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Oral presentation

Development of a granulator for MOX fuel fabrication for FBR

Suzuki, Mitsuru

no journal, , 

no abstracts in English

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

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

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

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

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.

267 (Records 1-20 displayed on this page)