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Journal Articles

Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests

Tanaka, Kosuke; Sato, Isamu*; Onishi, Takashi; Ishikawa, Takashi; Hirosawa, Takashi; Katsuyama, Kozo; Seino, Hiroshi; Ohno, Shuji; Hamada, Hirotsugu; Tokoro, Daishiro*; et al.

Journal of Nuclear Materials, 536, p.152119_1 - 152119_8, 2020/08

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

In order to obtain the release rate coefficients from fuels for fast reactors (FRs), heating tests and the subsequent analyses of the fission products (FPs) and actinides that are released were carried out using samples of uranium-plutonium mixed oxide (MOX) fuel pellets irradiated at the experimental fast reactor Joyo. Three heating tests targeting temperatures of 2773, 2973 and 3173 K were conducted using an FP release behavior test apparatus equipped with a high-frequency induction furnace and solid FP sampling systems consisting of a thermal gradient tube (TGT) and filters. Irradiated fuel pellets were placed into a tungsten crucible, then loaded into the induction furnace. The temperature was raised continuously at a heating rate of 10 K/s to the targeted temperature and maintained for 500 s in a flowing argon gas atmosphere. The FPs and actinides released from the MOX fuels and deposited in the TGT and filters were quantified by gamma-ray spectrometry and inductively coupled plasma mass spectrometry (ICP-MS) analysis. Based on the analysis, the release rates of radionuclides from MOX fuels for FR were obtained and compared with literature data for light water reactor (LWR) fuels. The release rate coefficients of FPs obtained in this study were found to be similar to or lower than the literature values for LWR fuels. It was also found that the release rate coefficient data for actinides were within the range of variation of literature values for LWR fuels.

Journal Articles

Adsorption of platinum-group metals and molybdenum onto aluminum ferrocyanide in spent fuel solution

Onishi, Takashi; Sekioka, Ken*; Suto, Mitsuo*; Tanaka, Kosuke; Koyama, Shinichi; Inaba, Yusuke*; Takahashi, Hideharu*; Harigai, Miki*; Takeshita, Kenji*

Energy Procedia, 131, p.151 - 156, 2017/12

 Times Cited Count:6 Percentile:97.85

no abstracts in English

JAEA Reports

Penetration behavior of solution containing radioactive nuclides into floor and wall materials

Usuki, Toshiyuki; Sato, Isamu; Suto, Mitsuo; Maeda, Koji; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Sekioka, Ken*; Ishigamori, Toshio*

JAEA-Testing 2014-001, 29 Pages, 2014/05

JAEA-Testing-2014-001.pdf:5.33MB

The penetration tests with solution containing radioactive nuclides were experimented to understand basic data for floor and wall materials of Fukushima Daiichi reactor buildings. The solution prepared from irradiated fuels was used as solution containing radioactive nuclides. The solution was applied to surface of epoxy paint, dried concrete and mortar used as specimens. Dose-rate profiles of direction of depth were given by radiation measurement and grinding of the specimens. The penetrations of radioactive nuclides for epoxy paint specimens were not clearly observed and the penetration depths would be within 0.4 mm. The penetrations of radioactive nuclides for dried concrete specimens proceeded. The penetration rates were substantially decreased when 16 days have elapsed from start. The dose rates of penetrated dried concrete specimens were reduced to background by grinding-2.0 mm. $$gamma$$-ray spectrometry measurement showed that penetration behavior of near surface concrete are different among nuclides and the penetration behavior of radioactive nuclides into dried concrete and mortar materials through solution is similar to migration behavior of ions into those water-saturated materials.

JAEA Reports

Chemical composition of artificial seawater after leaching tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*; Obayashi, Hiroshi; Koyama, Shinichi

JAEA-Research 2013-036, 31 Pages, 2013/12

JAEA-Research-2013-036.pdf:3.31MB

In the accident of Fukushima Daiichi NPPs, the water ingress was performed in order to decrease the reactor temperature. At that time, sea water was temporarily used as a coolant and the water contacted with nuclear fuel directly. It can be supposed that fission products (FP) were easily migrated from the fuel to sea water in this situation and that affect the water quality. The knowledge of leaching behavior, therefore, is necessary for evaluating the integrity of reactor component materials such as steels for pressure containment vessel and for reactor vessel. In order to obtain the fundamental knowledge for leaching behavior of FP in the hot sea water, the leaching tests of irradiated fuel were performed and the leachates were subjected to chemical analysis. It is found that he leaching rate of each nuclides obtained in this study were similar to that of the leaching results simulating the underground water.

Oral presentation

Uncertainty analysis for long-term dissolution scenario of waste glass

Takeda, Seiji; Sekioka, Yasushi; Yotsuji, Kenji; Kimura, Hideo; Inagaki, Yaohiro*

no journal, , 

no abstracts in English

Oral presentation

High linear power irradiation tests with Am-MOX fuels, 6; Burnup measurement and evaluation of irradiation condition

Sudo, Mitsuo; Obayashi, Hiroshi; Koyama, Shinichi; Maeda, Shigetaka; Tanaka, Kenya; Sekioka, Ken*

no journal, , 

I carried out the burn-up measurement (Nd monitor method) by the chemical analysis to evaluate a short-term irradiation condition of the "Monju" specifications fuel which contained Am irradiated in "Joyo".

Oral presentation

Blanket fuel with high proliferation resistance in fast breeder reactor, 8; Experimental analysis of irradiated Am sample in JOYO, 1

Onishi, Takashi; Sudo, Mitsuo; Koyama, Shinichi; Tanaka, Kenya; Sekioka, Ken*; Shiba, Tomooki*; Sagara, Hiroshi*; Saito, Masaki*

no journal, , 

In order to develop the high proliferation resistance fuel for fast breeder reactor, plutonium production/incineration behavior of americium samples irradiated in fast reactor "JOYO" was evaluated.

Oral presentation

Blanket fuel with high proliferation resistance in fast breeder reactor, 9; Experimental analysis of irradiated U sample in JOYO, 3

Onishi, Takashi; Sudo, Mitsuo; Koyama, Shinichi; Sekioka, Ken*; Shiba, Tomooki*; Sagara, Hiroshi*; Saito, Masaki*

no journal, , 

In order to develop blanket fuel with high proliferation resistance in fast breeder reactor, production and incineration behavior of Pu in U samples irradiated in fast experimental reactor JOYO were evaluated.

Oral presentation

Development of extraction chromatographic agent immobilizing TPEN-gels for separation of minor actinides, 3; Recovery of mnor actinide from the spent fuel

Suto, Mitsuo; Obayashi, Hiroshi; Koyama, Shinichi; Sekioka, Ken*; Takeshita, Kenji*; Inaba, Yusuke*; Ogata, Takeshi*; Oaki, Hiroshi*

no journal, , 

no abstracts in English

Oral presentation

Recovery of Pt groups metals by xerogel enclosing insoluble ferrocyanide compounds

Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Sekioka, Ken*; Ishigamori, Toshio*; Mimura, Hitoshi*

no journal, , 

As part of a development of nuclides separation process by using highly-functional xerogels, xerogels including insoluble ferrocyanide compounds were prepared for separation of Pt group metals. Adsorption and elution behaviors of Pt group metals were investigated in simulated high level radioactive liquid waste. Recovery of palladium was also conducted by a thermal decomposition and digestion method.

Oral presentation

Decontamination experiment for floor of Fukushima Dai-ichi Reactor Buildings, 2; Penetration behavior of simulated-contaminated water into floor and wall materials

Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of selective separation method of nuclear rare metal by highly-functional xerogel, 1; Separation of platinum groups

Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Ishigamori, Toshio*; Sekioka, Ken*; Mimura, Hitoshi*; Kawamura, Takuya*; Sugai, Hiroshi*

no journal, , 

As part of a development of nuclides separation process by using highly-functional xerogels, xerogels including insoluble ferrocyanide compounds were prepared for separation of Pt group metals. Adsorption and elution behaviors of Pt group metals were investigated in simulated high level radioactive liquid waste.

Oral presentation

Separation of MA and Ln by extraction chromatography using functional gel copolymerized with multidentate inclusion ligands, 3; Recovery of minor actinide from the spent fuel

Suto, Mitsuo; Obayashi, Hiroshi; Koyama, Shinichi; Sekioka, Ken*; Takeshita, Kenji*; Inaba, Yusuke*; Ogata, Takeshi*; Oaki, Hiroshi*

no journal, , 

no abstracts in English

Oral presentation

Penetration behavior of a solution containing radioactive nuclides into concrete and epoxy resin paint

Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.

no journal, , 

no abstracts in English

Oral presentation

Chemical composition of artificial seawater after immersion tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*

no journal, , 

Chemical analysis of artificial seawater after immersion tests of irradiated fuel was carried out.

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 2; Effects of a control material of boron for FP transport behavior

Sato, Isamu; Onishi, Takashi; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Ishigamori, Toshio*; Seki, Takayuki*; Shinada, Masanori*; et al.

no journal, , 

As a material simulating FP, CsI was heated and evaporated to be decomposited on the surface of a tube having a temperature gradient. Gaseous B$$_{2}$$O$$_{3}$$ made by heating it at higher temperature was react with CsI decomposited on the surface, and then the boron effects for decomposition and migration behavior of Cs and I were observed. Consequently, it was indicated that boron vapor could strip decomposited CsI to make it gaseous species again and then the guseous CsI could move to the colder position.

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 6; Deposition behavior of FP released from irradiated fuel during the heating test

Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Onishi, Takashi; Suto, Mitsuo; Miwa, Shuhei; Osaka, Masahiko; Koyama, Shinichi; Seki, Takayuki*; Shinada, Masanori*; et al.

no journal, , 

In order to evaluate chemical forms of deposited fission products, $$gamma$$ ray spectrometry, macroscopic observation, XRD, ICP-MS analysis were performed in the specimens of sampling parts after a heating test of a fuel which was irradiated at FUGEN.

Oral presentation

Release behavior of radioactive materials from over-heated fuels for fast reactor, 1; Heating test

Ishikawa, Takashi; Tanaka, Kosuke; Sato, Isamu*; Onishi, Takashi; Hirosawa, Takashi; Seino, Hiroshi; Ohno, Shuji; Hamada, Hirotsugu; Tokoro, Daishiro*; Sekioka, Ken*; et al.

no journal, , 

no abstracts in English

Oral presentation

Release behavior of radioactive materials from over-heated fuels for fast reactor, 2 Analysis of released nuclides

Onishi, Takashi; Tanaka, Kosuke; Sato, Isamu*; Ishikawa, Takashi; Hirosawa, Takashi; Katsuyama, Kozo; Seino, Hiroshi; Ohno, Shuji; Hamada, Hirotsugu; Tokoro, Daishiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Release behavior of radioactive materials from over-heated fuels for fast reactor, 3 Evaluation of fractional release rate

Tanaka, Kosuke; Sato, Isamu*; Onishi, Takashi; Ishikawa, Takashi; Hirosawa, Takashi; Katsuyama, Kozo; Seino, Hiroshi; Ohno, Shuji; Hamada, Hirotsugu; Tokoro, Daishiro*; et al.

no journal, , 

Fractional release rate was evaluated based on the results of chemical analysis of sampling parts on which released nuclides were deposited during the over-heating test of irradiated fuels in a fast reactor.

25 (Records 1-20 displayed on this page)