Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Uesawa, Shinichiro; Yamashita, Susumu; Shibata, Mitsuhiko; Yoshida, Hiroyuki
no journal, ,
no abstracts in English
Okita, Shoichiro; Aoki, Takeshi; Sato, Hiroyuki; Aihara, Jun; Ohashi, Hirofumi
no journal, ,
no abstracts in English
Uesawa, Shinichiro; Horiguchi, Naoki; Shibata, Mitsuhiko; Yoshida, Hiroyuki
no journal, ,
no abstracts in English
Horiguchi, Naoki; Yoshida, Hiroyuki; Kitatsuji, Yoshihiro; Fukumori, Mai*; Takemura, Yuki*; Hasegawa, Makoto*; Kishimoto, Tadafumi*
no journal, ,
no abstracts in English
Nakayama, Shinsuke
no journal, ,
JENDL-5 includes several sublibraries to contribute to various applications. The deuteron reaction sublibrary developed mainly for the design of accelerator neutron sources and the alpha-particle reaction one developed mainly for use in the nuclear backend field will be outlined. As for the deuteron reaction sublibrary, the data for Li-6,7, Be-9, and C-12,13 of JENDL/DEU-2020 were partially modified and adopted. The data for Al-27, Cu-63,65, and Nb-93 important as accelerator structural materials were newly evaluated based on the calculated values with the DEURACS code. As for the alpha-particle reaction sublibrary, the evaluated values based on the CCONE calculations were replaced only with respect to the neutron production cross-sections by the data of JENDL/AN-2005 and were adopted. As a result, the accuracy of the energy and angular distribution of the outgoing neutrons was improved while maintaining the accuracy of the neutron production cross-sections. In addition, the completeness of data other than neutron production such as gamma-ray production was improved.
Furutaka, Kazuyoshi; Ozu, Akira; Toh, Yosuke
no journal, ,
no abstracts in English
Yamashita, Susumu; Uesawa, Shinichiro; Yoshida, Hiroyuki
no journal, ,
no abstracts in English
Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke
no journal, ,
no abstracts in English
Ozu, Akira; Maeda, Makoto; Komeda, Masao; Toh, Yosuke
no journal, ,
no abstracts in English
Toh, Yosuke; Tsuchiya, Harufumi; Ozu, Akira; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo
no journal, ,
no abstracts in English
Minato, Futoshi
no journal, ,
no abstracts in English
Iwamoto, Osamu
no journal, ,
no abstracts in English
Luu, V. N.; Nakajima, Kunihisa
no journal, ,
Tamura, Ken; Shuji, Yoshiyuki; Hirano, Hiroshi*; Tachihara, Joji; Ono, Yosuke; Shoji, Hiroyuki*; Kawasaki, Takashi
no journal, ,
no abstracts in English
Ouchi, Kazuki; Kitatsuji, Yoshihiro; Maeda, Shigetaka; Takaki, Naoyuki*
no journal, ,
Efficient Actinium-225 Separation from Ra-226 irradiated in fast reactor was studied. Ba and La were used as alternatives to Ra and Ac, respectively. By using DGA resin as an adsorbent, it can be expected that Ra and impurities generated by irradiation will be removed and Ac will be isolated.
Ouchi, Kazuki; Tsukahara, Takehiko*; Brandt, A.*; Muto, Yuki*; Nabatame, Nozomi*; Koma, Yoshikazu; Kitatsuji, Yoshihiro
no journal, ,
We designed microchannel for packing with aion-exchange resins that can reduce the radiation exposure risk and the secondary radioactive wastes during uranium (U) separation. Two types of microchips were designed to densely pack the microchannels with resins. The microchannels had almost the same cross-sectional area, but different outer circumferences. A satisfactory separation performance could be obtained by arranging more than ca. 10 resins along the depth and width of the microchannels. The separation performance of the microchannel was evaluated using the seawater standard added Cs-133 as a reference of 1F retained water. The measured value of U in the seawater sample was in good agreement with the certified value. These results indicate that a resin-packed microchannel is suitable for determining the U from highly concentrated matrix elements.
Iwamoto, Nobuyuki
no journal, ,
no abstracts in English
Tsubota, Yoichi; Honda, Fumiya; Yoshida, Masato; Nakagawa, Takahiro; Tamakuma, Yuki*; Tokonami, Shinji*; Ikeda, Atsushi
no journal, ,
A large amount of radioactive aerosols are expected to be dispersed fuel during debris cutting during large-scale retrieval of fuel debris at the Fukushima Daiichi Nuclear Power Plant (1F) and dismantling of nuclear fuel attachments during decommissioning of nuclear fuel facilities. Particulates containing 
-nuclides (-aerosols) in particular have very high effective dose coefficients upon inhalation, therefore appropriate control and measurements are required. Conventional dust monitors using SSBD have difficulties with moisture resistance, noise resistance, and clogging of filter paper. We have designed and prototyped an -aerosol monitor that directly measures -rays from aerosols using a scintillator and a multi-channel photomultiplier tube after drying the aerosols by heating the flat channel inlet without using a collecting filter paper in order to realize monitoring near the point where highly concentrated -aerosols are generated. In this presentation, we report on the results of basic performance evaluations, the change in particle size due to air drying, and the improvement of the power supply method of the detection unit for on-site implementation at 1F.
Miyazaki, Yasunori; Sano, Yuichi; Takeuchi, Masayuki; Arai, Tsuyoshi*; Kim, S.-Y.*; Wu, H.*; Miwa, Misako*; Matsuyama, Shigeo*
no journal, ,
Separation of minor actinides (MA; Am, Cm) is social demand to reduce the volume and toxicity of radioactive waste generated by spent nuclear fuel reprocessing. We have proposed extraction chromatography that employs the TEHDGA-impregnated adsorbent in a separation column. From the previous study, MA recovery from the real radioactive waste liquid was achieved, and a flowsheet study is continued to improve the product purity (or decontamination coefficient). On the other hand, we are also investigating the decomposition and reuse of spent adsorbent. In this presentation, both of the degradability of the adsorbent by the Fenton reaction and the reusability of the re-impregnated adsorbent from the batch-wise adsorption test results are reported by the element distribution by micro-PIXE analysis.
Machida, Masahiko; Iwata, Ayako; Yamada, Susumu
no journal, ,
no abstracts in English