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Oral presentation

Solidification and leaching property of sludge containing fluoride

Tsunashima, Yasumichi; Shimazaki, Masao; Ohashi, Yusuke; Tanaka, Yoshio; Nomura, Mitsuo

no journal, , 

The operation waste of uranium conversion plant and uranium enrichment plant is called sludge, and contains many fluoride which is deleterious material. For disposal, elution of fluoride is a problem. Moreover, sludge contains many calcium sulfate and we are anxious about expansion of cement solidification object by superfluous generation ofettringite. Therefore, we report solidification and the leaching property of the cement solidification object of the sludge containing many fluoride. Moreover, we report solidification and the leaching property of sludge using magnesium oxide solidification material as a method of controlling elution and expansion of fluoride.

Oral presentation

Investigation for colloids in the groundwater of Horonobe URL, 1; Characterization of colloids in the groundwater by using ultra filtration

Amano, Yuki; Amamiya, Hiroki; Murakami, Hiroaki; Iwatsuki, Teruki; Terashima, Motoki; Mizuno, Takashi; Kirishima, Akira*; Kuno, Atsushi*; Sasaki, Takayuki*; Kubota, Takumi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Characterization for decommission of uranium handling facility, 3; Classification method based on the nuclide composition in Ningyo-Toge Environmental Engineering Center

Hata, Haruhi; Yokoyama, Kaoru; Tanaka, Yoshio; Ohara, Yoshiyuki; Sugitsue, Noritake

no journal, , 

For decommission of uranium handling facilities, it is important to characterize the details of the facilities, which are the distribution of nuclide, the existence of hazardous waste and so on. The report suggests classification method based on the nuclide composition by using principal component analysis.

Oral presentation

Rupture properties of plain-woven Tyranno-SA3 CVI SiC/SiC composites

Ozawa, Kazumi; Nozawa, Takashi; Toyoshima, Kazuoki*; Tanigawa, Hiroyasu; Hinoki, Tatsuya*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Learning from our communication efforts after the nuclear disaster

Yamamoto, Ryuichi

no journal, , 

The risk communication office of Nuclear fuel Cycle engineering Laboratories in JAEA has experience of the risk communication research more than ten years. Suffering the nuclear hazard which occurred on March 11, 2011, the risk communication office started interactive communication activity aiming at the improvement in literacy about the civic radiation and radioactivity of Ibaraki Prefecture and Fukushima Prefecture by making it into a background. This aimed at the uneasiness of the citizen by the improvement in literacy, and anxious mitigation. In this activity, the questionnaire survey is conducted simultaneously and it has already been going to just introduce analysis of that result by several pieces of verbal reports since the AESJ autumn convention of last year. Here, the meaning and suggestion which can be drawn up from there are discussed, quoting the data of a previous report.

Oral presentation

Design approach for LOHRS type event based on the safety design criteria for Generation-IV SFR, 2; Study of equipment specification

Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Nakata, Shuhei*; Yokoi, Shinobu*

no journal, , 

Plant design studies against "Loss of heat removal system" event were carried out based on the safety design criteria for 4th generation sodium-cooled fast reactor discussing in the Generation-IV international forum (GIF-SFR-SDC). This presentation introduces equipment specification study to match the GIF-SFR-SDC.

Oral presentation

Measurement examination of Pu content in radioactive waste with portable waste assay system, 2

Ono, Yosuke; Yokoyama, Hitoshi*; Watanabe, Naoki; Miyauchi, Masami; Shuji, Yoshiyuki; Daidai, Misao

no journal, , 

no abstracts in English

Oral presentation

Clearance of concrete debris generated from modification work of JRR-3, 5; Result of measurement and evaluation of radioactivity distribution

Nanri, Tomohiro; Kishimoto, Katsumi; Satoyama, Tomonori; Takaizumi, Hirohide; Kanno, Tomoyuki; Maruyama, Tatsuya; Yoshimori, Michiro

no journal, , 

no abstracts in English

Oral presentation

Inspection and repair techniques in reactor vessel of sodium cooled fast reactor, 8-2; Removal of cover gas boundary components on rotating plug of Joyo

Okuda, Eiji; Fujinaka, Hideaki; Suzuki, Toshiaki; Shimizu, Hisashi*; Kondo, Katsumi*

no journal, , 

no abstracts in English

Oral presentation

Measurement of neutron capture cross section of Np-237 by a neutron activation method

Nakamura, Shoji; Kitatani, Fumito; Harada, Hideo; Fujii, Toshiyuki*; Uehara, Akihiro*; Yamana, Hajimu*

no journal, , 

The neutron capture cross section of Np-237 was measured by a neutron activation method at the Kyoto University Research Reactor (KUR).

Oral presentation

Reliability enhancement of seismic risk assessment of NPP as risk management fundamentals, 4; Estimation of epistemic uncertainty in fragility evaluation (building and soil)

Nishida, Akemi

no journal, , 

This research develops methodology for quantification of uncertainty associated with final results from seismic probabilistic risk assessment (SPRA) in the framework of risk management of NPP facilities. In this research, we take a role of aggregation of expert opinion on structure/equipment fragility estimation and development of implementation guidance on epistemic uncertainty (modeling uncertainty). In this report, A model plant data which will be used for seismic response analysis and sensitivity study is shown.

Oral presentation

Chemical composition of artificial seawater after immersion tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*

no journal, , 

Chemical analysis of artificial seawater after immersion tests of irradiated fuel was carried out.

Oral presentation

Damage monitoring for SiC/SiC composites by acoustic emission

Nozawa, Takashi; Tanigawa, Hiroyasu

no journal, , 

SiC/SiC composite is one of promising candidates of advanced fusion blanket system. SiC/SiC composites with continuous fiber reinforcement specifically fails in quasi-ductile manner and this becomes a strong merit compared with brittle ceramics. However, this quasi-ductility is totally different from ductility of metals and hence material design standard and codes needs to be established. It is also important to identify the effect of permanent damage accumulation on the failure process and to identify the allowed geometry and size of flaws for the design. This study aims to fully understand the detailed tensile failure process by acoustic emission. Strength anisotropy of composites is specifically summarized by clarifying tensile failure mechanism by various failure modes, which can be achieved by tensile loading with various loading directions.

Oral presentation

Evaluation of SCCV integrity under hypothetical sodium combustion, 1; Sodium combustion evaluation

Yamamoto, Tomohiko; Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Sakaba, Hiroshi*; Sakashita, Takeshi*

no journal, , 

JSFR is planning to adopt a steel plate reinforced concrete (SC) structure for containment vessel (CV). This paper describes the analyses of hypothetical sodium combustion and load condition in the CV.

Oral presentation

Development of core seismic assessment method toward the FBR

Murakami, Hisatomo; Kitamura, Seiji; Yamazawa, Tomoyuki*; Ikarimoto, Iwao*; Kan, Taro*

no journal, , 

no abstracts in English

Oral presentation

Preliminary study on an analysis method of rare earths and others in spent fuel using an anion exchange resin

Sato, Makoto; Fukaya, Hiroyuki; Umeda, Miki; Suyama, Kenya; Tonoike, Kotaro; Kamohara, Keiko*; Suzuki, Norihisa*

no journal, , 

no abstracts in English

Oral presentation

Development and validation of the integrated burnup analysis code system SWAT4

Kashima, Takao; Suyama, Kenya; Uchida, Yuriko; Tonoike, Kotaro; Takada, Tomoyuki*

no journal, , 

no abstracts in English

Oral presentation

The Tritium removal for the decommissioning of FUGEN, 2; Estimation of amount of residual heavy water

Miyoshi, Nobuaki; Kadowaki, Haruhiko; Matsuo, Hidehiko; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

Development of prediction technology of two-phase flow dynamics under earthquake acceleration, 19; Numerical simulation of effects of vibration frequency on bubble behavior

Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

no journal, , 

no abstracts in English

271 (Records 1-20 displayed on this page)