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JAEA Reports

Development of stable solidification technique of ALPS sediment wastes by apatite ceramics (Contract research); FY2019 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*

JAEA-Review 2020-060, 116 Pages, 2021/02

JAEA-Review-2020-060.pdf:16.98MB

JAEA/CLADS had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project in FY2019. Among the adopted proposals in FY2019, this report summarizes the research results of the "Development of Stable Solidification Technique of ALPS Sediment Wastes by Apatite Ceramics" conducted in FY2019.

JAEA Reports

Development of the Sintering Solidification Method for Spent Zeolite to Long-term Stabilization (Contract research); FY2019 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Shibaura Institute of Technology*

JAEA-Review 2020-049, 78 Pages, 2021/01

JAEA-Review-2020-049.pdf:5.85MB

JAEA/CLADS had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project. Among the adopted proposals in FY2018, this report summarizes the research results of the "Development of the Sintering Solidification Method for Spent Zeolite to Long-term Stabilization" conducted in FY2019.

Journal Articles

Frontline of R&D for decommissioning and waste disposal, 1; R&D for processing and disposal of low-level radioactive waste and closure of uranium mine

Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya

Nippon Genshiryoku Gakkai-Shi, 62(11), p.658 - 663, 2020/11

no abstracts in English

JAEA Reports

Development of the sintering solidification method for spent zeolite to long-term stabilization (Contract research); FY2018 Center of World Intelligence Project for Nuclear Science/Technology and Human Resource Development

Collaborative Laboratories for Advanced Decommissioning Science; Shibaura Institute of Technology*

JAEA-Review 2019-028, 71 Pages, 2020/03

JAEA-Review-2019-028.pdf:6.46MB

JAEA/CLADS, had been conducting the Center of World Intelligence Project for Nuclear Science/Technology and Human Resource Development (hereafter referred to "the Project") in FY2018. Among the adopted proposals in FY2018, this report summarizes the research results of the "Development of the Sintering Solidification Method for Spent Zeolite to Long-term Stabilization". The present study aims to develop the sintering solidification method for zeolites (spent zeolites) that adsorbs continuously generated radionuclides such as cesium. The sintering solidification method is able to stabilize adsorbed radionuclides such as cesium in zeolites by adding a glass as a binder to spent zeolite and sintered it. It is expected that the sintering solidification method is significantly reduce the volume of the solidified body compare with the glass solidification method and to form a stable solidified body equivalent to the calcination solidification method. In this project, we planned to select a glass suitable for the sintering solidification method and optimize the sintering temperature, etc. using non-radioactive nuclides (cold tests), and verify it by using radioactive nuclides (hot tests). In FY2018, we investigated the thermal properties of candidate glasses for binder and the effect of heating atmosphere on the sintering solidification method. Irradiated fuel for preparing simulated contaminated water containing radionuclides was selected and the condition of it was observed. In addition, we surveyed existing research results and latest research trends about solidification of zeolite, calcination solidification and so on.

JAEA Reports

Waste liquid treatment for uranium liquid waste containing impurities

Sato, Yoshiyuki; Aono, Ryuji; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Testing 2019-003, 20 Pages, 2019/12

JAEA-Testing-2019-003.pdf:2.08MB

In the Radioactive Waste Management Technology Section, the radioactive liquid waste generated in the test using natural uranium in the past has been stored based on the contents of permission. Although we decided to perform solidification treatment in order to reduce the risk in storage, no rational treatment method has been established so far. Therefore, we examined adsorption treatment of natural uranium using uranium adsorbent (Tannix), and finally stabilized treatment by cement solidification. The treatment methods and findings obtained for a series of operations in waste liquid treatment are summarized in this report for reference when treating similar liquid waste.

Journal Articles

Waste management in a Hot Laboratory of Japan Atomic Energy Agency, 2; Condensation and solidification experiments on liquid waste

Watanabe, So; Ogi, Hiromichi*; Shibata, Atsuhiro; Nomura, Kazunori

International Journal of Nuclear and Quantum Engineering (Internet), 13(4), p.169 - 174, 2019/04

As a part of STRAD project conducted by JAEA, condensation of radioactive liquid waste containing various chemical compounds using reverse osmosis (RO) membrane filter was examined for efficient and safety treatment of the liquid wastes accumulated inside hot laboratories. NH$$_{4}$$$$^{+}$$ ion in the feed solution was successfully concentrated, and NH$$_{4}$$$$^{+}$$ ion involved in the effluents became lower than target value; 100 ppm. Solidification of simulated aqueous and organic liquid wastes was also tested. Those liquids were successfully solidified by adding cement or coagulants. Nevertheless, optimization in materials for confinement of chemicals is required for long time storage of the final solidified wastes.

JAEA Reports

The Catalog of solidification and volume reduction technologies for the treatment of radioactive waste generated by the decommissioning of Fukushima Daiichi Nuclear Power Station

Kato, Jun; Nakagawa, Akinori; Taniguchi, Takumi; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro

JAEA-Review 2017-015, 173 Pages, 2017/07

JAEA-Review-2017-015.pdf:6.67MB

Various radioactive wastes have been generated at the Fukushima Daiichi Nuclear Power Station (1F). To dispose of the wastes underground, it is necessary to make a suitable waste package by the volume reduction and solidification of the wastes. To plan the future decommissioning of 1F, it is also necessary to estimate feasibility of existing treatment technology for those wastes. Therefore the document survey has been performed about volume reduction and solidification technologies that have domestic or foreign experiences of practical treatment for radioactive wastes to assist selection of suitable treatment of the wastes. This report shows the arranged results. The 1F wastes are classified into two groups, homogeneous particulate and liquid wastes and heterogeneous solid wastes. The needful items for the feasibility study such as a technology name, a fundamental principle, treatment efficiency, and characteristic of solidified waste are summarized in each group.

Journal Articles

Completion of solidification and stabilization for Pu nitrate solution to reduce potential risks at Tokai Reprocessing Plant

Mukai, Yasunobu; Nakamichi, Hideo; Kobayashi, Daisuke; Nishimura, Kazuaki; Fujisaku, Sakae; Tanaka, Hideki; Isomae, Hidemi; Nakamura, Hironobu; Kurita, Tsutomu; Iida, Masayoshi*; et al.

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04

TRP has stored the plutonium in solution state for long-term since the last PCDF operation in 2007 was finished. After the great east Japan earthquake in 2011, JAEA had investigated the risk against potential hazard of these solutions which might lead to make hydrogen explosion and/or boiling of the solution accidents with the release of radioactive materials to the public when blackout. To reduce the risk for storing Pu solution (about 640 kg Pu), JAEA planned to perform the process operation for the solidification and stabilization of the solution by converted into MOX powder at PCDF in 2013. In order to perform PCDF operation without adaption of new safety regulation, JAEA conducted several safety measures such as emergency safety countermeasures, necessary security and safeguards (3S) measures with understanding of NRA. As a result, the PCDF operation had stared on 28th April, 2014, and successfully completed to convert MOX powder on 3rd August, 2016 for about 2 years as planned.

Journal Articles

Decontamination and volume reduction of cesium-contaminated soil by combining soil solidification with interpolyelectrolyte complex and wet classification

Yamashita, Yuji*; Yanase, Nobuyuki; Nagano, Tetsushi; Mitamura, Hisayoshi; Naganawa, Hirochika

Journal of Radioanalytical and Nuclear Chemistry, 305(2), p.583 - 587, 2015/08

 Times Cited Count:4 Percentile:56.57(Chemistry, Analytical)

We propose a method for the decontamination and waste volume reduction of cesium-contaminated soil. The soils were solidified with an interpolyelectrolyte complex solution and classified into several size fractions by wet sieving. $$gamma$$-ray spectrometry of these fractions showed that the distribution ratio of the activity concentration of coarse soil particles decreased, whereas that of soil particles under 0.075 mm increased relative to reference samples. Results show that the fine soil particles, on which radioactive cesium accumulates, were removed from the surface of the coarse soil particles during, and remained in the washing water.

JAEA Reports

Investigation report on the ruptured glove of ash removing room in the waste treatment building No.1 in JAERI Tokai Research Establishment

JAERI's Internal Investigation Group on the Ruptured Glove; Department of Decommissioning and Waste Management

JAERI-Review 2002-017, 121 Pages, 2002/09

JAERI-Review-2002-017.pdf:13.36MB

On November 21st, 2001, the glove rupture arose at an incinerator of Waste Treatment Building No.1 in JAERI Tokai Research Establishment. In order to examine the cause and recurrence prevention measure of the rupture, JAERI's Internal Investigation Group on the Ruptured Glove investigated the conditions of the incinerator including ash removing equipment and the glove, types and properties of waste which was incinerated on that day, and background factor of the trouble in cooperation with Department of Decommissioning and Waste Management.As the result, the causes of the rupture were that the solidification of liquid scintillator waste was insufficient, that the protective cover of the glove does not have pressure resistance and the degraded glove was used. For preventing the recurrence of the trouble, the direct confirmation of the solidification condition, the installation of protective cover for the glove, the improvement of the management of the glove, review of manuals and education and training were carried out.

Journal Articles

Unit sphere concept for macroscopic triggering of large-scale vapor explosions

Maruyama, Yu*; Moriyama, Kiyofumi; Nakamura, Hideo

Journal of Nuclear Science and Technology, 39(8), p.854 - 864, 2002/08

 Times Cited Count:4 Percentile:69.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Separation and immobilization of Sr and Cs contained in acidic media by using inorganic ion-exchangers (literature survey)

Yamagishi, Isao

JAERI-Review 2001-027, 52 Pages, 2001/07

JAERI-Review-2001-027.pdf:3.59MB

The present study deals with the survey of inorganic ion-exchangers suitable for separation and immobilization of Sr and Cs contained in acidic high-level liquid waste. For separation and immobilization of Cs, crystalline silicotitanate seems to be the most promising exchanger. For selective separation of Sr, there is no promising exchanger up to now. Sintered ceramics are favorable waste forms of inorganic ion-exchangers. Their stabilities are largely influenced by composition of exchangers, qualities of ceramics and disposal scenario.

Journal Articles

Steel plate-cast iron hybrid casting with steel shot mold

Nakamura, Hisashi; Hirabayashi, Takakuni; Akimoto, Jun*; Takahashi, Kenji*; Shindo, Hideaki*; Sakurai, Daihachiro*; Almansour, A.*; Okane, Toshimitsu*; Umeda, Takateru*

Proceedings Modeling of Casting & Solidification Processes 4, 1999, p.437 - 445, 1999/09

no abstracts in English

Journal Articles

Restricted recycling technology development for radioactive metallic waste; Waste container fablication tests

Nakamura, Hisashi; Hirabayashi, Takakuni

Nihon Kikai Gakkai Dai-6-Kai Doryoku, Enerugi Gijutsu Shimpojiumu '98 Koen Rombunshu, p.371 - 376, 1998/00

no abstracts in English

Journal Articles

Thermal characteristics of microencapsulated phase-change materials

E.Choi*; Akino, Norio

Proc. of 11th Int. Heat Transfer Conf. (Heat Transfer 1998), 7, p.121 - 126, 1998/00

no abstracts in English

Journal Articles

Casting test for manufacturing recycled items from slightly radioactive metallic materials arising from decommissioning

Nakamura, Hisashi; Shindo, Hideaki

Proc. of 3rd European Technical Seminar on Melting and Recycling of Metallic waste Materials, p.79 - 91, 1997/00

no abstracts in English

Journal Articles

High-frame-rate video visualization of simulated lower head behavior during TMI accident using neutron radioscopy

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka; Mishima, Kaichiro*; Hibiki, Takashi*

Fifth World Conf. on Neutron Radiography, 0, p.665 - 672, 1996/00

no abstracts in English

Journal Articles

Development of reactor decommissioning waste technology in JAERI

Kato, Kiyoshi

Hoshasei Haikibutsu Kanri Semmon Kenkyukai Hokokusho, p.24 - 28, 1987/00

no abstracts in English

Journal Articles

Reacter decommissioning technology development in JAERI 6, Development of waste management technology

Numakunai, Takao;

Genshiryoku Kogyo, 32(9), p.74 - 79, 1986/00

no abstracts in English

Journal Articles

Solidification of filter sludge with polyethylene

; ; *

Atomkernenerg.Kerntech., 40(4), p.254 - 258, 1982/00

no abstracts in English

25 (Records 1-20 displayed on this page)