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Journal Articles

Effect of $$^{90}$$Sr dissolved solution on corrosion potential of type 316L stainless steel

Aoyama, Takahito; Kato, Chiaki; Sato, Tomonori; Sano, Naruto; Yamashita, Naoki; Ueno, Fumiyoshi

Zairyo To Kankyo, 71(4), p.110 - 115, 2022/04

no abstracts in English

Journal Articles

Lens dosimetry study in $$^{90}$$Sr+$$^{90}$$Y beta field; Full-face mask respirator shielding and dosemeter positioning

Tsujimura, Norio; Hoshi, Katsuya; Yamazaki, Takumi; Momose, Takumaro; Aoki, Katsunori; Yoshitomi, Hiroshi; Tanimura, Yoshihiko; Yokoyama, Sumi*

KEK Proceedings 2020-5, p.21 - 28, 2020/11

Journal Articles

Measurements of the doses of eye lens for the workers of Fukushima Daiichi Nuclear Power Plant

Yokoyama, Sumi*; Ezaki, Iwao*; Tatsuzaki, Hideo*; Tachiki, Shuichi*; Hirao, Shigekazu*; Aoki, Katsunori; Tanimura, Yoshihiko; Hoshi, Katsuya; Yoshitomi, Hiroshi; Tsujimura, Norio

Radiation Measurements, 138, p.106399_1 - 106399_5, 2020/11

 Times Cited Count:2 Percentile:24.28(Nuclear Science & Technology)

Journal Articles

5.1.2 Properties and characteristics of radiations

Takahashi, Fumiaki

Genshiryoku No Ima To Ashita, p.106 - 109, 2019/03

The Atomic Energy Society of Japan has planned to publish a document for public, entitled "Current and tomorrow of atomic energy, -Experiences from the accident at the Tokyo Electronic Power Company Fukushima Dai-ichi NPPs-". The documents give us basics and usages of radiations, in addition to nuclear power plants and the accident at TEPCO Fukushima Dai-ichi NPPs. This manuscript explains interactions and penetrations in material for $$alpha$$-rays, $$beta$$-rays, $$gamma$$-rays and neutrons. In addition, exposure characteristics that is determined by properties of radiations are expressed here. This manuscript also explains characteristics in internal exposure and countermeasures of radiation protection following the TEPCO accident for Iodine-131 and Cesium-137.

Journal Articles

Addendum report of the JHPS expert committee on radiation protection of the lens of the eye, 2; When and how should the dosimetry of beta $$H_{rm p}$$(3) be made?

Akahane, Keiichi*; Iimoto, Takeshi*; Ichiji, Takeshi*; Iwai, Satoshi*; Oguchi, Hiroyuki*; Ono, Kazuko*; Kawaura, Chiyo*; Kurosawa, Tadahiro*; Tatsuzaki, Hideo*; Tsujimura, Norio; et al.

Hoken Butsuri, 50(4), p.257 - 261, 2015/12

In a mixed field of photon and beta radiations, the same dose assigned to skin is normally assigned to the dose to the lens of the eye as a conservative estimate of H$$_{p}$$(3). In exceptional cases that a very high beta dose might be imparted of the same order with the dose limit, however, the conservatively biased dose must be too limiting, and thereby an accurate estimate of beta $$H_{rm p}$$(3) is desirable. This article presents a practical proposal of when and how the dosimetry of beta $$H_{rm p}$$(3) should be made.

Journal Articles

Radiochemical reactions between tritium molecule and carbon dioxide

Shu, Wataru; Ohira, Shigeru; Suzuki, Takumi; Nishi, Masataka

Fusion Science and Technology, 48(1), p.684 - 687, 2005/07

 Times Cited Count:3 Percentile:24.22(Nuclear Science & Technology)

As part of a series of studies on radiochemical reactions that may take place in the fuel processing systems of a future D-T fusion machine like the ITER, reactions of tritium molecule (T$$_{2}$$) and carbon dioxide (CO$$_{2}$$) were examined by laser Raman spectroscopy and quadrupole mass spectrometry (QMS). Both T$$_{2}$$ and CO$$_{2}$$ decreased rapidly in the first 30 minutes after mixing, and then the reactions between them became much slower. As the predominant products of the reactions, carbon monoxide (CO) and tritiated water (T$$_{2}$$O) were found in gaseous phase and condensed phase, respectively. However, there existed also some solid products that were thermally decomposed to CO, CO$$_{2}$$, T$$_{2}$$, T$$_{2}$$O, etc. during baking at 150$$^{circ}$$C and 250$$^{circ}$$C.

Journal Articles

Radiation measurement for safeguards environmental samples by imaging plate

Yasuda, Kenichiro; Sakurai, Satoshi; Gunji, Hideho; Usuda, Shigekazu

Journal of Nuclear Science and Technology, 39(Suppl.3), p.552 - 555, 2002/11

In order to contribute to the strengthened safeguards system based on the Program 93+2 of the IAEA, Japan Atomic Energy Research Institute (JAERI) constructed the CLEAR facility (Clean Laboratory for Environmental Analysis and Research) and is developing analytical technology for ultra trace amounts of nuclear materials in environmental samples. To avoid cross-contamination among the samples and contamination of the clean rooms, radioactive materials in the samples to be introduced into the CLEAR facility will be limited to a certain amount. For this purpose the authors have examined the feasibility of Imaging-plate method, which is a kind of autoradiography and is suitable for determination on distribution of low-level radioactivity in the samples. Preliminary examination with $$beta$$-ray (K-40), the linearity was obtained in the range of 0.01 - 0.2 Bq. The experiments with $$alpha$$-ray (Sm-147) suggested the detection limit of 0.01 Bq, which was equivalent to 2 $$mu$$g of natural uranium. At the presentation, the results on actual environmental samples will be reported.

JAEA Reports

JENDL FP decay data file 2000

Katakura, Junichi; Yoshida, Tadashi*; Oyamatsu, Kazuhiro*; Tachibana, Takahiro*

JAERI 1343, 79 Pages, 2001/07

JAERI-1343.pdf:4.94MB

no abstracts in English

Journal Articles

Estimation of $$beta$$- and $$gamma$$-ray spectra for JENDL FP decay data file

Katakura, Junichi; Yoshida, Tadashi*; Oyamatsu, Kazuhiro*; Tachibana, Takahiro*

Journal of Nuclear Science and Technology, 38(7), p.470 - 476, 2001/07

 Times Cited Count:5 Percentile:38.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental radioimmunotherapy with $$^{186}$$Re-MAG3-A7 anti-colorectal cancer monoclonal antibody; Comparison with $$^{131}$$I-counterpart

Kinuya, Seigo*; Yokoyama, Kunihiko*; Kobayashi, Katsutoshi; Motoishi, Shoji; Onoma, Katsuyuki; Watanabe, Naoto*; Shuke, Noriyuki*; Bunko, Hisashi*; Nichigishi, Takatoshi*; Tonami, Norihisa*

Annals of Nuclear Medicine, 15(3), p.199 - 202, 2001/06

 Times Cited Count:9 Percentile:31.12(Radiology, Nuclear Medicine & Medical Imaging)

no abstracts in English

Journal Articles

Methylxanthine sensitization of human colon cancer cells to $$^{186}$$Re-labeled monoclonal antibody

Kinuya, Seigo*; Yokoyama, Kunihiko*; Kudo, Miho*; Kasahara, Yoshihito*; Kobayashi, Katsutoshi; Motoishi, Shoji; Onoma, Katsuyuki; Bunko, Hisashi*; Nichigishi, Takatoshi*; Tonami, Norihisa*

Journal of Nuclear Medicine, 42(4), p.596 - 600, 2001/04

no abstracts in English

JAEA Reports

Improvement of the technique for stack monitoring based on behavior analysis of natural radio-nuclides; The technique for reducing the value of the exhaust monitor's background

Izaki, Kenji; Noda, Kimio; ; Kashimuta, Yoshio*

JNC TN8410 2001-005, 30 Pages, 2001/01

JNC-TN8410-2001-005.pdf:0.62MB

Stack monitoring is the most important work in radiation control works. Exhaust monitors used for stack monitoring have the background (which is the counts by natural radio-nuclides) on normal condition, and the values of the background vary with the facilities. Therefore, if the value of background is high, it is difficult to estimate rapidly the radioactive concentration in the exhaust. In order to estimate rapidly the radioactive concentration in exhaust, we analyzed the behavior of natural radioactivity in the facilities and examine the technique fo reducing the value of the background. As a result of the examination, we found that it is possible to estimate rapidly if we change over the monitoring point to immediately after the HEPA filters on the exhaust duct. In this reports, the analyzed results of behavior of natural radio-nuclides in the facilities and the technique for reducing the values of the background are described. To reduce the value of the background has a major effect on not only rapidly estimating the radioactive density in the exhaust but also finding the unusual things on stack monitoring.

JAEA Reports

A study on improvements in accuracy of nuclear data measurements using $$gamma$$-ray spectroscopic methods

Furutaka, Kazuyoshi

JNC TN8400 2000-028, 70 Pages, 2000/10

JNC-TN8400-2000-028.pdf:1.71MB

This report describes the study done by the author as a postdoctoral research associate at Japan Nuclear Cycle Development Institute. This report is divided into two parts: improvements in accuracy in determination of thermal neutron capture cross sections, and improvements in accuracy of photo-nuclear absorption cross section measurements using the HHS. (1)In the measurements of thermal neutron capture cross sections using an activation method, accuracies of the final results attained are limited by (1) accuracy of $$gamma$$-ray peak detection efficiencies, and (2) accuracies of $$gamma$$-ray emission probabilities. In this study; to determine thermal neutron capture cross sections more accurately, the following researches have been done using a newly developed three-dimensional coincidence measurement system: (1)accurate determination of $$gamma$$-ray standard sources using a $$gamma$$-$$gamma$$ coincidence method, for precise calibration of $$gamma$$-ray peak detection efficiency, and (2) development of a $$beta$$-$$gamma$$ coincidence measurement system using a plastic scintillation detector as a $$beta$$-ray detector, for the determination of $$gamma$$-ray emission probabilities of short-lived nuclides, and measurement of $$gamma$$-ray emission probabilities of $$^{100}$$Tc nuclide using the coincidence system. (2)To transform radioactive nuclides with small thermal neutron capture cross sections, use of photonuclear absorption reaction has been suggested. In order to transform these nuclides efficiently using the reaction, one has to know detailed behavior of the photo-absorption cross sections. In this study, a Monte-Carlo simulation code has been used to create a standard set of $$gamma$$-ray response functions of the high-resolution high-energy spectrometer (HHS), to enable reliable analyses of the data obtained by the spectrometer.

JAEA Reports

Development of building surfaces contamination measurement technique (Contract research)

Hatakeyama, Mutsuo; Ito, Hirokuni; Yanagihara, Satoshi

JAERI-Tech 2000-056, 38 Pages, 2000/09

JAERI-Tech-2000-056.pdf:5.23MB

no abstracts in English

Journal Articles

Production of a radioactive endovascular stents by implantation of $$^{133}$$Xe ions

Watanabe, Satoshi; Osa, Akihiko; Sekine, Toshiaki; Ishioka, Noriko; Koizumi, Mitsuo; Kojima, Takuji; Hasegawa, A.*; Yoshii, M.*; Okamoto, E.*; Aoyagi, K.*; et al.

Applied Radiation and Isotopes, 51(2), p.197 - 202, 1999/08

 Times Cited Count:7 Percentile:49.7(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Nuclear data sheets for A=125

Katakura, Junichi

Nuclear Data Sheets, 86(4), p.955 - 1118, 1999/04

no abstracts in English

Journal Articles

Glass dosimeter for personal dosimetry

Yamaguchi, Takenori

Hoken Butsuri, 33(2), p.121 - 142, 1998/00

no abstracts in English

Journal Articles

Nuclear spectroscopy from the standpoint of nuclear data evaluation

Iimura, Hideki; Katakura, Junichi

KURRI-KR-25, p.27 - 29, 1998/00

no abstracts in English

Journal Articles

Introduction of model calculated $$beta$$-ray spectrum to ENDF/B-VI fission products decay data file

Katakura, Junichi; T.R.England*

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.438 - 443, 1998/00

no abstracts in English

Journal Articles

Determination of environmental Pu-241 using liquid scintillation counting techniques

Amano, Hikaru; Watanabe, Miki*

The 5th Low Level Counting Conf. using Liquid Scintillation Analysis, 0, p.86 - 91, 1996/00

no abstracts in English

42 (Records 1-20 displayed on this page)