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Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke
no journal, ,
no abstracts in English
Iwamoto, Nobuyuki; Iwamoto, Osamu; Rovira Leveroni, G.; Nakamura, Shoji; Kimura, Atsushi; Katabuchi, Tatsuya*
no journal, ,
no abstracts in English
Rovira Leveroni, G.; Katabuchi, Tatsuya*; Iwamoto, Osamu; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Nobuyuki; Endo, Shunsuke; Terada, Kazushi*; Kodama, Yu*; Nakano, Hideto*; et al.
no journal, ,
Cs derived from Fukushima Dai-ichi Nuclear Power Plant using the short-term emergency assessment system of marine environmental radioactivityIkenoue, Tsubasa; Kawamura, Hideyuki; Kamidaira, Yuki
no journal, ,
In this study, we analyzed the characteristics and trends of oceanic dispersal of Cs by performing the oceanic dispersion simulations using past oceanographic data received on the Short-Term Emergency Assessment system of Marine Environmental Radioactivity (STEAMER) developed at JAEA. Oceanic dispersion simulations in 1461 cases were carried out in the northwestern Pacific Ocean for 60 days from every day between 2015 and 2018. It was assumed that Cs was released into the ocean from the Fukushima Dai-ichi Nuclear Power Plant. In all calculation cases, the maximum concentration in 30 days at each computational grid (maximum concentration distribution) was calculated. Cs in the ocean surface in winter tended to be not dispersed so much. In the ocean surface, the seasonal variation was greater than the annual variation though the maximum concentration distributions have little annual variation. The average of the maximum concentration distribution in all calculation cases was inclined to be high from the coast of Fukushima to the offshore (140
E-145E) and near the Kuroshio Extension.
TaEndo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.
no journal, ,
no abstracts in English
Iwamoto, Hiroki; Meigo, Shinichiro; Nishio, Katsuhisa; Ishi, Yoshihiro*; Hirose, Kentaro; Iwamoto, Yosuke; Kuriyama, Yasutoshi*; Maekawa, Fujio; Makii, Hiroyuki; Nakano, Keita; et al.
no journal, ,
no abstracts in English
Takeuchi, Masayuki; Sano, Yuichi; Watanabe, So
no journal, ,
In order to achieve the reduction of vitrification waste volume, it is important not to move minor actinides (MA) to vitirification waste by its partitioning and transmutation. In this presentation, the summary of MA partitioning program from high level radioactive liquid waste using extraction chromatography will be introduced.
Malins, A.
no journal, ,
The inventories of radioactive nuclides present at nuclear power plants, research institutions, hospitals, in the environment, etc., change continuously due to radioactive decay. radioactive decay is an easy-to-use Python package that can calculate the changes in activities of radionuclides due to radioactive decay to high precision. The source code is published via GitHub and the Python Package Index (PyPI). This talk will explain the features and the development process of the code.
Motoyama, Risa; Hinai, Hiroshi; Ichige, Yoshiaki; Koma, Yoshikazu; Shibata, Atsuhiro
no journal, ,
no abstracts in English
Uchida, Shunsuke; Osaka, Masahiko; Karasawa, Hidetoshi; Kino, Chiaki*
no journal, ,
The Cs amounts in the major partial zone of the D/W and S/C of Units 1-3 have been evaluated by applying the BEP with the previously reported dose rate conversion factors. As a result of comparing the BEP results with those of the FEP based on the SA analysis code, the conclusions are summarized as follows. The measured dose rate for A and B detectors of D/W CAMS for Unit 1 showed the different patterns, which could be clearly explained by applying local wash-out effects. The Cs amounts in the D/W bottom regions for Units 1-3 could be evaluated by the BEP. The Cs amounts obtained with the BEP in the D/W bottom region and S/C for Unit 1 were consistent to those with the FEP. The Cs amounts obtained with the BEP in the D/W bottom regions for Units 2 and 3 were more than 10 times as large as those with the FEP.
Kasada, Ryuta*; Wang, H.*; Liu, J.*; Yu, H.*; Kondo, Sosuke*; Okuno, Yasuki*; Okubo, Nariaki; Tokunaga, Toko*; Ono, Naoko*
no journal, ,
With the aim of applying to materials in accelerator driven systems (ADS) core and advanced blankets of fusion systems, a Fe-Mn-Cr-Al-C steel, low-activation austenitic steel, and its oxide dispersion-strengthened (ODS) alloy have been developing. By reviewing the composition of Fe-Cr-Mn-based low-activation austenitic steel that was once examined, the ODS alloy has become a material design that is conscious of twinning induced plasticity (TWIP) steel used as an automobile steel plate, and it aims to improve high temperature strength characteristics and irradiation resistance by ODS. This presentation shows the initial result of the influence of ODS on the strength characteristics and lead bismuth corrosion on the alloy design policy and materials prototyped at the laboratory level. In addition, some issues for application to advanced fusion system blankets are also discussed.
Horiguchi, Naoki; Nakamura, Koichi*; Sekiguchi, Takashige*; Uesawa, Shinichiro; Himi, Masashi*; Yoshida, Hiroyuki; Nishimura, Satoshi*
no journal, ,
no abstracts in English
Takahashi, Fumiaki; Manabe, Kentaro; Takubo, Kazuya*; Sato, Kaoru
no journal, ,
JAEA has developed an internal dosimetry code based on the ICRP 2007 recommendation in a four-year plan from FY 2017 to FY 2020 through a project commissioned by the Nuclear Regulation Authority. In this year, we heard comments on operability and functions for the prototype code developed up to last from experts of institutions with knowledge and experience in radiation monitoring. After that, the GUI screen for input was improved and a new output function was added by reflecting the result of hearing. In addition, the new dose evaluation models released as ICRP Publ.141 in 2020 were investigated and implemented in the code. The improved code was verified to calculate effective dose coefficient correctly for the newly added models. In this presentation, we report the overall of the code and its utilization.
Riyana, E. S.; Okumura, Keisuke; Sakamoto, Masahiro; Matsumura, Taichi; Terashima, Kenichi
no journal, ,
Do, V. K.; Furuse, Takahiro; Ota, Yuki; Sano, Yuichi; Iwahashi, Hiroyuki; Homma, Shunta; Ichijo, Yurina; Kurosawa, Kiyoko*; Endo, Tsubasa*; Motoki, Yoshiaki*; et al.
no journal, ,
This paper presents an HCl-free chemical separation procedure for Sn recovery from concretes. Two pretreatment methods of solution samples followed by a proposed solid-phase extraction on TEVA resin were examined. The obtained results show that Sn can be highly recovered by the developed separation scheme with good reproducibility. The developed method is aimed at practical application to purification of Sn from concrete rubble for quantification of 
Sn by mass spectrometer.
Sato, Hiroyuki; Aoki, Takeshi; Yan, X.
no journal, ,
HTGR is expected to be used in various industrial fields due to its inherent safety characteristics and high temperature heat supply capability. JAEA is planning to connect heat application systems such as a helium gas turbine and a hydrogen production plant to the HTTR. This presentation reports summary and test plan for the HTTR direct gas turbine power generation system, HTTR hydrogen production system using steam methane reforming method and HTTR gas turbine cogeneration system.
Takai, Toshihide; Furukawa, Tomohiro; Watanabe, Shigeki*; Ishioka, Noriko*
no journal, ,
The authors report the result of corrosion test in stagnant bismuth at 500C for 500 hrs under a low oxygen partial pressure for the target window that is expected to have high corrosion resistance in high-temperature liquid bismuth.
Okumura, Keisuke; Sakamoto, Masahiro; Tada, Kenichi; Nishihara, Kenji; Mizokami, Shinya*; Mizokami, Masato*; Miki, Yosuke*; Kaneko, Seiji*
no journal, ,
no abstracts in English
Sakamoto, Masahiro; Okumura, Keisuke; Tada, Kenichi; Nishihara, Kenji; Mizokami, Shinya*; Mizokami, Masato*; Miki, Yosuke*; Kaneko, Seiji*
no journal, ,
no abstracts in English
Sato, Kaoru; Satoh, Daiki; Takahashi, Fumiaki; Furuta, Takuya
no journal, ,
Organ doses, which are basis of dose assessment in radiation protection, are derived from ICRP phantoms (Male: RCP-AM, Female: RCP-AF) with body physiques of standard Caucasian. In adult, Japanese have small size body, compared with Caucasian. Considering the physiques of Japanese is very important, when organ doses of RCP-AM and RCP-AF are applicable for constructing of radiation protection standard in Japan. So far, we reported the dosimetric characteristics of adult Japanese with various body sizes, which were irradiated with photons. In this study, we analyzed the impact of body sizes on organ doses due to external neutron irradiation. In analysis, we utilized the male and female phantoms with 3 body physiques by changing busts, chests, waists and hips of JM-103 and JF-103. In rotational geometry at 3 MeV, it was found that colon doses of adult Japanese phantoms with body sizes, which are applicable to most adult Japanese, agreed with those of RCP-AM and RCP-AF within 20%.