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Oral presentation

Corrosion behavior of simulated waste glass in synthetic seawater

Maeda, Toshikatsu; Omori, Hiroyuki*

no journal, , 

no abstracts in English

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

Decommissioning Project of Uranium Conversion Plant, 1; Decommissioning result (The First half of F.Y. 2010)

Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake

no journal, , 

no abstracts in English

Oral presentation

Status of development of a 500 kV photo-cathode electron gun for the next generation ERL light sources

Nishimori, Nobuyuki; Nagai, Ryoji; Hajima, Ryoichi; Yamamoto, Masahiro*; Miyajima, Tsukasa*; Honda, Yosuke*; Kuriki, Masao*; Iijima, Hokuto*; Kuwahara, Makoto*; Okumi, Shoji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Development of construction methods of a drift to be reduction of amount of cement use, 10; Study on bending properties of the rock segment using low alkaline mortar

Tada, Hiroyuki*; Saito, Akira*; Nakaya, Atsushi*; Kumasaka, Hiroo*; Hayashi, Katsuhiko; Noguchi, Akira; Kishi, Hirokazu; Nakama, Shigeo

no journal, , 

Bending test of the segmental rings consist of staggered pieces of rocks bonded by low-pH mortar is conducted in order to identify the mechanical properties of rock segmental rings comparing with parallel arrangement. As a result, it was found that the maximum load was reached at 130 to 210 kN in the positive bending tests for staggered rock blocks, lower than 210 to 270 kN for rock blocks arranged in parallel. In the negative bending tests, on the other hand, the maximum load was reached at 30 to 40 kN, lower than a maximum load of 40 kN for the rock blocks arranged in parallel. The results thus varied. Cracks occurred along the interface between the rock block and mortar in the specimen for the blocks arranged in parallel. For the staggered rock blocks, cracks penetrated through the mortar and the rock block near the point of loading in the specimen. Thus, it was confirmed that cracking occurred in different manners.

Oral presentation

Mizunami Underground Research Laboratory Project, 1; Status of construction and research & development

Sato, Toshinori; Saegusa, Hiromitsu; Hama, Katsuhiro; Ogata, Nobuhisa; Mikake, Shinichiro

no journal, , 

Japan Atomic Energy Agency has been conducting Mizunami Underground Research Laboratory (URL) Project aiming to establish a firm scientific basis for safe geological disposal including: establishing investigation techniques, analysis and assessment of the deep geological environment, and applicability assessment of engineering technologies for designing and constructing underground facilities. This report describes the construction status of the URL, the results of deep geological investigations carried out, and the future plan of this project.

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi; Terai, Takayuki*; et al.

no journal, , 

Three and half years has been passed from the start of IFMIF/EVEDA. In IFMIF/EVEDA, tasks for Lithium Target System consists of 5 validation tasks (LF1-5) and a design task (ED3), and are shared by Japan and Europe. Japan is covering the construction and operation of EVEDA Li Test Loop (LF1), diagnostics (LF2), purification system (LF4), remote handling system (LF5) and engineering design (ED3) with the contribution from universities. The present status of these tasks will be reported in the conference.

Oral presentation

Evaluation of nuclear data on Pd isotopes

Terada, Kazushi*; Iwamoto, Nobuyuki

no journal, , 

no abstracts in English

Oral presentation

Investigation of HTO transport in the environment using SPEEDI-MP's coupling calculation for material circulation

Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki

no journal, , 

no abstracts in English

Oral presentation

Fundamental study on electrolyte recycle process by phosphate conversion technique, 11; Evaluation of phosphate conversion reaction based on the heat capacity

Kofuji, Hirohide; Sawada, Nobuyuki*; Sasaki, Kazuya*; Amamoto, Ippei; Myochin, Munetaka; Suzuki, Akihiro*; Terai, Takayuki*

no journal, , 

The phosphate conversion process has been studied for reuse of spent electrolyte generated from pyrochemical reprocessing. As the fundamental information of thermodynamic data, heat capacities of some kind of phosphate were measured and phosphate conversion reactions were discussed based on such thermodynamic data.

Oral presentation

Mizunami Underground Research Laboratory Project; Achievements of geological environmental investigation and support to implementer and regulator

Kunimaru, Takanori; Hama, Katsuhiro; Ogata, Nobuhisa; Sato, Toshinori; Saegusa, Hiromitsu; Tsuruta, Tadahiko; Takeuchi, Ryuji; Matsuoka, Toshiyuki; Mizuno, Takashi

no journal, , 

no abstracts in English

Oral presentation

Outline of FUGEN decommissioning project

Ozaki, Shinji

no journal, , 

no abstracts in English

Oral presentation

Sorption site capacities for Cs on the sedimentary rock in Horonobe area

Ishidera, Takamitsu; Kurosawa, Seiichi*; Kibe, Satoshi*; Ouchi, Yuji*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Fabrication of metallic fuel for irradiation test at JOYO, 4; Fabrication of metallic fuel elements

Nakamura, Kinya*; Kikuchi, Hironobu; Ogata, Takanari*; Iwai, Takashi; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori

no journal, , 

Irradiation test of metallic fuel at fast test reactor JOYO is planned. By using techniques of casting, fabrication, analysis and inspection, metallic fuel elements were made for the first time in Japan. In this paper, fabrication technique of metallic fuel elements is reported. After filling up thermal bond (Na), a reflector element, a thermal shelter element and a fuel slug, the upper plug was welded. Sodium bonding treatment was carried out by vibrating the fuel element under heating. By inspection, it was confirmed that the specifications were satisfied.

Oral presentation

Feasibility study on material creation and new-type fuel utilization by using HTTR, 1; Outline of feasibility study

Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*

no journal, , 

As collaborative research project by Japan Atomic Energy Agency, Toyota Tsusho Corporation and Nuclear Fuel Industries, Ltd., new utilizations of HTGR and new R&D of a cooperative relationship between car industries and HTGR are presented. Specifically, we showed the results of feasibility study on material creation and new-type fuel utilization by using HTTR.

267 (Records 1-20 displayed on this page)