JOPSS - Search Results

Oral presentation

Dependence of the dissolution rate of compacted montmorillonite on OH $^{-}$ activity under highly alkaline conditions

Sawaguchi, Takuma; Kadowaki, Mitsushi*; Mukai, Masayuki; Tsukada, Manabu; Maeda, Toshikatsu; Tanaka, Tadao

no journal, ,

no abstracts in English

Oral presentation

Development on evaluation method for hydraulic conductivity of compacted bentonite under alkaline conditions, 1; Outline of long-term hydraulic conductivity experiments

Tsukada, Manabu; Kadowaki, Mitsushi*; Mukai, Masayuki; Sawaguchi, Takuma; Kataoka, Masaharu; Maeda, Toshikatsu; Tanaka, Tadao

no journal, ,

no abstracts in English

Oral presentation

Development of fuel handling system in FaCT project, 6; Safety study on JSFR fuel handling system

Chikazawa, Yoshitaka; Kato, Atsushi; Uzawa, Masayuki*; Tozawa, Katsuhiro*; Chishiro, Ryo*; Obata, Hiroyuki*; Nishiyama, Noboru

no journal, ,

no abstracts in English

Oral presentation

On the cell homogenization for a lattice composed of asymmetric unit cells

Chiba, Go; Van Rooijen, W. F. G.*

no journal, ,

A property of a lattice composed of asymmetric unit cells is investigated. It is shown that usual deterministic calculation procedure based on the unit cell homogenization works well even if the unit cell is asymmetric by considering a direction dependence of homogenized total cross sections.

Oral presentation

Source term evaluation in containment vessel during late phase of severe accident, 20; Modeling of organic iodide production in the containment

Moriyama, Kiyofumi; Chiba, Noriaki; Tashiro, Shinsuke; Nakamura, Hideo; Nakamura, Koichi*

no journal, ,

no abstracts in English

Oral presentation

Realistic evaluation of the containment source term during severe accidents, 6; Experiment and analysis on the volatile iodine release in the containment

Moriyama, Kiyofumi

no journal, ,

no abstracts in English

Oral presentation

Development on evaluation method for hydraulic conductivity of compacted bentonite under alkaline conditions, 2; Analysis using coupled mass-transport/chemical-reaction code

Kataoka, Masaharu; Mukai, Masayuki; Sawaguchi, Takuma; Tsukada, Manabu; Kadowaki, Mitsushi*; Maeda, Toshikatsu; Tanaka, Tadao

no journal, ,

no abstracts in English

Oral presentation

Core designs corresponding to progress in nuclear fuel cycle technologies and related infrastructure for Fast-spectrum Light Water Reactor (FLWR)

Uchikawa, Sadao; Nakano, Yoshihiro; Okubo, Tsutomu

no journal, ,

no abstracts in English

Oral presentation

Establishment of high-precision fluence derivation method for quasi-monoenergetic neutron calibration fields of high energy at TIARA

Shikaze, Yoshiaki; Tanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio

no journal, ,

no abstracts in English

Oral presentation

Status of theoretical investigation of surrogate reactions

Chiba, Satoshi; Ogata, Kazuyuki*; Hashimoto, Shintaro; Aritomo, Yoshihiro

no journal, ,

no abstracts in English

Oral presentation

Verification tests for clearance monitor at Fugen Decommissioning Engineering Center

Kawagoe, Shinji; Higashiura, Norikazu; Goto, Tetsuo*

no journal, ,

no abstracts in English

Oral presentation

Investigation of $^{99}$ Mo amount generated by irradiating natural Mo in JRR-3

Komeda, Masao; Hirose, Akira; Sorita, Takami; Wada, Shigeru; Ishikawa, Koji*

no journal, ,

no abstracts in English

Oral presentation

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

Ishii, Junichi; Kobayashi, Fuyumi; Uchida, Shoji; Sumiya, Masato; Umeda, Miki

no journal, ,

no abstracts in English

Oral presentation

Study on hydrogenation and radiation effects in Zr-Nb alloys; Development of an interatomic potential for Zr-H binary systems

Udagawa, Yutaka; Yamaguchi, Masatake; Abe, Hiroaki*; Sekimura, Naoto*

no journal, ,

no abstracts in English

Oral presentation

Basic study on system decontamination by iodine heptafluoride, 1; Estimation of deposition rate and mechanism based uranium enrichment plant operation data

Yokoyama, Kaoru; Hata, Haruhi; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*

no journal, ,

The decontamination technique using the iodine heptafluoride is known as a system decontamination technique of facilities like the uranium enrichment plant where the uranium hexafluoride was handled. In this report, the mechanism of the system decontamination using the iodine heptafluoride is clarified at a molecular level. The generation process of the uranium tetrafluoride is estimated using the plant operation data. In addition, the generation speed of the uranium tetrafluoride and the activation energy are of the uranium tetrafluoride and iodine heptafluoride reaction are estimated.

Oral presentation

Development of manufacturing technology for a large amount of $^{99m}$ Tc generated from natural-Mo(n,) $^{99}$ Mo, 4; Analysis in the verification test of the producing process of $^{99m}$ Tc milked from a highly radioactive $^{99}$ Mo

Sonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*

no journal, ,

no abstracts in English

Oral presentation

Development of pyro-chemical reprocessing technology using alkaline molybdate melt, 7; Measuring UO $_{2}$ $^{2+}$ /UO $_{2}$ $^{+}$ redox potential in Li $_{2}$ MoO $_{4}$ -Na $_{2}$ MoO $_{4}$ by absorption spectrometry

Nagai, Takayuki; Fukushima, Mineo; Myochin, Munetaka; Uehara, Akihiro*; Fujii, Toshiyuki*; Yamana, Hajimu*

no journal, ,

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 9; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*

no journal, ,

This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 7; Estimation of the amount of Pu in dissolution residue formed at highly concentrated condition

Ikeuchi, Hirotomo; Shibata, Atsuhiro; Ouchi, Shinichi; Katsurai, Kiyomichi; Sano, Yuichi; Washiya, Tadahiro

no journal, ,

no abstracts in English

Oral presentation

Corrosion behavior of simulated waste glass in synthetic seawater

Maeda, Toshikatsu; Omori, Hiroyuki*

no journal, ,

no abstracts in English

Presentation/Publication Type

Journal/Book Title

Meeting title

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Keyword

Language

Publication Year

Held year of conference

Dependence of the dissolution rate of compacted montmorillonite on OH $^{-}$ activity under highly alkaline conditions

Development on evaluation method for hydraulic conductivity of compacted bentonite under alkaline conditions, 1; Outline of long-term hydraulic conductivity experiments

Development of fuel handling system in FaCT project, 6; Safety study on JSFR fuel handling system

On the cell homogenization for a lattice composed of asymmetric unit cells

Source term evaluation in containment vessel during late phase of severe accident, 20; Modeling of organic iodide production in the containment

Realistic evaluation of the containment source term during severe accidents, 6; Experiment and analysis on the volatile iodine release in the containment

Development on evaluation method for hydraulic conductivity of compacted bentonite under alkaline conditions, 2; Analysis using coupled mass-transport/chemical-reaction code

Core designs corresponding to progress in nuclear fuel cycle technologies and related infrastructure for Fast-spectrum Light Water Reactor (FLWR)

Establishment of high-precision fluence derivation method for quasi-monoenergetic neutron calibration fields of high energy at TIARA

Status of theoretical investigation of surrogate reactions

Verification tests for clearance monitor at Fugen Decommissioning Engineering Center

Investigation of $^{99}$ Mo amount generated by irradiating natural Mo in JRR-3

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

Study on hydrogenation and radiation effects in Zr-Nb alloys; Development of an interatomic potential for Zr-H binary systems

Basic study on system decontamination by iodine heptafluoride, 1; Estimation of deposition rate and mechanism based uranium enrichment plant operation data

Development of manufacturing technology for a large amount of $^{99m}$ Tc generated from natural-Mo(n,) $^{99}$ Mo, 4; Analysis in the verification test of the producing process of $^{99m}$ Tc milked from a highly radioactive $^{99}$ Mo

Development of pyro-chemical reprocessing technology using alkaline molybdate melt, 7; Measuring UO $_{2}$ $^{2+}$ /UO $_{2}$ $^{+}$ redox potential in Li $_{2}$ MoO $_{4}$ -Na $_{2}$ MoO $_{4}$ by absorption spectrometry

Development of efficient dissolution technology for FBR MOX fuel, 9; Endurance test of the bearing for rotary dram type continuous dissolver

Development of efficient dissolution technology for FBR MOX fuel, 7; Estimation of the amount of Pu in dissolution residue formed at highly concentrated condition

Corrosion behavior of simulated waste glass in synthetic seawater