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Hirata, Sakiko*; Kusaka, Ryoji; Meiji, Shogo*; Tamekuni, Seita*; Okudera, Kosuke*; Hamada, Shoken*; Sakamoto, Chihiro*; Honda, Takumi*; Matsushita, Kosuke*; Muramatsu, Satoru*; et al.
Inorganic Chemistry, 62(1), p.474 - 486, 2023/01
Times Cited Count:0 Percentile:0.01(Chemistry, Inorganic & Nuclear)Nankawa, Takuya; Sekine, Yurina
Isotope News, (778), p.34 - 35, 2021/12
A high-performance adsorbent was synthesized by reaction of waste bone and sodium hydrogen carbonate. Since waste bones are inexpensive and well-supplied materials, it has the potential to be used for a wide range of decontamination and removal of harmful metals.
Mizutani, Akihiko; ;
JNC TN9400 2000-013, 66 Pages, 2000/02
Feasibility study on a self-consistent fuel cycle system has been performed in the nuclear fuel recycle system with fast reactors. ln this system, the self-generated MAs (Minor Actinides) and LLFPs (Long-Lived Fission Products) are confined and incinerated in the fast reactor, which is called the "Equilibrium Core" concept. However, as the isotope separations for selected LLFPs have been assumed in this cycle system, it seems that this assumption is far from realistic one from the viewpoint of economy with respect to the fuel cycle system. ln this study, the possibility for realization of the "Equilibrium Core" concept is evaluated for three fuel types such as oxide, nitride and metallic fuels, provided that the isotopic separation of LLFPs is changed to the element one. This study provides, that is to say, how many LLFP elements can be confined in the "Equilibrium Core" with element separation. This report examines the nuclear properties of the "Equilibrium Core" for various combinations of LLFP incineration schemes from the viewpoints of the risk of geological disposal and the limit in confinable quantity of LLFPs. From the viewpoint of the risk of geological disposal estimated by the retardation factor, it is possible to confine with element separation for T, I and Se even in the oxide fueled core. From the standpoint of the limit of confinable amounts of LLFPs, on the other hand, T, I, S, S and Cs can be confined with element separation in case that the nitride fuel is chosen.
Yomogida, Takumi; Asai, Shiho; Saeki, Morihisa; Hanzawa, Yukiko; Esaka, Fumitaka; Oba, Hironori; Magara, Masaaki
no journal, ,
Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive waste (HLW) is indispensable for the long-term safety assessment of geological repository. Reliability of the estimated inventory is verified with actual measurement values which are drawn from proven analytical techniques. There has been increasing interest in the development of new determination methods of Pd-107 which is one of the LLFPs with a half-life of 6.510 y because little measured data has been reported. Major difficulty in determination of Pd-107 involves the poor recovery of Pd in separation step required prior to measurement. In this study, a highly selective separation technique based on laser-induced microparticle formation has been applied to Pd separation. The recovery percentage of Pd from a simulated HLW solution were affected by irradiation time and laser pulse energy. The maximum recovery percentage of 60% was achieved by 20-min irradiation at the energy of 100 mJ.
Yomogida, Takumi; Asai, Shiho; Saeki, Morihisa; Hanzawa, Yukiko; Esaka, Fumitaka; Oba, Hironori; Kitatsuji, Yoshihiro
no journal, ,
Palladium-107, which is one of the long-lived fission products in high-level radioactive waste (HLW), is a pure beta emitter with a half-life of 6.510 y. The inventory estimation of Pd is demanded for the long-term safety assessment of geological repository. ICP-MS is suitable for the determination of Pd because radiometry with a low beta energy of 33 keV is practically inapplicable. However, cumbersome chemical separation accompanied with highly radioactive sample treatment is still necessary prior to the measurement with ICP-MS. To minimize radioactive contamination and radiation exposure, simplified procedure is desirable. In this study, a simple separation technique based on laser-induced microparticle formation has been applied to Pd separation in a simulated HLW solution. Sufficiently high decontamination factors of coexisting elements ( 1000) were observed, indicating that the proposed method achieved highly-selective separation of Pd.
Yomogida, Takumi; Asai, Shiho; Saeki, Morihisa; Hanzawa, Yukiko; Esaka, Fumitaka; Oba, Hironori; Kitatsuji, Yoshihiro
no journal, ,
Sekio, Yoshihiro; Iwamoto, Yasuhiro; Hamada, Maho; Maeda, Koji; Higuchi, Toru*; Suzuki, Tatsuya*; Idemitsu, Kazuya*; Konashi, Kenji*; Nagai, Yasuyoshi*
no journal, ,
It is essential to understand the properties of fuel debris for implementation of various countermeasures related to fuel debris retrieval and storage management at the Fukushima Daiichi Nuclear Power Station (1F). The step-by-step retrieval and property analysis are planned in the future. Especially, the chemical analysis is needed for chemical composition information but fuel debris is considered to be insoluble due to the occurrence of melt core-concrete interaction. Therefore, the establishment of chemical analysis method is an key issue. In this research, to establish suitable dissolution methods as well as separation and analysis processes is planned by using Inductively Coupled Plasma Mass Spectrometry which has been applied in the field of radiochemistry in recent years. In this presentation, we will introduce the outline of the implementation and the collaborative laboratories established at JAEA and Tohoku University as a place for human resource development.