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Oral presentation

On performance experience and measurements with Ningyo Waste Assay System (NWAS)

Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi

no journal, , 

We developed uranium mass assay systems for 200-litter wastes drums applied neutron and $$gamma$$ measurements by NDA method. In this intermediate report we will describe measurement systems and trial data. The systems are composed of the 16 pieces of helium-3 proportional counters for neutron detection and a large sized NaI(Tl) scintillation detector for $$gamma$$-ray detection. The extensive testing trials using the calibrated uranium sources with different enrichment and some kinds of matrices in drums were performed. Through the one year testing the useful experiences of this system concerning neutron and $$gamma$$-ray measurements for uranium mass were obtained. Almost all instruments and software were so good performance as is designed. As the next step we are going to schedule to try measurements for actual wastes that are stored in the Uranium Refining and Conversion Plant at Ningyo-toge, and put practical uses near future. Our research was accomplished with the support of Los Alamos National Laboratory.

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.

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

Replacement of filter casing in the vessel ventilation of HAW storage process at the Tokai reprocessing plant

Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi

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

Proposal of a $$gamma$$-ray NDA experiment at the Compact ERL

Hajima, Ryoichi; Hayakawa, Takehito; Seya, Michio; Kawata, Hiroshi*; Kobayashi, Yukinori*; Urakawa, Junji*

no journal, , 

no abstracts in English

Oral presentation

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

Decommissioning project of uranium conversion plant, 2; The Feature of a secondary waste by dismantling, 2

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

no journal, , 

In the Decommissioning Project of Uranium Conversion Plant, we try that gather dismantling objects for a purpose by promotion of efficiency of work, SW (Secondary Waste) reduction to the exclusive area from 2009. About the feature of the SW generation, we weighed it against the results of 2008 when we didn't gather dismantling objects to the exclusive area. The SW generation per dismantling objects 1 ton was "non gathered case" = 51.3 kg and "gathered case" = 38.3 kg. We confirmed a reduction effect that 20 % with combustibles and 40 % with flame retarded by gathering dismantling objects. The main SW materials were Gh structure materials, mainly on the polyethylene seats, together in 2008 and 2009. In addition, "non gathered case" generates SW after Gh removal work intensively. On the other hand, "gathered case" generates SW constantly for a dismantling period.

Oral presentation

Development of PRW technology for ODS steel, 12; Strength evaluation test by using artificially-defected test pieces

Seki, Masayuki; Kihara, Yoshiyuki; Hirako, Kazuhito*; Motoki, Kazuhiko*; Tsukada, Tatsuya*

no journal, , 

no abstracts in English

267 (Records 1-20 displayed on this page)