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Journal Articles

Development of mineralization techniques for organic solvents by the silver mediated electrochemical oxidation process with the ultrasound agitation

Kobayashi, Fuyumi; Ishii, Junichi; Shirahashi, Koichi; Umeda, Miki; Sakuraba, Koichi

Kakuhan, Kongo Gijutsu To Toraburu Taisaku, p.341 - 344, 2014/10

The silver mediated electrochemical oxidation (Ag/MEO) process with the ultrasound agitation has been developed for the purpose of the mineralization of organic wastes containing transuranium nuclides at the nuclear fuel reprocessing process. In the Ag/MEO process, organic solvents are decomposed by divalent silver cations under the relatively low temperature and the ambient pressure condition. The ultrasound agitation is effective in mixing the electrolytic solutions and the organic solvents, and is expected to promote the oxidation of the organic solvents. Therefore, the Ag/MEO process with the ultrasound agitation could be a candidate for the treatment of organic solvents. Destruction tests of TBP and dodecane by the Ag/MEO process were conducted to optimize some treatment conditions. Under optimized conditions, the destruction tests of kerosene and TODGA were carried out. It was confirmed that the Ag/MEO process is effective for the mineralization of these organic solvents.

JAEA Reports

Basic study on decontamination of TRU wastes with cerium mediated electrolytic oxidation method

Ishii, Junichi; Kobayashi, Fuyumi; Uchida, Shoji; Sumiya, Masato; Kida, Takashi; Shirahashi, Koichi; Umeda, Miki; Sakuraba, Koichi

JAEA-Technology 2009-068, 20 Pages, 2010/03

JAEA-Technology-2009-068.pdf:2.49MB

At Nuclear Fuel Cycle Safety Engineering Research Facility, the cerium mediated electrolytic oxidation method which is a decontamination technique to decrease the radioactivity of TRU wastes to the clearance-level has been developed for the effective reduction of TRU wastes generated from the decommissioning of a nuclear fuel reprocessing facility and so on. This method corrodes the oxide layer and the surface of metallic TRU metal wastes by the strong oxidation power of Ce$$^{4+}$$ in nitric acid. In this study, parameter tests were conducted to optimize the solution condition of Ce$$^{3+}$$ initial concentrations and nitric acid concentrations. The target corrosion rate of metallic TRU wastes set to be 2$$sim$$4$$ mu$$m/h for the practical use of this method. Under the optimized solution condition, a dissolution test of stainless steel simulating wastes was carried out. From the result of the dissolution test, the average corrosion rate was 3.3 $$mu$$m/h during the test time of 90 hours. Based on the supposition that the corrosion depth of metallic TRU wastes was 20 $$mu$$m enough to achieve the clearance-level, the treatment time for the decontamination was about 6 hours. It was confirmed from the result that the decontamination could be performed within one day and the decontamination solution could repeatedly reuse 15 times.

JAEA Reports

Basic study on the mineralization of organic solvents by the silver mediated electrochemical oxidation process with the ultrasound agitation

Kobayashi, Fuyumi; Ishii, Junichi; Shirahashi, Koichi; Umeda, Miki; Sakuraba, Koichi

JAEA-Technology 2009-056, 16 Pages, 2009/11

JAEA-Technology-2009-056.pdf:1.53MB

The silver mediated electrochemical oxidation (Ag/MEO) process with the ultrasound agitation has been developed for the purpose of the mineralization of organic wastes containing transuranium nuclides at the nuclear fuel reprocessing process. In the Ag/MEO process, organic solvents are decomposed by divalent silver cations under the relatively low temperature and the ambient pressure condition. The ultrasound agitation is effective in mixing the electrolytic solutions and the organic solvents, and is expected to promote the oxidation of the organic solvents. Therefore, the Ag/MEO process with the ultrasound agitation could be a candidate for the treatment of organic solvents. Destruction tests of TBP and dodecane by the Ag/MEO process were conducted to optimize some treatment conditions. Under optimized conditions, the destruction tests of kerosene and TODGA were carried out. It was confirmed that the Ag/MEO process is effective for the mineralization of these organic solvents.

Journal Articles

Operation and management of STACY experiment using Pseudo-FPs-doped fuel

Izawa, Kazuhiko; Seki, Masakazu; Hirose, Hideyuki; Kaminaga, Jota; Aoyama, Yasuo; Yoshida, Hiroshi; Sono, Hiroki; Ogawa, Kazuhiko; Sakuraba, Koichi

UTNL-R-0453, p.9_1 - 9_10, 2006/03

no abstracts in English

Journal Articles

Report on investigation of unexpected reactor shutdown of the TRACY facility; Cause and countermeasures

Sono, Hiroki; Tsukamoto, Michio; Aizawa, Eiju; Takeuchi, Masaki; Fukaya, Yuji; Iseda, Hirokatsu*; Ogawa, Kazuhiko; Sakuraba, Koichi; Tonoike, Kotaro

UTNL-R-0446, p.3_1 - 3_10, 2005/03

This report describes an investigation and countermeasures of the unexpected reactor shutdown of the TRACY facility at the Japan Atomic Energy Research Institute on June 17, 2004, caused by a malfunction of a safety rod of the facility. As a result of the investigation, the principal cause of the malfunction was ascribed to a drop in attraction of a binding magnet for the safety rod by a small piece of a foreign material. The following countermeasures were taken against its recurrence: prevention of incidence of foreign materials, reduction of the chance of intrusion of foreign materials into devices, and certain detection of foreign materials. This lesson learned through the experience is expected to be shared with the staffs concerned in reactor operation and maintenance.

JAEA Reports

Report of TRACY operation

Aizawa, Eiju; Ogawa, Kazuhiko; Sakuraba, Koichi; Tsukamoto, Michio; Sugawara, Susumu; Takeuchi, Masaki*; Miyauchi, Masakatsu; Yanagisawa, Hiroshi; Ono, Akio

JAERI-Tech 2002-031, 120 Pages, 2002/03

JAERI-Tech-2002-031.pdf:4.32MB

TRACY (Transient Experiment Critical Facility) in NUCEF (Nuclear Safety Research Facility) is the pulse-type critical facility using uranyl nitrate solution which can carry out various supercritical experiments changing reactivity addition up to 3$.TRACY achieved its first criticality on 20th December 1995,and transient operations have been conducted Since1996.This report summarizes the operation data of 176 experiments from the first criticality to FY2000.

JAEA Reports

Annual report of STACY operation in FY. 2000; Experiments on neutron-interacting systems with two slab-shaped core tanks and 10% enriched uranyl nitrate solution, 2 (Contract research)

Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.

JAERI-Tech 2001-057, 54 Pages, 2001/09

JAERI-Tech-2001-057.pdf:4.28MB

no abstracts in English

Journal Articles

Development of solution behavior observation system under criticality accident conditions in TRACY

Ogawa, Kazuhiko; Morita, Toshio*; Yanagisawa, Hiroshi; Aizawa, Eiju; Sakuraba, Koichi; Sugawara, Susumu; Ono, Akio

Journal of Nuclear Science and Technology, 37(12), p.1088 - 1097, 2000/12

no abstracts in English

JAEA Reports

Annual report of STACY operation in FY.1999; Experiments on two unit neutron-interacting system with slab-shaped core tanks and 10% enriched uranyl nitrate solutions, 1 (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Kaminaga, Jota*; Myomae, Tomoki*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; et al.

JAERI-Tech 2000-059, 46 Pages, 2000/11

JAERI-Tech-2000-059.pdf:2.86MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1998, 2; 800mm-diameter cylindrical core$$cdot$$10% enriched uranyl nitrate solution (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Nagasawa, Makoto*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Yamane, Yuichi; Ono, Akio

JAERI-Tech 2000-013, p.57 - 0, 2000/03

JAERI-Tech-2000-013.pdf:2.43MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1998, 1; 280mm thickness slab core$$cdot$$10% enriched uranyl nitrate solution (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Nagasawa, Makoto*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Kikuchi, Tsukasa; Ono, Akio

JAERI-Tech 99-084, p.54 - 0, 1999/12

JAERI-Tech-99-084.pdf:2.7MB

no abstracts in English

Journal Articles

Measurement of the power profile during nuclear excursions initiated by various reactivity additions using TRACY

; Nakajima, Ken; Yanagisawa, Hiroshi; ; ; *; *; Sakuraba, Koichi; Ono, Akio

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 3, p.1277 - 1285, 1999/00

no abstracts in English

Journal Articles

Experiments on transient behavior of a low-enriched uranyl nitrate solution system with TRACY to study hypothetical criticality accidents in reprocessing plants

Yanagisawa, Hiroshi; Nakajima, Ken; ; ; Sakuraba, Koichi; ; *; *; Sonoda, Takashi; Ono, Akio

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 2, p.900 - 906, 1999/00

no abstracts in English

JAEA Reports

Construction of STACY(Static Experiment Critical Facility)

Murakami, Kiyonobu; ; Hirose, Hideyuki; ; *; *; Sakuraba, Koichi; ; ; *; et al.

JAERI-Tech 98-033, 70 Pages, 1998/08

JAERI-Tech-98-033.pdf:2.25MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1997; 280mm thickness slab core・10% enriched uranyl nitrate solution (Contract research)

; ; Hirose, Hideyuki; *; *; Murakami, Kiyonobu; Takahashi, Tsukasa; Sakuraba, Koichi; Miyauchi, Masakatsu; ; et al.

JAERI-Tech 98-023, 66 Pages, 1998/06

JAERI-Tech-98-023.pdf:2.89MB

no abstracts in English

JAEA Reports

Improvement of fuel sampling device for STACY and TRACY

Hirose, Hideyuki; Sakuraba, Koichi; ; ; *; *; ; ; ; Miyauchi, Masakatsu; et al.

JAERI-Tech 98-015, 52 Pages, 1998/05

JAERI-Tech-98-015.pdf:1.68MB

no abstracts in English

JAEA Reports

Seismic design of reactors in NUCEF

*; *; *; *; ; Sakuraba, Koichi; Izawa, Naoki; Takeshita, Isao

JAERI-Tech 97-010, 276 Pages, 1997/03

JAERI-Tech-97-010.pdf:8.45MB

no abstracts in English

JAEA Reports

Annual report of STACY in 1995; 600mm diameter cylindrical core and 10% enriched uranyl nitrate solution

; ; Hirose, Hideyuki; *; *; Ono, Akio; Sakuraba, Koichi; Izawa, Naoki; Tonoike, Kotaro; *; et al.

JAERI-Tech 97-005, 107 Pages, 1997/03

JAERI-Tech-97-005.pdf:3.26MB

no abstracts in English

Journal Articles

Experimental study on criticality accidents using the TRACY

Nakajima, Ken; ; ; ; *; Sakuraba, Koichi; Ono, Akio

PHYSOR 96: Int. Conf. on the Physics of Reactors, 4, p.L83 - L92, 1996/00

no abstracts in English

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