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Cause Investigation Team for the PFRF Contamination Incident
JAEA-Review 2017-038, 83 Pages, 2018/03
The contaminated accident occurred at Plutonium Fuel Research Facility on June, 2017. The PVC bag packaging in a fuel storage container burst when a worker opened the lid, and a part of contents (uranium and plutonium) was spattered over the room. In order to clarify the cause of the burst, the Cause Unfolding Team collected information concerning characteristics of the contents from any past records and interview. And then we observed and analyzed the contents in a glove box. We also performed experiments on radiolysis of organic materials, degradation of PVC bag by radiation, and PVC bag burst. Based on fault tree analysis, finally we concluded that the main gas generation source was alpha radiolysis of the epoxy resin mixed with the fuel powder. We hope that the calculation procedures for the gas generation and the inner pressure transition described in this report can be useful reference for the management of fuel storage in other facilities.
Mine, Tatsuya*; Mihara, Morihiro;
JNC TN8430 2000-010, 27 Pages, 2000/07
In the geological disposal system of the radioactive wastes, gas generation by microorganism could be significant for the assessment of this system, because organic material included in groundwater, buffer material and wastes might serve as carbon sources for microorganisms. In this study, gas generation tests using microorganisms were carried out under anaerobic condition. The amount of methane and carbon dioxide that were generated by activity of Methane Producing Bacteria (MPB) were measured with humic acid, acetic acid and cellulose as carbon sources. The results showed that methane was not generated from humic acid by activity of MPB. However, in the case of using acetic acid and cellulose, methane was generated, but at high pH condition (pH=10), the amount of generated methane was lower than at low pH (pH=7). It was not clear whether the pH would affect the amount of generated carbon dioxide.
Hashizume, Shuji*; Matsumoto, Junko; Bamba, Tsunetaka
Genshiryoku Bakkuendo Kenkyu, 6(1), p.101 - 106, 1999/12
no abstracts in English
Morita, Yosuke; Yagi, Toshiaki; *
Denki Gakkai Yuden, Zetsuen Zairyo Kenkyukai Shiryo; DEI-99-13, p.27 - 30, 1999/02
no abstracts in English
G.Wu*; Katsumura, Yosuke*; Kudo, Hisaaki; Morita, Yosuke; Seguchi, Tadao
J. Polym. Sci., Part A, 37(10), p.1541 - 1548, 1999/00
no abstracts in English
Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka
Genshiryoku Bakkuendo Kenkyu, 5(1), p.45 - 49, 1998/08
no abstracts in English
M.Celina*; Kudo, Hisaaki; T.J.Renk*; K.T.Gillen*; R.L.Clough*
Radiation Physics and Chemistry, 51(2), p.191 - 194, 1998/00
no abstracts in English
Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka
Zairyo To Kankyo, 47(10), p.638 - 644, 1998/00
no abstracts in English
Wada, Ryutaro*; Nishimura, Tsutomu*; Fujiwara, Kazuo*; *; *
PNC TJ1058 97-003, 33 Pages, 1997/03
None
Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka
JAERI-Review 96-013, 25 Pages, 1996/10
no abstracts in English
Kudo, Hisaaki; Kasai, Noboru; Sasuga, Tsuneo; Seguchi, Tadao
Radiation Physics and Chemistry, 48(1), p.95 - 100, 1996/00
Times Cited Count:18 Percentile:80.29(Chemistry, Physical)no abstracts in English
Kudo, Hisaaki; Kasai, Noboru; Sasuga, Tsuneo; Seguchi, Tadao
Radiation Physics and Chemistry, 48(3), p.695 - 696, 1996/00
Times Cited Count:2 Percentile:24.74(Chemistry, Physical)no abstracts in English
*; *; *; Yagi, Toshiaki; Seguchi, Tadao
Mitsubishi Densen Kogyo Jiho, (87), p.45 - 49, 1994/04
no abstracts in English
; Yokouchi, Iichiro;
Shitsuryo Bunseki, 22(4), p.275 - 280, 1974/04
no abstracts in English
Arai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Nishimura, Yuki; Shimada, Taro; Takeda, Seiji
no journal, ,
no abstracts in English
Arai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
Multi-Radionuclide Removal System (MRRS) has been utilized for decontaminate of the radioactive contaminated water in Fukushima Daiichi Nuclear Power Station (1F). The secondary wastes including iron hydroxide, carbonate and used adsorbents are packed in the High Integrity Container (HIC). It was reported that the radioactive liquid was overflowed in several HICs. This phenomenon was only observed in HICs containing the carbonate slurry waste. It was inferred that volume increase of wastes due to gas generation caused by the water radiolysis. However, the gas generation behavior was not well known. Therefore, it is important to investigate gas generation behavior of radioactive carbonate slurry waste. Ten ml of the carbonate slurry waste was put into the sealing vial. After standing sample for certain duration, concentration of hydrogen was measured by gas-chromatography. Total amounts of hydrogen gas produced from the slurry was proportionally increased with time. Measured G-value was equivalent to the theoretical G value. This result showed that hydrogen gas generated by water radiolysis in radioactive carbonate slurry waste.
Motooka, Takafumi; Yamagishi, Isao; Nagaishi, Ryuji
no journal, ,
Simulated carbonate slurry was irradiated by -rays to obtain the basic knowledge of the cause of stagnant water over the High Integrity Container. The rise in water level, air bubbles in the slurry, and supernatant were observed when the carbonate slurry with 95 g/L density was irradiated by -rays at 8.5 kGy/h. It was suggested that the cause of the rise in liquid level was regarded as the volume expansion by the gas retention in carbonate slurry.
Meguro, Yoshihiro
no journal, ,
From contaminated water treatment systems at Fukushima Daiichi Nuclear Power Station, various radioactive wastes have been generated and stored. Especially, concentrated waste liquid, iron hydroxide slurry and carbonate slurry contain high concentration of strontium-90 and a large amount of water and sea water components. Therefore, when these wastes are stored for a long period, the risk of leakage of radioactive waste due to corrosion of storage containers and burning of hydrogen gas generated by radiolysis increases. In this research, we are developing technology to solidify these wastes using phosphate solidification materials. We are trying suppressing the generation of hydrogen gas by performing heat dehydration at the time of curing of the solidified material and to fix Sr and seawater component by making poorly water-soluble stable compounds.