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Oral presentation

Oral presentation

Acquisition and analysis of alpha-radioactivity data for glove box dismantling

Yoshida, Masato; Tsubota, Yoichi; Aita, Takahiro

no journal, , 

no abstracts in English

Oral presentation

Physical condition monitoring for workers wearing air-fed suit using wearable device data

Goto, Kenta

no journal, , 

In the dismantling of gloveboxes, workers wear air-fed suits and perform heavy work, therefore it is important to manage the physical condition of the workers during their work. We aimed to establish a physical condition management method to prevent problems caused by workers' physical conditions. Using the wearable device, the skin temperature and pulse rate data were continuously measured during workers' work, and the relationship between the acquired data and changes in workers' physical conditions was analyzed. The analysis results suggest that the risk of physical health problems increases, both when the rate of temperature increase in skin temperature is high during the first few tens of minutes of work and when the pulse rate remains outside the normal range of variation for a long time.

Oral presentation

Oral presentation

Development of dry suction decontamination method for alpha-activity, 2

Asakawa, Jun; Shibanuma, Tomohiro

no journal, , 

no abstracts in English

Oral presentation

Development of sodium determination in high active liquid waste using ion selective electrode

Aoya, Juri; Kono, Soma; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko

no journal, , 

Vitrification of high active liquid waste (HALW) is a top priority toward the decommissioning of Tokai Reprocessing Plant. Concentration of Sodium (Na) in HALW is required to be analyzed accurately and quickly for the vitrification process control, because it affects viscosity of molten glass and element leaching rate from the vitrified waste. An inductively coupled plasma optical emission spectrometer (ICP-OES), which is modified for remote operation by manipulator in the hot cell, is used for determination of Na in HALW. However, the trouble of the ICP-OES generally requires long recovery time and causes possibility of the vitrification process delay. Therefore, for alternative determination method to prevent the vitrification process delay, Na determination method in HALW using Na-ion selective electrode, which measures electromotive force generated in accordance with ion concentration in solution sample is developed. In this study, influences by hydrogen ion (H$$^{+}$$) and the other coexistent elements on analytical performance, and measurement results of Na in HALW by the ion selective electrode are reported.

Oral presentation

Investigation of method for stabilization of cadmium, 2

Taniguchi, Takumi

no journal, , 

no abstracts in English

Oral presentation

Examination of an effective decontamination method near the face due to powdered radioactive contamination

Honda, Fumiya; Isozaki, Kohei; Nabatame, Satoru

no journal, , 

no abstracts in English

Oral presentation

Effects of iron ion on dissolution of nuclear waste glass

Iwata, Hajime

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Standing position of worker with protective goggles impacts equivalent dose of the lens of eye in the Nuclear Fuel Cycle Engineering Laboratories

Sakuma, Shuhei; Watanabe, Yuki; Kuroe, Ayame; Takimoto, Misaki; Takashima, Hideki; Takada, Chie; Tsujimura, Norio

no journal, , 

no abstracts in English

Oral presentation

Improvement of measurement conditions for Fuel cladding ultrasonic testing

Nemoto, Shuji

no journal, , 

no abstracts in English

Oral presentation

Development of incinerator volume reduction technology for uranium adsorbent (tannics) related to decommissioning of the Engineering Demonstration Facility I

Omori, Kohei; Shibata, Atsuhiro; Yano, Kimihiko; Sato, Daisuke

no journal, , 

no abstracts in English

Oral presentation

Impacts of spatial variation in distribution coefficient on radionuclide migration

Takahashi, Yuta

no journal, , 

no abstracts in English

Oral presentation

Development of reagent-free decontamination technology by ultra fine bubble

Kimura, Shuya; Shibata, Atsuhiro; Yano, Kimihiko

no journal, , 

no abstracts in English

Oral presentation

Preliminary investigation for upgrading of all-weather type dust sampler

Uchiyama, Rei; Yamada, Ryohei

no journal, , 

no abstracts in English

Oral presentation

Design and manufacture of substitutive assemblies for MONJU reactor decommissioning

Sakakibara, Hiroshi; Aoki, Nobuhiro; Muto, Masahiro; Otabe, Jun; Takahashi, Kenji*; Fujita, Naoyuki*; Hiyama, Kazuhiko*; Suzuki, Hirokazu*; Kamogawa, Toshiyuki*; Yokosuka, Toru*; et al.

no journal, , 

no abstracts in English

Oral presentation

Performance evaluation of a $$beta$$-particle detector designed for monitoring of airborne dust with high radioactivity

Fujisawa, Makoto; Sagawa, Naoki; Hosomi, Kenji; Morishita, Yuki; Takada, Chie

no journal, , 

no abstracts in English

Oral presentation

Development of identification method of unsteady gas entrainment vortex; Evaluation of three dimensional behavior of free vortex by identification of vortex center line

Matsushita, Kentaro; Ezure, Toshiki; Imai, Yasutomo*; Fujisaki, Tatsuya*; Tanaka, Masaaki

no journal, , 

In safety design of sodium-cooled fast reactor, generation of a cover gas entrainment vortex at free surface in upper plenum is an issue. It is necessary to evaluate gas entrainment vortex by numerical analysis, and gas entrainment amount evaluation tool "Stream Viewer" based on velocity distribution obtained by numerical analysis is developed. In this report, as a part of the development of Stream Viewer, evaluation method to identify vortex center line from free surface is examined to evaluate three dimensional behavior of gas entrainment vortex. The evaluation method was applied to an open channel water test in which an wake vortex is generated unsteadily from the plate. It was confirmed that vortex center line can be identified and a vortex that propagates to downstream and gas core grows can be distinguished from a vortex in which gas core does not grow by evaluation method of the vortex center line.

Oral presentation

Investigation on applicability of subchannel analysis code ASFRE on thermal hydraulics analysis in fuel assembly with inner duct structure on sodium-cooled fast reactor

Kikuchi, Norihiro

no journal, , 

In the design study of a sodium-cooled fast reactor (SFR) in JAEA, the adoption of a fuel assembly (FA) with an inner duct structure called FAIDUS has been investigated to enhance safety of SFR. Due to the asymmetric layout of fuel rods by addition of the inner duct, the velocity and temperature distributions in FAIDUS may differ from that in typical FA. It is need to confirmed that applicability of the subchannel analysis code named ASFRE which has been developed as a FA design tool, to thermal hydraulics analysis in FAIDUS. Because the reference data on the thermal hydraulics in FAIDUS have not been obtained by the mock-up experiment, the code-to-code comparisons with numerical results of ASFRE and those of a CFD code named SPIRAL was conducted. The applicability of ASFRE was indicated through the confirmation of the consistency of mechanism of the specific temperature and velocity distributions occurring around the inner duct between the numerical results by ASFRE and SPIRAL.

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