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Journal Articles

Development of a portable $$beta$$-ray dust monitor for highly-concentrated airborne contaminants

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

Hoken Butsuri (Internet), 58(3), p.135 - 140, 2023/11

Radioactivity concentrations of airborne dust are important measurements because they are used to protect workers from intakes and to assess internal exposure doses. Therefore, we developed a portable $$beta$$-ray dust monitor by using an ultra-thin plastic scintillator, which is designed for continuous monitoring of highly-concentrated airborne contaminants ($$>$$ 10$$^{-2}$$ Bq/cm$$^{3}$$, equivalent to 30 times larger than the derived air concentration of $$^{90}$$Sr) such as a decommissioning work in the Fukushima Daiichi Nuclear Power Plant. From the performance test results, it is evaluated that the developed portable $$beta$$-ray dust monitor is functional in continuous monitoring with an airborne concentration of 1 Bq/cm$$^{3}$$.

Journal Articles

Development of a method of evaluating PuO$$_{2}$$ particle diameters using an alpha-particle imaging detector

Morishita, Yuki; Sagawa, Naoki; Takada, Chie; Momose, Takumaro; Takasaki, Koji

Radiation Protection Dosimetry, 199(13), p.1376 - 1383, 2023/08

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

It is very important to evaluate the diameters (activity median aerodynamic diameter) of Plutonium dioxide (PuO$$_{2}$$) particles for internal exposure dose evaluation. In this study, a method of evaluating PuO$$_{2}$$ particle diameters using an alpha-particle imaging detector was developed. PuO$$_{2}$$ particles with different diameters were modeled by Monte Carlo simulation, and the change in the shape of the energy spectrum for each particle diameter was evaluated. Two different patterns were modeled, namely, the case of $$^{239}$$PuO$$_{2}$$ and the case of PuO$$_{2}$$ (including isotopic composition of Pu). Multiple regression analysis was performed to determine the PuO$$_{2}$$ particle diameter from the obtained parameters. The simulated diameters and the diameters obtained with the regression model were in good agreement. The advantage of using the alpha-particle imaging detector is to measure the alpha energy spectrum for individual particle, and this allows accurate measurement of particle diameter distribution.

JAEA Reports

Application of imaging plate to the radiation protection in the MOX fuel fabrication facility, 2; The effect of changing exposure conditions and analysis conditions

Sagawa, Naoki; Izaki, Kenji; Mizuniwa, Harumi*

JAEA-Technology 2013-029, 28 Pages, 2013/11

JAEA-Technology-2013-029.pdf:3.35MB

Developed in the Mixed Oxide fuel fabrication facility, Basic handling of IP, analysis method, detection of Pu and radioactivity quantification. These are the conditions that the exposure conditions and the analysis condition are constant. However, in the case of Contamination has occurred in the workplace, contaminated samples are not only Pu. It may contain a Pb or RnTn. Then, if other work is being carried out in a room that is the operation of IP, it's difficult to darken the room. PSL is reduced when light hits the IP. In this study, we have investigated in order to upgrade radiation protection, in the case of Containing the Pb or PSL reduction by light. Additionally, regarding change of analysis condition, the analysis method was examined when the resolution was changed to 50 micro, 100 micro and 200 micro.

JAEA Reports

Safety demonstration test using the High Temperature Engineering Test Reactor (HTTR); Cold test of the loss of forced cooling

Shinohara, Masanori; Yanagi, Shunki; Tochio, Daisuke; Shimazaki, Yosuke; Nojiri, Naoki; Owada, Hiroyuki; Sato, Nao; Sagawa, Hiroshi; Umeda, Masayuki

JAEA-Technology 2011-029, 39 Pages, 2011/12

JAEA-Technology-2011-029.pdf:3.03MB

JAEA plans and performs the safety demonstration test using the HTTR to develop High Temperature Gas Reactor technologies. Cold test of the loss of forced cooling was conducted prior to the safety demonstration test, to check test procedure and plant behavior. Cold test consists of two phases, Phase1, 1 or 2 Vessel Cooling System (VCS) terminates, in the Phase2, all 3 Gas circulators and 1 VCS terminates. Cold test could confirm test process, and obtain data necessary to analysis and 2-dimensional horizontal sectional model analysis was verified to simulate actual measurement value.

Journal Articles

An Autoradiographical method using an imaging plate for the analyses of plutonium contamination in a plutonium handling facility

Takasaki, Koji; Sagawa, Naoki; Kurosawa, Shigeyuki; Mizuniwa, Harumi

Journal of Nuclear Science and Technology, 48(6), p.911 - 918, 2011/06

 Times Cited Count:12 Percentile:66.68(Nuclear Science & Technology)

An autoradiographical method using an imaging plate (IP) was developed to analyze the plutonium contamination in the plutonium handling facility and was applied to the monitoring of the workplace in a practical uranium-plutonium mixed oxide (MOX) fuel fabrication facility. A good relationship between the photo stimulated luminescence (PSL) intensities of IP and radioactivities measured by a radiation counter was obtained by the least-square fitting, taking the fading effect into consideration. The $$alpha$$-radioactivities of plutonium contamination were derived from the PSL image in this IP method, and their relative errors were evaluated from exposure time.

JAEA Reports

Application of imaging plate to the radiation protection in the MOX fuel fabrication facility

Sagawa, Naoki; Yamazaki, Takumi; Kurosawa, Shigeyuki*; Izaki, Kenji; Mizuniwa, Harumi; Takasaki, Koji

JAEA-Technology 2010-051, 35 Pages, 2011/03

JAEA-Technology-2010-051.pdf:1.83MB

The image analysis method using a imaging plate (IP) is recent technique, and this method can get the information of radioactivity distribution by the unit of Photo Simulated Luminescence (PSL). We have investigated the PSL images obtained by measuring some plutonium samples which are radiation protection samples in order to apply imaging plate to the radiation protection at the MOX fuel facility. Plutonium spots were extracted from the PSL image extracted by the threshold, in which about 99% of the back ground was excluded, and identified by the additional requirement that the spot size is more than 40 pixels. The average background is subtracted from PSL strength of the spot area identified as Pu, and the radioactivity of the Pu spot was evaluated by multiplying the conversion calculation that is in consideration of fading.

Journal Articles

Neutron spectra measurements at JAEA MOX fuel facility

Tsujimura, Norio; Yoshida, Tadayoshi; Sagawa, Naoki; Shoji, Shigeru

Progress in Nuclear Science and Technology (Internet), 1, p.154 - 157, 2011/02

JAEA Reports

Development of image-analysis method of plutonium samples by imaging plate; Measurement of plutonium samples in mixed oxide fuel fabrication facility

Takasaki, Koji; Sagawa, Naoki; Kurosawa, Shigeyuki*; Shioya, Satoshi; Suzuki, Kazunori; Horikoshi, Yoshinori; Mizuniwa, Harumi

JAEA-Technology 2008-028, 73 Pages, 2008/03

JAEA-Technology-2008-028.pdf:5.88MB

Recently, an imaging plate (IP) was developed. Pu analysis by an IP was studied in the JAEA Cooperative Research Scheme on the Nuclear Fuel Cycle, and the availability about detection of Pu and discrimination with radon progenies was shown. In order to apply these results to the radiation control, this research aims at evaluation of radioactivity, discrimination with radon progenies, and evaluation of AMAD by an IP. In the conventional autoradiography (ARG) by a ZnS and Polaroid film, Contamination of Pu can only be grasped by viewing. Since the digital data of the radiation and location is obtained by an IP, Pu can be detected quantitatively and radioactivity can be evaluated. As a result of this research, the image of alpha emitter on an IP is the same as that of the conventional ARG, and can be applied also to the ARG of beta and $$gamma$$ emitter. In measurement of Pu, the function of Image J (image-analysis software) was very available. Pu radioactivity was evaluated by an IP.

Oral presentation

Development of image-analysis method of plutonium samples by imaging plate

Mizuniwa, Harumi; Takasaki, Koji; Horikoshi, Yoshinori; Suzuki, Kazunori; Shioya, Satoshi; Sagawa, Naoki; Kurosawa, Shigeyuki*

no journal, , 

no abstracts in English

Oral presentation

Neutron spectrometry in the MOX fuel fabrication process for the experimental FBR Joyo

Yoshida, Tadayoshi; Tsujimura, Norio; Sagawa, Naoki; Shoji, Shigeru

no journal, , 

no abstracts in English

Oral presentation

Application of imaging plate to the radiation protection in the MOX fuel fabrication facility

Sagawa, Naoki; Kurosawa, Shigeyuki*; Takasaki, Koji; Mizuniwa, Harumi

no journal, , 

no abstracts in English

Oral presentation

A Trial the distribution measurement of the alpha ray radioactivity using flat panel type PMT

Yamazaki, Takumi; Sagawa, Naoki; Izaki, Kenji; Mizuniwa, Harumi

no journal, , 

no abstracts in English

Oral presentation

Examination of autoradiography with digital camera

Sagawa, Naoki; Odano, Takayuki*; Morifuji, Masayuki; Izaki, Kenji; Mizuniwa, Harumi

no journal, , 

no abstracts in English

Oral presentation

Measurements and simulations of response of silicon semiconductor detector produced by incident neutron

Morishita, Yuki; Sagawa, Naoki; Tsubaki, Hirohiko; Izaki, Kenji; Mizuniwa, Harumi

no journal, , 

no abstracts in English

Oral presentation

Radiation dose rate mapping around a glove box at a MOX fuel facility

Morishita, Yuki; Sagawa, Naoki; Suga, Takumi; Tsujimura, Norio; Yoshida, Tadayoshi; Nagai, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Investigations of personal dose characteristics involved Fukushima Daiichi reactor accident, 4; Field test, 2; Response of the personal dosemeter on the phantoms and result of a measurement of the ambient dose and the energy spectrum of $$gamma$$ rays

Yamazaki, Takumi; Takada, Chie; Nakamura, Keisuke; Sagawa, Naoki; Hoshi, Katsuya; Nakagawa, Takahiro; Takimoto, Misaki; Tanimura, Yoshihiko*; Takahashi, Fumiaki; Momose, Takumaro; et al.

no journal, , 

no abstracts in English

Oral presentation

Evaluation of dose distribution of an eye lens and a body surface using Si semiconductor detector

Morishita, Yuki; Sagawa, Naoki; Suga, Takumi; Yamazaki, Takumi; Tsujimura, Norio; Yoshida, Tadayoshi; Nagai, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Evaluation of dose distribution of an eye lens and a body surface using an anthropomorphic phantom at a MOX fuel facility

Suga, Takumi; Morishita, Yuki; Sagawa, Naoki; Yamazaki, Takumi; Tsujimura, Norio; Yoshida, Tadayoshi; Nagai, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Development of a dust monitor detector reducing radon progeny impact using ZnS (Ag) scintillator, 2; Field test

Sasaki, Kazuki; Okuyama, Shun; Sagawa, Naoki; Hosomi, Kenji; Takada, Chie

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

25 (Records 1-20 displayed on this page)