Chemical forms of uranium evaluated by thermodynamic calculation associated with distribution of core materials in the damaged reactor pressure vessel

Autor: Hirotomo Ikeuchi, Tadahiro Washiya, Kimihiko Yano

Publikováno v: Journal of Nuclear Science and Technology. 57:704-718

To suggest efficient process of the fuel debris treatment after the retrieval from the Fukushima Daiichi Nuclear Power Plant (1F), thorough investigation is indispensable on potential source of U in the fuel debris. The present study aims to estimate

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a0ecfb21253d9558455fac581c59f283
https://doi.org/10.1080/00223131.2020.1720844

Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

Autor: Hirotomo Ikeuchi, Sylvie Dubois, Cédric David, Tadahiro Washiya, Toru Kitagaki, Akira Nakayoshi, Pascal Piluso, Véronique Testud, Viviane Bouyer, Josselin Gousseau, Julien Roger, Laurent Brissonneau

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2020, 528, pp.151860. ⟨10.1016/j.jnucmat.2019.151860⟩
Journal of Nuclear Materials, 2020, 528, pp.151860. ⟨10.1016/j.jnucmat.2019.151860⟩

International audience; In the framework of JAEA-CEA collaboration, experimental studies have been conducted for estimating the material characteristics of corium debris representative of the Fukushima Daiichi nuclear damaged plants. A test has been

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cfe4908122661952fe387ad1ec4e8023
https://hal-cea.archives-ouvertes.fr/cea-02535235

Characterization of the VULCANO test products for fuel debris removal from the Fukushima Daiichi Nuclear Power Plant

Autor: Hirotomo Ikeuchi, Brigitte Tormos, Kimihiko Yano, J. F. Haquet, Pascal Piluso, Toru Kitagaki, Tadahiro Washiya, Laurent Brissonneau, Hideki Ogino

Publikováno v: Progress in Nuclear Science and Technology. 5:217-220

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a95c7870e1e649056f273de16655e993
https://doi.org/10.15669/pnst.5.217

Dissolution behavior of (U,Zr)O2-based simulated fuel debris in nitric acid

Autor: Yasuo Nakajima, Naoya Kaji, Miho Ishihara, Kimihiko Yano, Tadahiro Washiya, Hirotomo Ikeuchi

Publikováno v: Journal of Nuclear Science and Technology. 51:996-1005

To explore the possibility of dissolving fuel debris into nitric acid as a potential pre-treatment for waste treatment in which the U and Pu are removed from the inventory, dissolution tests of U1−...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1052bdd0772b13a46a742ba8a837d203
https://doi.org/10.1080/00223131.2014.924445

Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal

Autor: Takahiro Chikazawa, Izumi Hirasawa, Tadahiro Washiya, Kazunori Nomura, Masaumi Nakahara

Publikováno v: Radiochimica Acta. 98:315-320

In order to examine the decontamination behavior of the Pu and fission products (FPs) that contained with the uranyl nitrate hexahydrate (UNH) crystals in the U crystallization process, experiments were carried out using mixed oxide (MOX) fuel dissol

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::230e086e625efadd7f64424cdeb78dff
https://doi.org/10.1524/ract.2010.1732