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Sato, Takumi; Otobe, Haruyoshi; Morishita, Kazuki; Marufuji, Takato; Ishikawa, Takashi; Fujishima, Tadatsune; Nakano, Tomoyuki
JAEA-Technology 2023-016, 41 Pages, 2023/09
JAEA-Technology-2023-016.pdf:2.74MB
This report summarizes the results of the stabilization treatments of post-experiment nuclear materials in Plutonium Fuel Research Facility (PFRF) from August 2018 to March 2021. Based on the management standards for nuclear materials enacted after the contamination accident that occurred at PFRF on June 6, 2017, the post-experiment nuclear materials containing plutonium (Pu): samples mixed with organic substances that cause an increase in internal pressure due to radiolysis (including X-ray diffraction samples mixed with epoxy resin and plutonium powder which caused contamination accidents), carbides and nitrides samples which is reactive in air, and chloride samples which may cause corrosion of storage containers, were selected as targets of the stabilization. The samples containing organic materials, carbides and nitrides were heated in an air flow at 650 
C and 950 C for 2 hours respectively to remove organic materials and convert uranium (U) and Pu into oxides. U and Pu chlorides in LiCl-KCl eutectic melt were reduced and extracted into liquid Cd metal by a reaction with lithium (Li) -cadmium (Cd) alloy and converted to U-Pu-Cd alloy at 500 C or higher. All of the samples were stabilized and stored at PFRF. We hope that the contents of this report will be utilized to consider methods for stabilizing post experiment nuclear materials at other nuclear fuel material usage facilities.
Seki, Misaki; Fujita, Yoshitaka; Fujihara, Yasuyuki*; Zhang, J.*; Yoshinaga, Hisao*; Sano, Tadafumi*; Hori, Junichi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; et al.
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 29(1), p.2 - 9, 2022/06
no abstracts in English
Senzaki, Tatsuya; Arai, Yoichi; Yano, Kimihiko; Sato, Daisuke; Tada, Kohei; Ogi, Hiromichi*; Kawanobe, Takayuki*; Ono, Shimpei; Nakamura, Masahiro; Kitawaki, Shinichi; et al.
JAEA-Testing 2022-001, 28 Pages, 2022/05
JAEA-Testing-2022-001.pdf:2.33MB
In preparation for the decommissioning of Laboratory B of the Nuclear Fuel Cycle Engineering Laboratory, the nuclear fuel material that had been stored in the glove box for a long time was moved to the Chemical Processing Facility (CPF). This nuclear fuel material was stored with sealed by a polyvinyl chloride (PVC) bag in the storage. Since it was confirmed that the PVC bag swelled during storage, it seems that any gas was generated by radiolysis of the some components contained in the nuclear fuel material. In order to avoid breakage of the PVC bag and keep it safety for long time, we began the study on the stabilization treatment of the nuclear fuel material. First, in order to clarify the properties of nuclear fuel material, radioactivity analysis, component analysis, and thermal analysis were carried out. From the results of thermal analysis, the existence of organic matter was clarified. Then, ion exchange resin with similar thermal characteristics was selected and the thermal decomposition conditions were investigated. From the results of these analyzes and examinations, the conditions for thermal decomposition of the nuclear fuel material contained with organic matter was established. Performing a heat treatment of a small amount of nuclear fuel material in order to confirm the safety, after which the treatment amount was scaled up. It was confirmed by the weight change after the heat treatment that the nuclear fuel material contained with organic matter was completely decomposed.
Seki, Misaki; Ishikawa, Koji*; Sano, Tadafumi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Fujihara, Yasuyuki*; et al.
KURNS Progress Report 2019, P. 279, 2020/08
no abstracts in English
Seki, Misaki; Ishikawa, Koji*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
KURNS Progress Report 2018, P. 257, 2019/08
no abstracts in English
Sakauchi, Hitoshi; Kikuchi, Yuki; Imaizumi, Haruki; Fukui, Yasutaka
Dekomisshoningu Giho, (57), p.34 - 42, 2018/03
OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of radioactive solid waste, which generate from hot facilities in Oarai Research and Development Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. In this report, we describe the outline of OWTF under construction and treatment technologies, in which incinerating and melting.
Sakauchi, Hitoshi; Sato, Isamu*; Donomae, Yasushi; Kitamura, Ryoichi
JAEA-Technology 2015-059, 352 Pages, 2016/03
JAEA-Technology-2015-059.pdf:51.53MB
OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of 
solid waste, which was generated from hot facilities in Oarai Research and Develop Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. This report describes corroborative tests, in which incinerating and melting performance for OWTF is confirmed with a full-scale testing furnace. We have been carrying out the tests of incinerating and melting treatment with some kinds of simulated wastes, such as enclosure form of radioactive wastes, material and articles.
Ishiyama, Takashi; Bamba, Tsunetaka; Mitamura, Hisayoshi; Maeda, Toshikatsu
Haikibutsu Gakkai Rombunshi, 12(2), p.82 - 86, 2001/03
no abstracts in English
Nishimura, Kazuaki; Tanaka, Hideki; Kobayashi, Daisuke; Suzuki, Shohei; Numata, Shinji; Nakamichi, Hideo; Kurita, Tsutomu; Iida, Masayoshi*; Tajiri, Kazuma*; Sukegawa, Katsumi*
no journal, ,
no abstracts in English
Numata, Shinji; Isomae, Hidemi; Omura, Masami; Tsutagi, Koichi; Kobayashi, Daisuke; Nakamura, Daishi; Nemoto, Masahiro; Iida, Masayoshi*; Tajiri, Kazuma*; Kurita, Tsutomu
no journal, ,
no abstracts in English
Seki, Misaki; Ishikawa, Koji*; Fujihara, Yasuyuki*; Sano, Tadafumi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Ide, Hiroshi; Hori, Junichi*; Tsuchiya, Kunihiko
no journal, ,
no abstracts in English
Taniguchi, Takumi; Osugi, Takeshi; Sone, Tomoyuki; Kobayashi, Kentaro
no journal, ,
no abstracts in English
Sato, Takumi; Morishita, Kazuki; Otobe, Haruyoshi; Fujishima, Tadatsune; Nakano, Tomoyuki
no journal, ,
no abstracts in English
関 美沙紀; 井手 広史; 永田 寛; 大塚 薫; 大森 崇純
石川 幸治*; 川上 智彦*; 田仲 睦*; 鈴木 祐未*
JP, 2019-149027 Patent licensing information Patent publication (In Japanese)
【課題】放射性アルミニウム廃棄物に含まれるアルミニウムを、化学的に安定である酸化アルミニウムに変換する放射性アルミニウム廃棄物処理方法を提供する。 【解決手段】本発明に係る放射性アルミニウム廃棄物処理方法は、放射性アルミニウム廃棄物に含まれるアルミニウムを酸化アルミニウムに変換する放射性アルミニウム廃棄物処理方法であって、放射性アルミニウム廃棄物を、アルカリ金属の水酸化物の水溶液で溶解し、不純物を沈殿させる溶解工程(工程S1)と、前記溶解工程で得られた溶液を、固液分離し不純物を除去する第1固液分離工程(工程S2)と、前記第1固液分離工程で得られた溶液に酸性水溶液を添加し、水酸化アルミニウムを主成分とする固体を沈殿させる中和工程(工程S3)と、前記中和工程で得られた溶液を、固液分離し固体を得る第2固液分離工程(工程S4)と、前記第2固液分離工程で得られた固体を焼成する焼成工程(工程S6)と、を含むことを特徴とする。
関 美沙紀; 中野 寛子; 藤田 善貴; 井手 広史
工藤 勇*; 末松 久幸*; Do Thi-Mai-Dung*; Yang Yaru*
JP, 2020-208604 Patent licensing information
【課題】放射性アルミニウムを含むアルカリ活性材料を固化する場合において、放射性アルミニウムの含有量を増やす技術を提供する。 【解決手段】固化体の作製方法は、アルミニウム合金をアルカリ金属の水酸化物溶液に溶解することによって、アルミニウム溶解液を生成する溶解工程(S1)と、原料としてのアルミニウム溶解液、活性フィラー、及びアルカリシリカ溶液を混錬することによって、アルカリ活性材料を生成する混錬工程(S3)と、アルカリ活性材料を型に充填して養生することによって、固化体を作製する固化工程(S4)を含む。
