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JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2020

Nakada, Akira; Nakano, Masanao; Kanai, Katsuta; Seya, Natsumi; Nishimura, Shusaku; Nemoto, Masashi; Tobita, Keiji; Futagawa, Kazuo; Yamada, Ryohei; Uchiyama, Rei; et al.

JAEA-Review 2021-062, 163 Pages, 2022/02

JAEA-Review-2021-062.pdf:2.87MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2020 to March 2021. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc. (the trade name was changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016) in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and exceeded the normal range of fluctuation in the monitoring, were evaluated.

Journal Articles

Measurement of isotopic composition of lanthanides in reprocessing process solutions by high-performance liquid chromatography with inductively coupled plasma mass spectrometry (HPLC/ICP-MS)

Okano, Masanori; Jitsukata, Shu*; Kuno, Takehiko; Yamada, Keiji

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Journal Articles

Determinations of plutonium and curium in the insoluble materials of spent fuel dissolver solutions at the Tokai Reprocessing Plant

Okano, Masanori; Kuno, Takehiko; Nemoto, Hirokazu*; Yamada, Keiji; Watahiki, Masaru; Hiyama, Toshiaki

Proceedings of INMM 50th Annual Meeting (CD-ROM), 9 Pages, 2009/07

no abstracts in English

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

JAEA Reports

Evaluation technology for burnup and generated amount of plutonium by measurement of xenon isotopic ratio in dissolver off-gas at reprocessing facility (Joint research)

Okano, Masanori; Kuno, Takehiko; Takahashi, Ichiro*; Shirozu, Hidetomo; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*; Yamada, Keiji; Sakai, Toshio

JAEA-Technology 2006-055, 38 Pages, 2006/12

JAEA-Technology-2006-055.pdf:3.33MB

The amount of Pu in the spent fuel was evaluated from Xe isotopic ratio in off-gas in reprocessing facility, is related to burnup. Six batches of dissolver off-gas at spent fuel dissolution process were sampled from the main stack in Tokai Reprocessing Plant during BWR fuel reprocessing campaign. Xenon isotopic ratio was determined with GC/MS. Burnup and generated amount of Pu were evaluated with Noble Gas Environmental Monitoring Application code (NOVA), developed by Los Alamos National Laboratory. Inferred burnup evaluated by Xe isotopic measurements and NOVA were in good agreement with those of the declared burnup in the range from -3.8% to 7.1%. Also, the inferred amount of Pu in spent fuel was in good agreed with those of the declared amount of Pu calculated by ORIGEN code in the range from -0.9% to 4.7%. The evaluation technique is applicable for both burnup credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection.

JAEA Reports

Confirmation of the availability of an analytical technique, Pu(VI) spectrophotometry for HALW; Technical Support for the Joint IAEA/Japan On-site Analytical Laboratory at the Rokkasho Reprocessing Plant (JASPAS JU-01-01)

Kitao, Takahiko; Sato, Soichi; Kuno, Takehiko; Keiji, Yamada,; Watahiki, Masaru; Kamata, Masayuki

JNC TN8410 2003-014, 29 Pages, 2003/11

JNC-TN8410-2003-014.pdf:1.82MB

The Agency requested the Tokai Reprocessing Plant(TRP) to confirm the applicability of three kinds of analytical procedure for Pu(VI) spectrophotometry in On-Site Analytical Laboratory (OSL) at Rokkasho, in order to obtain accurate plutonium(Pu) concentration in High Active Liquid Waste (HALW). Three analytical procedures, (1) Calibration method, (2) Nd internal standard method and (3) Reduction method, were tested. The measurement sample was prepared by adding the known amount of plutonium in the actual HALW after removing original Pu by solid extraction. We measured the Pu concentration in the sample by three methods and calculated the accuracy and precision. The results of each method are summarized as follows:(1) Calibration method Plutonium concentration calculated by the calibration method agreed with that by adjusted concentration. (2) Nd internal standard method Accurate results were obtained by this method. The error of pretreatment, especially dilution, has not influenced on the Pu measurements. (3) Reduction method The measured Pu concentrations were higher than those by adjusted. From the comparison with these results, the calibration method is the most simple and rapid in the three methods. Analysis time was within 1 hour including sample preparation. The detection limit, with the calibration method, was 1.3 mgPu/L in the actual HALW measurements.

Journal Articles

None

; Yamada, Keiji; ; Ikeda, Hisashi ; Kuno, Yusuke

Donen Giho, (94), p.91 - 94, 1995/06

None

Journal Articles

Determination of Technetium in Spent Fuel Reprocessing Process Streams by Glove-Box-Enclosed Inductively Coupled Plasma Emission Spectrometer

Kuno, Yusuke; Yamada, Keiji;

Analytical Sciences, 6, p.97 - 101, 1990/00

 Times Cited Count:2 Percentile:15.99(Chemistry, Analytical)

JAEA Reports

2nd power-up test for JRR-2

Kambara, Toyozo; Uno, Hidero; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Takayanagi, Hiroshi; Fujimura, Tsutomu; Morita, Morito; Ichihara, Masahiro; et al.

JAERI 1045, 11 Pages, 1963/03

JAERI-1045.pdf:0.72MB

no abstracts in English

Oral presentation

Composition of insoluble materials in highly active liquid waste at Tokai Reprocessing Plant

Okano, Masanori; Kuno, Takehiko; Watahiki, Masaru; Yamada, Keiji; Kurakata, Koichiro

no journal, , 

no abstracts in English

Oral presentation

Determination of neptunium in reprocessing process, 3; Determination of neptunium by $$gamma$$ spectrometry in nitric acid media

Kitao, Takahiko; Nemoto, Hirokazu*; Shoji, Kazuhiro; Yamada, Keiji; Kurakata, Koichiro; Sato, Soichi

no journal, , 

no abstracts in English

Oral presentation

Determination of neptunium of Tokai reprocessing plant; Determination of neptunium by $$gamma$$ spectrometry in nitric acid media

Kitao, Takahiko; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Determination of neptunium in Tokai reprocessing plant; Determination of neptunium by $$gamma$$ spectrometry in nitric acid media

Kitao, Takahiko; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Evaluation technology for burnup and generated amount of plutonium by measurement of xenon isotopic ratio in dissolver off-gas at reprocessing facility

Okano, Masanori; Kuno, Takehiko; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Development of fuel design system for BWR composed of open computer code, 3

Yoshikawa, Takamichi*; Iwasaki, Tomohiko*; Endo, Hideki*; Suyama, Kenya; Shikoda, Keiji*; Yamada, Kohei*; Hamahata, Yoshiki*; Oeda, Shin*

no journal, , 

In order to develop a fuel design system of BWR based on opened calculation codes, a burnup code system SWAT2 using continuous energy Mote Carlo code was revised to include a function of branch calculation. A tool to evaluate lattice constants used in calculation code adopting modern nodal method was also developed and validated by comparison with CASMO.

Oral presentation

Determination of Pu/Cm ratio in sludge at Tokai reprocessing plant

Okano, Masanori; Nemoto, Hirokazu*; Jitsukata, Shu*; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Determination of plutonium in insoluble residue at reprocessing facility

Igarashi, Kazuto*; Nemoto, Hirokazu*; Okano, Masanori; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Determination of uranium by flow injection analysis (FIA) in reprocessing process

Yokosuka, Keisuke*; Suwa, Toshio; Kitao, Takahiko; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Determination of impurity in dissolved solution of spent nuclear fuel by ICP-AES

Okano, Masanori; Igarashi, Kazuto*; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

32 (Records 1-20 displayed on this page)