.
Takeda, Seiji; Inoue, Yoshihisa; Kimura, Hideo
Materials Research Society Symposium Proceedings, Vol.1518, p.237 - 242, 2013/10
The sensitive analysis of radionuclide migration for the scenarios on deterioration or loss of safety functions expected in HLW disposal system due to the human error (initial defective scenarios) is performed in this study. Release rates for Cs-135 and Se-79 are estimated from Monte Carlo-based analysis. Maximum release rates of radionuclides for initial defective scenarios, buffer (colloidal transport case) and sealing plugs (pathway of short-circuit), are about one or two order magnitude higher than that normal scenario. From a viewpoint of future safety review, these results especially indicate the need to understand the feasibility on two types of initial defective scenario for the buffer and sealing plugs, leading to the loss of restraint of colloidal migration in the buffer and the loss of restraint with the plugs from migration through dominant pathway in tunnels and their vicinity.
Sasaki, Toshiki; Kaminishi, Shuji*; Miyamoto, Yasuaki; Funasaka, Hideyuki
Materials Research Society Symposium Proceedings, Vol.1518, p.257 - 268, 2013/10
The Fukushima Daiichi Nuclear Power Station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as radionuclide analysis of the waste, hydrogen generation/diffusion analysis of a storage vessel, corrosion evaluation of storage vessels, etc. have been performed for characterization and safe storage of the waste. The detailed R&D plan for processing and disposal waste will be established by the end of FY2012.
Yoshikawa, Hideki; Iijima, Kazuki; Sasamoto, Hiroshi; Fujiwara, Kenso; Mitsui, Seiichiro; Kitamura, Akira; Kurikami, Hiroshi; Tokizawa, Takayuki; Yui, Mikazu; Nakayama, Shinichi
Materials Research Society Symposium Proceedings, Vol.1518, p.269 - 275, 2013/10
Following the release of radionuclides into the environment as a result of the accident at Fukushima Daiichi Nuclear Power Plant, Japan Atomic Energy Agency (JAEA) had to develop an immediate and effective method of reducing the dose rate received by students in school facilities. A demonstration of a reducing method was carried out by JAEA at a junior high school ground and kindergarten yard in the center of Fukushima-city. Dose rates of the released radionuclides are largely controlled by the ground level contamination and accumulation of mainly cesium-137 (Cs) and cesium-134 (Cs) in populated areas. An effective means of reducing dose rate was to remove the surface soil and to bury it on-site under fresh uncontaminated soil or soil collected under deep depth at the site for shielding. The dose rate at1 m above ground level was reduced from 2.5 Sv/h to 0.15 Sv/h.
Sato, Haruo; Niizato, Tadafumi; Amano, Kenji; Tanaka, Shingo; Aoki, Kazuhiro
Materials Research Society Symposium Proceedings, Vol.1518, p.277 - 282, 2013/10
The accident of the TEPCO Fukushima Dai-ichi Nuclear Power Plant occurred by the 2011 off the Pacific coast of Tohoku Earthquake on 11 March, 2011. It is estimated that 1.2-1.510 Bq for Cs and 1.5-1.610 Bq for I-131 were released until the beginning of April and those radionuclides (RN) were deposited on soil surface and forest etc. widely around Fukushima Pref. This work was carried out as one of the investigations for making the distribution maps of radiation dose rate and soil contaminated by RNs which the MEXT promotes. The Geoslicer investigation on the depth distribution of RNs in soil was carried out after 3 months from the accident. The investigation was conducted at 11 locations in Nihonmatsu City, Kawamata Town and Namie Town, and soil samples of depth 50 cm to 1 m were taken. Both of Cs and Cs were detected in all investigated locations, and Te and Ag were detected only in areas where radiation dose rates are high. At many locations investigated, radiocaesium more than 99% distributed within a depth of 10 cm in soil in the surface layer. On the other hand, RNs tended to distribute to deeper part in soil at locations that are supposed to have been used as farmland than in soil in the surface layer, and radiocaesium more than 99% in soil at locations that are supposed to have been used as farmland also distributed within a depth of around 14 cm. The apparent diffusion coefficients of RNs derived from penetration profiles near the surface layer showed a tendency to be higher in soil at locations that are supposed to have been used as farmland than in soil in the surface layer. The distribution coefficients by a batch method were also obtained for Cs and I, and the relationship between D and K was discussed.
Abe, Yosuke; Tsuru, Tomohito; Jitsukawa, Shiro
Materials Research Society Symposium Proceedings, Vol.1535 (Internet), 7 Pages, 2013/04
In this study, in addition to adequately model the 1D reaction kinetics of SIA loops in the framework of a production bias model, reaction kinetics associated with carbon impurity atoms present in -iron have been formulated to take into account the trapping effect of glissile SIA loops by vacancy-carbon (V-C) complexes that have been shown to have strong bindings with SIA loops by atomistic simulations. Results of calculated defect accumulation behavior of neutron irradiated -iron show that the developed CD model can successfully reproduce the number densities of SIA loops and vacancy clusters when the applied impurity concentration is the same order as experimental one. This indicates that the assumed mechanism for the trapping of glissile SIA loops by V-C complexes is reasonable. The dependences of irradiation dose, dose rate, and temperature are discussed in detail.
Harjo, S.; Tsuchida, Noriyuki*; Gong, W.; Abe, Jun; Aizawa, Kazuya
Materials Research Society Symposium Proceedings, Vol.1528 (Internet), 7 Pages, 2013/01
Transformation Induced Plasticity (TRIP) is one of important effects of steel strengthening mechanism to improve strength, ductility and excellent high-speed deformation behavior. To measure strengthening mechanism of TRIP steel during deformation, in situ neutron diffraction measurement during tensile deformation was performed. Two kinds of TRIP steels with different carbon content were prepared. Neutron diffraction measurements were performed using beamline 19 TAKUMI, a pulsed-neutron TOF diffractometer in J-PARC. Detail results will be shown and discussed during presentation.