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Journal Articles

U-Pb ages of zircons from metamorphic rocks in the upper sequence of the Hidaka metamorphic belt, Hokkaido, Japan; Identification of two metamorphic events and implications for regional tectonics

Takahashi, Yutaka*; Mikoshiba, Masumi*; Shimura, Toshiaki*; Nagata, Mitsuhiro; Iwano, Hideki*; Danhara, Toru*; Hirata, Takafumi*

Island Arc, 30(1), p.e12393_1 - e12393_15, 2021/01

 Times Cited Count:2 Percentile:18.21(Geosciences, Multidisciplinary)

The Hidaka metamorphic belt is an excellent example of island-arc-type crust, and in this belt the metamorphic grade increases westwards from unmetamorphosed sediment up to the granulite facies. The metamorphic age of the belt had previously been considered to be ca. 55 Ma. However, zircons from the granulites in the lower sequence have given U-Pb ages of ca. 21-19 Ma and a preliminary report on zircons from pelitic gneiss in the upper sequence gave a U-Pb age of ca. 40 Ma. In this paper we provide new U-Pb ages for zircons from the pelitic gneisses in the upper sequence in order to assess the metamorphic age and also the maximum depositional age of the sedimentary protolith. The weighted mean $$^{206}$$Pb/$$^{238}$$U ages and 2 sigma errors for zircons from biotite gneiss in the central area of the belt are 39.6 $$pm$$ 0.9 Ma for metamorphic overgrowth rims and 53.1 $$pm$$ 0.9 Ma for the youngest inherited detrital cores. The ages of zircons from cordierite-biotite gneiss in the southern area are 35.9 $$pm$$ 0.7 Ma for overgrowth rims and 46.5 $$pm$$ 2.8 Ma for the youngest detrital cores. These results indicate that the metamorphism of the upper sequence took place at ca. 40-36 Ma, and that the sedimentary protolith was deposited after ca. 53-47 Ma. These metamorphic ages are consistent with the reported ages of ca. 37-36 Ma plutonic rocks in the upper sequence, but contrast with the ca. 21-19 Ma ages of metamorphic and plutonic rocks in the lower sequence. Therefore, we conclude, that the upper and lower metamorphic sequences developed independently but became coupled before ca. 19 Ma as a result of dextral reverse tectonic movements, as indicated by the intrusion of ca. 19-18 Ma magmas, possibly generated in the lower sequence, into the upper sequence.

Journal Articles

A Cubic CeBr$$_{3}$$ gamma-ray spectrometer suitable for the decommissioning of the Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Uenomachi, Mizuki*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

Nuclear Instruments and Methods in Physics Research A, 971, p.164118_1 - 164118_8, 2020/08

 Times Cited Count:7 Percentile:67.5(Instruments & Instrumentation)

JAEA Reports

Radioactivity analysis of metal samples taken from pipes of the Fugen, 5

Haraga, Tomoko; Tobita, Minoru*; Takahashi, Shigemi*; Seki, Kotaro*; Izumo, Sari; Shimomura, Yusuke; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Data/Code 2016-017, 53 Pages, 2017/02

JAEA-Data-Code-2016-017.pdf:3.17MB

Fugen Nuclear Power Station was shut down and now is under decommissioning. Many radioactivity concentration data of dismantled materials have to be accumulated to calculate the scaling factors of radioactive wastes and to verify that the cleared dismantled materials conform to the clearance levels. A simple and rapid radioactivity determination method for radioactive waste samples was developed by Department of Decommissioning and Waste Management. For its demonstration, the simple and rapid radioactivity determination method was applied to metal samples, which were taken from dismantled pipes in contact with heavy water or carbon dioxide gas of Fugen. This report summarizes the radioactivity data obtained from the analysis of those samples.

JAEA Reports

Current status of a decommissioning project in the Enrichment Engineering Facility; Results in the second-half of the fiscal year of 2014

Matsumoto, Takashi; Takahashi, Nobuo; Hayashibara, Kenichi; Ishimori, Yuu; Mita, Yutaka; Kakiya, Hideyoshi

JAEA-Technology 2016-020, 80 Pages, 2016/11

JAEA-Technology-2016-020.pdf:17.8MB

The Enrichment Engineering Facility of the Ningyo-toge Environmental Engineering Center was constructed in order to establish the technological basis of plant engineering for uranium enrichment in Japan. Uranium enrichment tests, using natural and reprocessed uranium, were carried out from 1979 to 1989 with two types of centrifuges in the facility. According to the decommissioning plan of the facility, UF$$_{6}$$ handling equipment and supplemental equipment in these plants are intended to be dismantled by 2019 in order to make vacant spaces for future projects use, for example, inventory investigation, precipitation treatment, etc. This report shows the current state of the decommissioning project in the second-half of the fiscal year of 2014.

JAEA Reports

Radioactivity analysis of metal samples taken from pipes of the Fugen, 4

Haraga, Tomoko; Tobita, Minoru*; Takahashi, Shigemi*; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Data/Code 2015-025, 52 Pages, 2016/03

JAEA-Data-Code-2015-025.pdf:1.92MB

Fugen Nuclear Power Station was shut down and now is under decommissioning. Many radioactivity concentration data of dismantled materials have to be accumulated to calculate the scaling factors of radioactive wastes and verify that the cleared dismantled materials conform to the clearance levels. A simple and rapid radioactivity determination method for radioactive waste samples was developed in Department of Decommissioning and Waste Management. For the demonstration, the simple and rapid radioactivity determination method was applied to metal samples, which were taken from dismantled pipes of Fugen. This report summarizes the radioactivity data obtained from the analysis of those samples.

Journal Articles

Method of dynamic image measurement for analyzing cricket behavior

Takahashi, Satoru*; Okuda, Yasutake*; Kawabata, Kuniaki; Aonuma, Hitoshi*; Sato, Yutaka*; Iwata, Kenji*

Journal of Signal Processing, 20(2), p.65 - 74, 2016/03

Journal Articles

Precise determination of $$^{12}_{Lambda}$$C level structure by $$gamma$$-ray spectroscopy

Hosomi, Kenji; Ma, Y.*; Ajimura, Shuhei*; Aoki, Kanae*; Dairaku, Seishi*; Fu, Y.*; Fujioka, Hiroyuki*; Futatsukawa, Kenta*; Imoto, Wataru*; Kakiguchi, Yutaka*; et al.

Progress of Theoretical and Experimental Physics (Internet), 2015(8), p.081D01_1 - 081D01_8, 2015/08

 Times Cited Count:14 Percentile:66.75(Physics, Multidisciplinary)

Level structure of the $$^{12}_{Lambda}$$C hypernucleus was precisely determined by means of $$gamma$$-ray spectroscopy. We identified four $$gamma$$-ray transitions via the $$^{12}$$C$$(pi^{+},K^{+}gamma)$$ reaction using a germanium detector array, Hyperball2. The spacing of the ground-state doublet $$(2^{-}, 1^{-}_{1})$$ was measured to be $$161.5pm0.3$$(stat)$$pm0.3$$ (syst)keV from the direct $$M1$$ transition. Excitation energies of the $$1^{-}_{2}$$ and $$1^{-}_{3}$$ states were measured to be $$2832pm3pm4$$, keV and $$6050pm8pm7$$, keV, respectively. The obtained level energies provide definitive references for the reaction spectroscopy of $$Lambda$$ hypernuclei.

Journal Articles

Determination of $$^{129}$$I in the Accumulated radioactive water and processing water of the Fukushima Daiichi Nuclear Power Plant

Shimada, Asako; Sakatani, Keiichi; Kameo, Yutaka; Takahashi, Kuniaki

Journal of Radioanalytical and Nuclear Chemistry, 303(2), p.1137 - 1140, 2015/02

 Times Cited Count:6 Percentile:46.16(Chemistry, Analytical)

Accumulated radioactive water and processing water were sampled from back and forth of the Accumulated radioactive water processing facility (ARWPF) at Fukushima Daiichi Nuclear Power Plant (FDNPP) to estimate the radioactivity of the secondary waste such as zeolite and sludge adsorbed radioactive material. Separation method of I$$^{-}$$ from the radioactive materials using solid phase extractant, Anion-SR, was developed, and the concentration of $$^{129}$$I in the accumulated water and processing water was determined by Inductively Coupled Plasma Mass Spectrometry including dynamic reaction cell (DRC-ICP-MS).

Journal Articles

Development of a rapid analytical method for $$^{129}$$I in the contaminated water and tree samples at the Fukushima Daiichi Nuclear Power Station

Shimada, Asako; Ozawa, Mayumi; Kameo, Yutaka; Yasumatsu, Takuyo*; Nebashi, Koji*; Niiyama, Takuya; Seki, Shuhei; Kajio, Masatoshi; Takahashi, Kuniaki

Nuclear Back-end and Transmutation Technology for Waste Disposal, p.311 - 317, 2015/00

no abstracts in English

Journal Articles

Development of radionuclide distribution database and map system on the Fukushima nuclear accident

Seki, Akiyuki; Takemiya, Hiroshi; Takahashi, Fumiaki; Saito, Kimiaki; Tanaka, Kei*; Takahashi, Yutaka*; Takemura, Kazuhiro*; Tsuzawa, Masaharu*

Progress in Nuclear Science and Technology (Internet), 4, p.47 - 50, 2014/04

The radionuclide distribution database and map system, which provide basic information for evaluations and countermeasures of the Fukushima nuclear accident, are explained. Due to massive earthquake and tsunami, Fukushima Dai-ichi Nuclear Power Plant has been damaged and had spread out radioactive materials around the Fukushima site. It is necessary to collect, analyze, and provide the information of radioactivity correctly and immediately. We developed two providing systems to identify the current distribution of released radionuclides and support decontamination activities.

Journal Articles

A New method to analyze $$^{242m}$$Am in low-level radioactive waste based on extraction chromatography and $$beta$$-ray spectrometry

Shimada, Asako; Kameo, Yutaka; Takahashi, Kuniaki

Analytical Chemistry, 85(16), p.7726 - 7731, 2013/08

 Times Cited Count:6 Percentile:21.71(Chemistry, Analytical)

A new method for identifying $$^{242m}$$Am in low-level radioactive waste (LLW) using $$beta$$-ray spectrometry is proposed. First, Eu, Am, and Cm in a digested solution of simulated LLW were separated from the major components of the digested solution and Pu using transuranium resin. Next, Am and Cm were separated from Eu using tetravalent actinide resin. A $$beta$$-ray spectrum of the fraction containing Am and Cm was recorded and the contribution of $$^{237}$$Np, which is a daughter nuclide of $$^{243}$$Am, was subtracted to determine the radioactivity of $$^{242}$$Am. The radioactivity of $$^{242m}$$Am determined by $$beta$$-ray spectrometry agreed with that obtained by analyzing the increase in $$^{242}$$Cm in the Am fraction just after its separation from Cm with tertiary pyridine resin.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in low-level radioactive wastes generated at JPDR facilities, 1

Tsuji, Tomoyuki; Kameo, Yutaka; Sakai, Akihiro; Hoshi, Akiko; Takahashi, Kuniaki

JAEA-Technology 2012-045, 37 Pages, 2013/02

JAEA-Technology-2012-045.pdf:2.43MB

It is necessary to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes in order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA. In this report, the practical evaluation methods such as the scaling factor method for JPDR facilities have been studied for disposal of the low-level radioactive wastes generated from nuclear reactor facilities in JAEA.

JAEA Reports

Radioactivity analysis of metal samples taken from pipes of the Fugen

Haraga, Tomoko; Kameo, Yutaka; Ishimori, Kenichiro; Shimada, Asako; Tobita, Minoru*; Takahashi, Shigemi*; Takahashi, Kuniaki

JAEA-Data/Code 2012-031, 39 Pages, 2013/02

JAEA-Data-Code-2012-031.pdf:9.28MB

The Fugen Nuclear Power Station was shut down and decommissioning of the Fugen has been implemented. To calculate the scaling factor of radioactive waste or advance the clearance of dismantled materials, a large number of radioactivity concentration data of dismantled materials have to be accumulated. For these reasons, the simple and rapid radioactivity determination method was applied for metal samples, which were taken from pipes of the Fugen. The present report is summarized analytical procedures and obtained radioactivity data of the Fugen pipe samples.

Journal Articles

Simple determination method using ICP-MS for $$^{129}$$I in radioactive liquid waste solidified with bitumen

Kameo, Yutaka; Ishimori, Kenichiro; Shimada, Asako; Takahashi, Kuniaki

Bunseki Kagaku, 61(10), p.845 - 849, 2012/10

 Times Cited Count:4 Percentile:14.68(Chemistry, Analytical)

A simple determination method was developed to measure $$^{129}$$I in low level radioactive liquid waste solidified with bitumen. A simulated bituminized product sample was cut to 0.02 g pieces, subsequently these pieces and sodium carbonate were heated in an electric furnace. This procedure could well decompose the bituminized sample without volatilizing $$^{129}$$I. Sixty to seventy percent of $$^{129}$$I was recovered by a solid phase extraction disk from a solution containing the decomposed sample. A dynamic reaction cell inductively coupled plasma mass spectrometer was applied to measure $$^{129}$$I, and as a result, detection limit of $$^{129}$$I was reduced to by a factor of about 6 comparing with conventional ICP-MS measurement. Determined radioactivity concentration for the simulated bituminized sample containing $$^{129}$$I was good agreement with expected value within 6% error.

Journal Articles

Highly sensitive detection of neodymium ion in small amount of spent nuclear fuel samples using novel fluorescent macrocyclic hexadentate polyaminocarboxylate probe in capillary electrophoresis-laser-induced fluorescence detection

Saito, Shingo*; Sato, Yoshiyuki*; Haraga, Tomoko; Nakano, Yuta*; Asai, Shiho; Kameo, Yutaka; Takahashi, Kuniaki; Shibukawa, Masami*

Journal of Chromatography A, 1232, p.152 - 157, 2012/04

 Times Cited Count:14 Percentile:45.28(Biochemical Research Methods)

A rapid and high-sensitive detection method of total concentration of Nd ion in a spent nuclear fuel sample is desirable since precise quantification of total Nd is useful as indicator of burnup. In this work, a capillary electrophoresis-laser-induced fluorescent detection method (CE-LIF) was proposed for analysis of total Nd in the spent fuel sample solution, employing a newly synthesized metal fluorescent probe with a fluorescein and a macrocylic hexadentate chelating group, FTC-ABNOTA, for lanthanide (Ln) ions. The mutual separation among the Ln-FTC-ABNOTA complexes was achieved by pH control providing dynamic ternary complexation with hydroxide ions. In this method, high resolution of Nd from other Ln ions with high resolution of 1.3-1.9 and a very low detection limit of 3.2 ppt were successfully obtained. A simulated spent fuel sample containing various metal ions was examined, so that a good quantification result with 99.3% recovery was obtained even with large excess of U.

Journal Articles

The Rectal temperature estimation method based on tympanic temperature for workers wearing protective clothing in nuclear facilities

Takahashi, Naoki; Lee, J.-Y.*; Wakabayashi, Hitoshi*; Tochihara, Yutaka*

Hoken Butsuri, 47(1), p.54 - 65, 2012/03

no abstracts in English

JAEA Reports

Performance evaluation of multiple gamma-ray detection instrument by non-destructive measurement of radioactive waste sample

Kochiyama, Mami; Haraga, Tomoko; Kameo, Yutaka; Takahashi, Kuniaki

JAEA-Technology 2011-038, 26 Pages, 2012/02

JAEA-Technology-2011-038.pdf:2.94MB

A nondestructive measurement of gamma-ray emitting nuclides has been studied and Multiple gamma-ray Detection Instrument is newly constructed with 4 detection units consisting of Ge and BGO detectors. Compton scattering was decreased by the combination of Ge and BGO detectors. This instrument was applied to the detection of interested nuclides in radioactive waste sample, which contains significant amount of Co-60, and detection limit of the interested gamma-ray emitting nuclides were improved by a factor of 4 to 12 times than single gamma-ray spectrometer. As for Nb-94, the radioactivity determined from measurements using Multiple gamma-ray Detection Instrument in this sample was agreed with that determined by radiochemical analysis within 15%. It was confirmed that the instrument are useful for radioactivity determination of gamma-ray emitting nuclides in radioactive waste.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in the bituminized products generated from research facilities

Tsuji, Tomoyuki; Kameo, Yutaka; Sakai, Akihiro; Amazawa, Hiroya; Takahashi, Kuniaki

JAEA-Technology 2011-028, 66 Pages, 2011/11

JAEA-Technology-2011-028.pdf:3.16MB

In order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA, we need to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes. In this report, we have studied on establishing the practical evaluation methods such as the scaling factor method for bituminized products generated at Nuclear Science Research Institute and also summarized subjects for establishment of the practical evaluation methods for the bituminized products.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities

Hoshi, Akiko; Tsuji, Tomoyuki; Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Sakai, Akihiro; Kameo, Yutaka; Kogure, Hiroto; Higuchi, Hidekazu; Takahashi, Kuniaki

JAEA-Data/Code 2011-011, 31 Pages, 2011/10

JAEA-Data-Code-2011-011.pdf:1.7MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data (262 data) about the radioactivity concentrations of the 7 important nuclides ($$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{59}$$Ni, $$^{63}$$Ni, $$^{90}$$Sr, $$^{137}$$Cs) which accumulated by the analysis.

Journal Articles

Prediction and verification of rectal temperature from measured infrared tympanic temperature in workers wearing impermeable protective clothing in nuclear facilities

Takahashi, Naoki; Lee, J.-Y.*; Wakabayashi, Hitoshi*; Tochihara, Yutaka*

Proceedings of 4th International Conference on Human-Environment System (ICHES 2011) (USB Flash Drive), p.745 - 750, 2011/10

no abstracts in English

113 (Records 1-20 displayed on this page)