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Journal Articles

Analysis of the activities of the website "Question and Answer about radiation in Daily Life" after the accident at the Fukushima Daiichi Nuclear Power Station and some lessons learned from it; To pass on this experience to the future

Kono, Takahiko; Shimo, Michikuni*; Hayakawa, Hironobu*; Taniguchi, Kazufumi*; Tanaka, Masato*; Tanaka, Hitomi*; Onoue, Yosuke*; Nagaya, Hiroshi*; Torii, Hiroyuki*; Uno, Kazuko*

Hoken Butsuri (Internet), 55(4), p.226 - 238, 2020/12

After the accident at the Fukushima Daiichi Nuclear Power Station, artificial radionuclides such as radioactive cesium and iodine were released into the environment. It caused great anxiety not only in the vicinity of the Fukushima Daiichi Nuclear Power Station but also in other regions of Japan. Some members of the Japan Health Physics Society (JHPS) which is a leading academic society in Japan in the field of radiation protection volunteered to establish the website called "Question and Answer about radiation in Daily Life" just after the accident to reduce the anxiety of the residents about the health effects of radiation. After that, Committee of "Question and Answer about radiation in Daily Life" was established in August 2011 in JHPS, and this activity had been carried out under the responsibility of the society that answered with sincerity against questions from the public as specialists until February 2013. The number of questions on the website had gradually decreased as time passed; therefore, the Committee members decided to end these activities in February 2013. In this paper, following contents were shown; the activities of the Q&A website for about two years, the issues of the stance on our activities, the information related to the website activities and the analysis of Twitter data. Based on the experience and the knowledge obtained from these activities, the issues and experiences that can be utilized in the initial response to emergencies for radiation protection experts as well as other fields are presented.

JAEA Reports

A Study for a fire gas behavior by using a vertical shaft model (Contract research)

Abe, Hironobu; Hatakeyama, Nobuya; Yamazaki, Masanao; Okuzono, Akihiko*; Sakai, Tetsuo*; Inoue, Masahiro*

JAEA-Research 2009-019, 192 Pages, 2020/02

JAEA-Research-2009-019.pdf:8.07MB

Construction of the underground facility is on going at the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency. The facility is consisted of three shafts and horizontal drifts at the completion of construction and it is excavated in geological environment with methane gas, so it is important to secure the workers and visitors security in case of fire in the underground. However, it is known that the fire gas such as methane shows a complicated behavior by drift effect and so on and very difficult to predict its behavior, even if under enforced ventilation. In order to construct new prediction method of the fire gas behavior, the model scaled experiments were conducted by using the basic model which consists of shafts and drifts. As a results, fundamental data of the fire gas behavior was grasped and complicated behavior of the fire gas such as three-dimensional backflow and main flow inversion phenomena at the underground structure were ascertained. A new fire gas behavior analysis system has been designed and a prototype system has been programmed which is able to simulate the phenomena noted above. Coupling analysis method is adapted to the system, which consists of mainly one-dimensional ventilation network analysis and simplified computational fluid dynamics program named M-CFD. To minimize calculation time, M-CFD was designed as two-dimensional calculation with simulators multi area analysis system. Using the prototype system, several experimented models representing typical behavior of fire gas have been simulated for model scaled experiments. The system qualitatively reappeared the phenomena such as back flow or main flow inversion, and most of calculations completed in expected time. This indicates appropriateness of the prototype system, but some upgrade such as heat conductivity analysis in the wall rock mass transfer calculation, user friendly interface system and others will be required.

Journal Articles

Security measures at nuclear fuel facilities, 2; Internal threat countermeasure in cyber-security

Kono, Soma; Yamada, Hiroyuki; Goto, Atsushi*; Yamazaki, Katsuyuki; Nakamura, Hironobu; Kitao, Takahiko

Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (Internet), 2 Pages, 2018/11

no abstracts in English

Journal Articles

Discussion of effective insider threat mitigation method at reprocessing plant

Nakamura, Hironobu; Kitao, Takahiko; Yamada, Hiroyuki; Kono, Soma; Kimura, Takashi; Tasaki, Takashi

Proceedings of INMM 59th Annual Meeting (Internet), 9 Pages, 2018/07

Journal Articles

Performance test of automatic analysis system of strontium-90 in environmental sample

Fujita, Hiroki; Nojima, Takehiro; Nagaoka, Mika; Osawa, Takahito; Yokoyama, Hiroya; Ono, Hironobu*

KEK Proceedings 2016-8, p.168 - 172, 2016/10

An automatic analysis system was developed to analyze Strontium-90 ($$^{90}$$Sr) radioactivity in environmental sample for 2013-2015. Various kinds of ashed environmental samples were used in performance tests of the automatic system. These tests were successful without any system trouble. However, $$^{90}$$Sr concentration had not been measured using the samples analyzed by the system. In this research, $$^{90}$$Sr concentration in seaweed sample was compared by between the system's analysis and worker's one. Moreover, the system was improved in each analysis process.

Journal Articles

Development of automatic analysis system of Strontium-90 in environmental sample

Nojima, Takehiro; Fujita, Hiroki; Nagaoka, Mika; Osawa, Takahito; Yokoyama, Hiroya; Ono, Hironobu*

KEK Proceedings 2015-4, p.111 - 115, 2015/11

Automatic strontium-90 analysis system was developed for environmental sample in this research. The system was successful to do wet ashing, chemical separation and ion exchange processes using robot, automatic heating system and so on. Hand-made control program can operate the system by itself.

Journal Articles

Feasible evaluation of neutron capture therapy for hepatocellular carcinoma using selective enhancement of boron accumulation in tumour with intra-arterial administration of boron-entrapped water-in-oil-in-water emulsion

Yanagie, Hironobu*; Kumada, Hiroaki*; Nakamura, Takemi; Higashi, Shushi*; Ikushima, Ichiro*; Morishita, Yasuyuki*; Shinohara, Atsuko*; Fujiwara, Mitsuteru*; Suzuki, Minoru*; Sakurai, Yoshinori*; et al.

Proceedings of 14th International Congress on Neutron Capture Therapy (ICNCT-14) (CD-ROM), p.157 - 160, 2010/10

JAEA Reports

Post-irradiation examinations of inert matrix nitride fuel irradiated in JMTR (01F-51A capsule)

Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Honda, Junichi; Hatakeyama, Yuichi; Ono, Katsuto; Matsui, Hiroki; Arai, Yasuo

JAEA-Research 2007-026, 75 Pages, 2007/03

JAEA-Research-2007-026.pdf:13.6MB

A plutonium nitiride fuel pin containing inert matrix such as ZrN and TiN was encapsuled in 01F-51A and irradiated in JMTR. Minor actinides are surrogated by plutonium. Average linear powers and burnups were 408W/cm, 30000MWd/t(Zr+Pu)(132000MWd/t-Pu) for (Zr,Pu)N and 355W/cm, 38000MWd/t(Ti+Pu)(153000MWd/t-Pu) for (TiN,PuN). The irradiated capsule was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. Any failure was not observed in theirradiated fuel pin. Very low fission gas release rate of about 1.6% was measured. The inner surface of cladding tube did not show any signs of chemical interaction with fuel pellets.

Journal Articles

Study of stellar reactions in explosive hydrogen burning with CRIB

Kubono, Shigeru*; Teranishi, Takashi*; Notani, Masahiro*; Yamaguchi, Hidetoshi*; Saito, Akito*; He, J. J.*; Wakabayashi, Yasuo*; Fujikawa, Hisashi*; Amadio, G.*; Baba, Hidetada*; et al.

Nuclear Physics A, 758, p.733 - 736, 2005/07

 Times Cited Count:1 Percentile:14.46(Physics, Nuclear)

With using $$^{17}F$$ RNB from CRIB, proton inelastic scattering was observed. From this experiment, some resonance parameters have been deduced for the key reaction, $$^{14}O(alpha,p)^{17}F$$ at the explosive hydrogen burning stage in stars. Proton inelastic scattering of $$^{23}Mg$$ are also reported.

Journal Articles

The XAFS beamline BL01B1 at SPring-8

Uruga, Tomoya*; Tanida, Hajime*; Yoneda, Yasuhiro; Takeshita, Kunikazu*; Emura, Shuichi*; Takahashi, Masao*; Harada, Makoto*; Nishihata, Yasuo; Kubozono, Yoshihiro*; Tanaka, Tsunehiro*; et al.

Journal of Synchrotron Radiation, 6(Part3), p.143 - 145, 1999/05

An x-ray absorption fine-structure (XAFS) spectroscopy beamline, BL01B1, was installed at a bending magnet source at SPring-8 and has been open to users since October 1997. It was designed for XAFS experiments covering a wide energy range. Position tables and automatical control programs were established to adjust the x-ray optics and achieve the designed performance of the beamline under each experimental condition. This has enabled conventional XAFS measurements to be made with a good data quality from 4.5 to 110 keV.

Journal Articles

XAFS study on RbC$$_{60}$$

Kubozono, Yoshihiro*; Mimura, Kazue*; Takabayashi, Yasuhiro*; Maeda, Hironobu*; Kashino, Setsuo*; Emura, Shuichi*; Nishihata, Yasuo; Uruga, Tomoya*; Tanaka, Tsunehiro*; Takahashi, Masao*

Journal of Synchrotron Radiation, 6(Part3), p.564 - 566, 1999/05

The Rb K-edge XAFS spectra for the stable phase of RbC60 which is a quasi one-dimensional polymer were measured in the temperature range from 14.6 to 210 K in order to clarify the origin of the metal-insulator transition around 50 K. The distances and mean-square relative displacements between the Rb atom and the neighboring C atoms determined by XAFS exhibited no change around 50 K, implying that the metal-insulator transition originates from the SDW instablity.

Oral presentation

Clinical study of neutron capture therapy for locally recurrent breast cancer

Yanagie, Hironobu*; Sakurai, Yoshinori*; Kumada, Hiroaki; Naka, Hideji*; Furuya, Yoshitaka*; Takamoto, Shinichi*; Ono, Koji*; Takahashi, Hiroyuki*

no journal, , 

no abstracts in English

Oral presentation

Expecting of heat generation effects for the condition of various fuel component of MOX powder transportation

Nakamichi, Hideo; Hirono, Kenji*; Shoji, Kaoru*; Nakamura, Hironobu; Matsumoto, Masaki; Fujisaku, Sakae; Yoshimoto, Katsunobu

no journal, , 

In order to establish the conversion technology development test regarding MOX powder handling during transportation when high burn-up plutonium is used, temperature measurement on the canister in a transportation cask and powder property analysis were performed. As a result of the test, effective guideline of anticipated temperature on the canister could be obtained.

Oral presentation

The Experience obtained by risk communication activity with radiation question and answer in life website after Fukushima Daiichi Nuclear Power Plant Accident

Kono, Takahiko; Ogino, Haruyuki*; Hayakawa, Hironobu*; Shimo, Michikuni*; Taniguchi, Kazufumi*; Ban, Nobuhiko*

no journal, , 

no abstracts in English

Oral presentation

The Experience of risk communication activities using the Q&A web site concerning about radiation in life after Fukushima Daiichi Nuclear Power Plant accident

Kono, Takahiko; Ogino, Haruyuki*; Hayakawa, Hironobu*; Shimo, Michikuni*; Taniguchi, Kazufumi*; Ban, Nobuhiko*

no journal, , 

After Fukushima Daiichi Nuclear Power Plant accident happened on 11 March 2011, we have been providing the right information about radiation and radioactivity via a Q&A website. Immediately after the accident, volunteers of Japan Health Physics Society (JHPS) built up a website named Questions and Answers about Radiation in Daily Life. They carefully answered all of the questions posted on the website. In August, Steering Committee of the Q&A site was officially established in JHPS. Since then, the Committee has been engaged in the risk communication activities to the public. We have analyzed characteristics of questioners and question contents of about 1,500 posted on our web site so far. It has been found that mothers of small children form the major portion of the questioners all through the period.

Oral presentation

Development of automatic analysis system of Strontium-90 in environmental sample

Nojima, Takehiro; Fujita, Hiroki; Nagaoka, Mika; Osawa, Takahito; Yokoyama, Hiroya; Ono, Hironobu*

no journal, , 

An automatic analysis system was developed to analyze radioactive strontium ($$^{90}$$Sr) radioactivity in environmental sample. The analysis method was followed to the manual compiled by the MEXT, to determine low level of $$^{90}$$Sr radioactivity concentration in environmental sample. In this research, the procedure of the Sr analysis before milking procedure of $$^{90}$$Y was automated except for a part of the analysis. The systems were controlled by an original program under the LabVIEW. Various kinds of ashed environmental samples were used in performance tests of the automatic system. These tests were successful without system trouble. Finally, Sr recovery was about 40-70% to whitebait analysis.

Oral presentation

Application of automatic analysis system of Strontium-90 to analysis of environmental sample

Fujita, Hiroki; Nojima, Takehiro*; Nagaoka, Mika; Osawa, Takahito; Ono, Hironobu*

no journal, , 

no abstracts in English

Oral presentation

Nuclear security measures at nuclear fuel facilities, 1; Trust worthiness program for insider mitigation method

Yamada, Hiroyuki; Kono, Soma; Tasaki, Takashi; Kojima, Junji; Kitao, Takahiko; Nakamura, Hironobu

no journal, , 

no abstracts in English

18 (Records 1-18 displayed on this page)
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