Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), p.1554 - 1559, 2013/09

Development of short stroke shearing technology for FBR fuel pin

Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*

Journal of Power and Energy Systems (Internet), 4(1), p.244 - 251, 2010/04

https://doi.org/10.1299/jpes.4.244

no abstracts in English

Conceptual design study of the powdered fuel dissolver

Washiya, Tadahiro; Higuchi, Hidetoshi; Sano, Yuichi; Aose, Shinichi

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13), P. 330, 2005/05

Japan Nuclear Cycle Development Institute (JNC) has been developing the crystallization technology for the advanced aqueous reprocessing plant to realize the FBR fuel cycle. The crystallization process is applied in front of the extraction process for removing large amount of uranium and reducing the throughput of extraction process. The crystallization process requires high concentrated dissolution (500g-HM/L) to mitigate the cooling conditions. The powdered fuel dissolution is a promising technology to obtain the high concentrated dissolution. Hot experiments of the powdered fuel dissolution were carried out at CPF to verify the dissolution speed and characteristics. As result, the speed is ten times faster than conventional sheared fuel. For the powdered fuel dissolution, particle handling is a key issue to prevent piling up of the fuel particles on the dissolver bottom and elutriation rate to the off gas system. In this paper, functional requirements and subjects for the powdered fuel dissolution were discussed. And an innovative dissolver design based on the cylindrical stirring type dissolver was proposed for reliable continuous dissolver system with the powdered fuel. Some engineering scale test and computer code evaluations were carried out to verify the dynamic performance of simulated fuel particles and water in the dissolver design.

Determination of neptunium in neptunium-uranium-plutonium mixed oxide fuel by spectrophotometry.

; ; ; ; ; ;

JNC TN8400 2001-026, 29 Pages, 2001/12

JNC-TN8400-2001-026.pdf:0.99MB

The measurement condition by spectrophotometry was evaluated to measure Np content in MOX fuel containing Np. The Np concentration was obtained by measuring the 727nm absorption peak, after the valence of Np in the sample solution was adjusted to the Np(Ⅳ). The calibration curve showed the linearity up to Np concentration 0.8mg/ml. Though Pu and U quantity were respectively added to the Np solution to 30 times and 60 times of Np concentration, there was no effect to the Np analysis. By using this method, relative standard deviation (RSD) of the analyzed values of Np content for 2%Np - MOX fuel was about 4%. In addition, It was confirmed that the Np content could be measured without separating Np from Pu and U. This method can be sufficiently applied as a quick simple method to analyze Np content in MOX fuel containing Np.

Development of FBR fuel disassembly and pin bundle chopping technology, 10; Fundamental performance evaluation by the fuel disassembly test system

Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*

no journal, , 

no abstracts in English

Development of mechanical disassembly and shearing systems for FBR spent fuel in FaCT project

Washiya, Tadahiro; Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Kobayashi, Tsuguyuki*; Koyama, Tomozo; Tasaka, Masayuki*

no journal, , 

JAEA have been developing a reliable fuel disassembly and shearing systems in cooperation with Japan Atomic Power Company (JAPC). We proposed a disassembly system utilizing mechanical cutting and pulling method. We designed and fabricated an engineering-scale test device, and confirming the system performance by using the simulated fuel assembly. And we proposed new shearing procedure as short-stroke cutting to provide highly fragmented fuel to realize efficient fuel dissolution required from the uranium crystallization process. We designed and fabricated the fuel transfer device and carried out some experiment to confirm that the fuel fragmentation rate and shared stroke was chosen to be 1 cm. In this paper, we will report the latest experiment for these systems.

Development of FBR fuel disassembly and pin bundle shearing technology, 13; Mechanical disassembly system test using simulated fuel assembly

Kitagaki, Toru; Higuchi, Hidetoshi; Takeuchi, Masayuki; Washiya, Tadahiro; Kawabe, Yukinari*; Kobayashi, Tsuguyuki*

no journal, , 

no abstracts in English

FaCT phase-I evaluation on advanced aqueous reprocessing process, 2; Disassembly and shearing technologies for FBR fuel

Kitagaki, Toru; Takeuchi, Masayuki; Higuchi, Hidetoshi; Wakui, Ryohei; Koizumi, Kenji; Suganuma, Takashi; Washiya, Tadahiro

no journal, , 

no abstracts in English

Basic tests of fiber laser for wrapper tube cutting

Wakui, Ryohei; Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Takeuchi, Masayuki; Washiya, Tadahiro

no journal, , 

no abstracts in English

Selection of fuel-debris properties required for defueling work at post severe accident

Ikeuchi, Hirotomo; Kitagaki, Toru; Wakui, Ryohei; Higuchi, Hidetoshi; Koizumi, Kenji; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro

no journal, ,