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JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2016

Nakano, Masanao; Fujita, Hiroki; Mizutani, Tomoko; Nemoto, Masashi; Tobita, Keiji; Hosomi, Kenji; Nagaoka, Mika; Hokama, Tomonori; Nishimura, Tomohiro; Koike, Yuko; et al.

JAEA-Review 2017-028, 177 Pages, 2018/01

JAEA-Review-2017-028.pdf:3.61MB

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 2016 to March 2017. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Electric Power Company Holdings, Inc. 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 were exceeded the normal range of fluctuation in the monitoring, were evaluated.

Journal Articles

Advanced-ORIENT cycle project; Summary of phase I fundamental studies

Koyama, Shinichi; Suzuki, Tatsuya*; Ozawa, Masaki*; Kurosawa, Kiyoko*; Fujita, Reiko*; Mimura, Hitoshi*; Okada, Ken*; Morita, Yasuji; Fujii, Yasuhiko*

Procedia Chemistry, 7, p.222 - 230, 2012/00

 Times Cited Count:2 Percentile:71.19

Adv.-ORIENT cycle strategy has been proposed as a basic concept for trinitarian research on separation, transmutation and utilization of nuclides and elements based on FBR fuel cycle. Validation of principal separation method and related safety research were performed from 2006 through 2011 as Phase I program. First, more than 90% of Cs could be recovered from the actual spent fuel [IXC(I) step]. The next is the adsorption of the platinum group metals (PGM), lanthanides, Am and Cm were separated by using a tertiary pyridine-type resin (TPR) as ion exchange steps [IXC(II, III, IV) steps]. The separated PGM metals will be supplied to the electrochemical extraction [CEE step]. As experiment for safety issues, Hastelloy-B at RT and Ta at 90$$^{circ}$$C were confirmed their anti-corrosive in highly concentrated HCl media. Thermo-chemical stability for TPR was verified. Issues to be solved for next phase based on the final results of phase I program.

Journal Articles

Current status and future plans of advanced ORIENT cycle strategy

Koyama, Shinichi; Suzuki, Tatsuya*; Mimura, Hitoshi*; Fujita, Reiko*; Kurosawa, Kiyoko*; Okada, Ken*; Ozawa, Masaki

Progress in Nuclear Energy, 53(7), p.980 - 987, 2011/09

 Times Cited Count:5 Percentile:38.79(Nuclear Science & Technology)

Individual basic researches of separation step were performed in the Advanced ORIENT Cycle project. High separation selectivity for Cs and Sr by novel nano adsorbents AMP-SG (D) and D18C6-MC were confirmed, respectively. TPR well adsorbed Pd and Tc in dilute HCl condition. Formation of rare metal fission product RMFP-deposit Pt electrodes from SHLLW was verified, and it was confirmed that high catalytic reactivity on electrolytic production of hydrogen. As experiment for engineering feasibility, Hastelloy-B at RT and Ta at 90$$^{circ}$$C were confirmed their anti-corrosive in highly concentrated HCl media. Thermo-chemical stability for TPR was verified in either HCl or HNO$$_{3}$$ media toward its practical use in the separation process. Issues to be solved for optimization based on the results of lab-scale experiment have revealed in this study.

Journal Articles

Study of thermal stability for tertiary pyridine ion exchange resin and anti-corrosion property of structural material toward eluents used in the advanced ORIENT cycle process

Koyama, Shinichi; Ozawa, Masaki; Kurosawa, Kiyoko*; Tatenuma, Katsuyoshi*; Sato, Yoshihiko*; Okada, Ken*

Journal of Radioanalytical and Nuclear Chemistry, 286(3), p.807 - 813, 2010/12

 Times Cited Count:1 Percentile:10.01(Chemistry, Analytical)

A multi-functional separation process is proposed on the Adv.-ORIENT cycle concept. In this process, hydrochloric acid, mixture of nitric acid and methanol should be used as eluents. Two important subjects should be solved so as to prove the availability. One is corrosion aspect for the use of HCl solution, Tantalum was anti-corrosive in HCl media, and Hastelloy-B seemed to be acceptable at RT, with evidence of low corrosion rate ($$<$$ 0.1 mm/y). The other is explication of the reactive safety between ion exchange resin and solvent (nitric acid and methanol). The reaction occurred regardless of nitric acid concentration and presence or absence of methanol when the temperature of heater reached 220 $$^{circ}$$C. However, it was confirmed that the reaction did not occur when the heating temperature decreased.

Journal Articles

Safety research of multi-functional reprocessing process considering nonproliferation based on an ion-exchange method

Koyama, Shinichi; Ozawa, Masaki; Okada, Ken*; Kurosawa, Kiyoko*; Suzuki, Tatsuya*; Fujii, Yasuhiko*

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1530 - 1536, 2007/09

Simplified separation process was proposed based on ion-exchange technique. HCl, HNO$$_{3}$$ and MeOH were used as an eluent. To develop an engineering scale concept, it is indispensable to establish the condition for safety operation. Corrosion test of structural materials in the HCl was performed by using some metals. In this experiment, it was proved that the Ta, Zr, Nb and hastelloy have good endurance to HCl solution. Research of thermal hazard of pyridine-type ion-exchange resin, MeOH and HNO$$_{3}$$ media system was studied in the view point of fire and explosion safety. There is no hazardous reaction between IER/MeOH, HNO$$_{3}$$ media system. In the case of more than 150$$^{circ}$$C, we should pay attention to the exothermic reaction at dried condition NO$$_{3}$$-IER or IER/HNO$$_{3}$$ media system.

JAEA Reports

None

Yoshida, Shigeru*; Kurosawa, Kiyoko*; *

PNC TJ9407 95-001, 109 Pages, 1995/03

PNC-TJ9407-95-001.pdf:2.32MB

None

Oral presentation

Study on $$^{99}$$Mo production method with irradiation of circulating Mo solution, 1; Results of cold tests (preliminary tests)

Inaba, Yoshitomo; Ishikawa, Koji*; Ishida, Takuya; Ishitsuka, Etsuo; Kurosawa, Kiyoko*; Hishinuma, Yukio*; Tatenuma, Katsuyoshi*

no journal, , 

The circulating solution irradiation method is a new production method of $$^{99}$$Mo, which is the parent nuclide of $$^{99m}$$Tc used as medical diagnosis medicine. In order to realize this method, compatibility between molybdenum solutions and structural materials, etc. were investigated. As a result, it was found that the potassium molybdate solution have good characteristics as an irradiation target.

Oral presentation

Evaluation of anti-corrosion materials for tertiary pyridine resine-based reprocessing, 3; The First screening of anti-corrosion materials for a novel reprocessing system

Ozawa, Masaki; Koyama, Shinichi; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Fujii, Yasuhiko*

no journal, , 

no abstracts in English

Oral presentation

Advanced ORIENT cycle study (Phase I), 5; Metal corrosion evaluation in hydrochloric acid media

Koyama, Shinichi; Ozawa, Masaki; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*

no journal, , 

Corrosion experiments (Immersion, exposure and electro chemistry) in pure HCl and HCl type SHLLW solution at RT and 90$$^{circ}$$C were performed using selected candidate metals, Ta, Zr, Nb and Hastelloy-B. We found the measured corrosion rates were less than 0.05 mm/y for Ta in all experiment, and therefore, Ta showed an all-round anti-corrosion property. Hastelloy-B, Nb and Zr were not acceptable at 90$$^{circ}$$C because of its relatively high corrosion rate ($$>$$0.1 mm/y).

Oral presentation

Metal corrosion evaluation in hydrochloric acid media on tertiary pyridine-type resin applying to fuel reprocessing system, 5; Corrosion evaluation of Ti-0.15Pd and Ta-lining metals in hydrochloric acid media

Koyama, Shinichi; Ozawa, Masaki*; Fujii, Yasuhiko; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*

no journal, , 

In order to develop a separation process using tetriary pyridine-type resin, Ti-0.5Ps, Ta-lining Ti-0.15Pd and Ta-lining hastelloy-B were selected as candidate materials toward HCl solution used as solvent in this system. Immersion test in 12M pure HCl solution at RT was carried out. And immersion test, exposure test and electrochemical measurement in 7M HLLW-simulated HCl solution at RT and 90 deg. C were performed. As a result, all the materials show anti-corrosive property at the corrosion rate less than 1mm/y, except for Ti-0.5Pd in 12M pure HCl condition.

Oral presentation

Metal corrosion evaluation in hydrochloric acid media on tertiary pyridine-type resin applying to fuel reprocessing system, 6; Influence of $$gamma$$-ray irradiation to hydrochloric acid corrosion of Ta and Hastelloy-B

Koyama, Shinichi; Fujii, Yasuhiko; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*

no journal, , 

Corrosion experiment for Ta and Hastelloy-B was performed by $$gamma$$-ray irradiation under co-existence system of tertiary pyridine type resin and HCl media. As a result, Ta showed perfect anti-corrosion property under all experimental conditions. On the other hand, it was clear that the corrosion rate of Hastelloy-B was proportion to $$gamma$$-ray intensity. It is expected that oxidative species, such as hydrogen peroxide and ozone, were produced by irradiation, and were affected to corrosion.

Oral presentation

Metal corrosion evaluation in hydrochloric acid media on tertiary pyridine-type resin applying to fuel reprocessing system, 7; Erosion corrosion evaluation of Ta and Hastelloy-B based on hydrochloric acid media

Koyama, Shinichi; Matsumura, Tatsuro; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*

no journal, , 

no abstracts in English

Oral presentation

An Examination of humoral conversion on tertiary pyridine-tyep resin applying to fuel reprocessing systemDenitration by electrodialysis method

Koyama, Shinichi; Matsumura, Tatsuro; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Development of chemical separation of Sn from concrete matrices using TEVA resin

Do, V. K.; Furuse, Takahiro; Ota, Yuki; Sano, Yuichi; Iwahashi, Hiroyuki; Homma, Shunta; Ichijo, Yurina; Kurosawa, Kiyoko*; Endo, Tsubasa*; Motoki, Yoshiaki*; et al.

no journal, , 

This paper presents an HCl-free chemical separation procedure for Sn recovery from concretes. Two pretreatment methods of solution samples followed by a proposed solid-phase extraction on TEVA resin were examined. The obtained results show that Sn can be highly recovered by the developed separation scheme with good reproducibility. The developed method is aimed at practical application to purification of Sn from concrete rubble for quantification of $$^{126}$$Sn by mass spectrometer.

Oral presentation

Removal of interferences for ultrasensitive detection of $$^{126}$$Sn in radioactive rubbles by ICP-MS/MS

Ota, Yuki; Do, V. K.; Furuse, Takahiro; Sano, Yuichi; Iwahashi, Hiroyuki; Homma, Shunta; Ichijo, Yurina; Kurosawa, Kiyoko*; Endo, Tsubasa*; Motoki, Yoshiaki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Interference removal for high-sensitivity rapid analysis of $$^{107}$$Pd in radioactive rubbles by ICP-MS/MS

Iwahashi, Hiroyuki; Do, V. K.; Furuse, Takahiro; Ota, Yuki; Homma, Shunta; Kurosawa, Kiyoko*; Motoki, Yoshiaki*; Hirosawa, Takashi

no journal, , 

The radiometric determination of beta emitting $$^{107}$$Pd (half-life of 6.5 million years) requires a multiple-step chemical separation and a time-consuming radioactive measurement. Inductively coupled plasma tandem mass spectrometry (ICP-MS/MS) with recent technological advances in interference removal by two quadrupole mass filters and a collision/reaction cell could be an alternative for highly sensitive analysis of long-lived radionuclides. In this study, we have developed an analytical method for the determination of $$^{107}$$Pd in concrete rubble by ICP-MS/MS combined with single-column chromatographic separation. A simplified procedure for the separation of Pd from concrete matrices was developed. The measurement condition was optimized to completely suppress the interference including the isobar $$^{107}$$Ag and the sample matrices. The application of the developed method to radioactive concrete rubble is under consideration.

Oral presentation

Development of analytical method for interference-free determination of $$^{79}$$Se in concrete by ICP-MS/MS

Banjarnahor, I. M.; Do, V. K.; Motoki, Yoshiaki*; Ota, Yuki; Iwahashi, Hiroyuki; Kurosawa, Kiyoko*; Furuse, Takahiro

no journal, , 

Pure beta-emitting $$^{79}$$Se is one of the long-lived fission products that might release to the environment due to the nuclear accident at Fukushima Daiichi Nuclear Power Plant (FDNPP). A reliable and simple determination method of the radionuclide is important for proceeding the disposal of the wastes obtained from the decommissioning of FDNPP. We developed a new analytical procedure for the measurement of $$^{79}$$Se by inductively coupled plasma triple quadrupole mass spectrometry (ICP-MS/MS). All interferences that potentially interfere in the measurement of $$^{79}$$Se could be effectively removed by the chemical separation pretreatment and ICP-MS/MS. The method is tested with inactive concrete to verify the interference removal efficiency. Also, the analytical figures of merit such as detection capability etc. are reported.

Oral presentation

Development of HCl-free analysis method of $$^{113m}$$Cd using liquid scintillation counter

Ito, Chihiro; Tanaka, Yasuyuki; Kurosawa, Kiyoko*; Motoki, Yoshiaki*; Do, V. K.; Furuse, Takahiro

no journal, , 

In this presentation, an HCl-free analytical method for $$^{113m}$$Cd in aqueous solution samples containing multiple radionuclides by liquid scintillation counting is reported. We aimed to develop a chemical separation procedure of $$^{113m}$$Cd from co-existing nuclides such as $$^{60}$$Co and/or $$^{55}$$Fe, which interfere with the beta-counting. The use of hydrochloric acid (HCl) was avoided to prevent facilities from corrosion. Accordingly, after a sample-matrix separation with a chelating disk, Cd was adsorbed on a cation exchange resin and then selectively eluted by sodium thiosulfate (Na$$_{2}$$S$$_{2}$$O$$_{3}$$), which has a high affinity for Cd. This developed method allowed the separation and purification of Cd from the sample matrix without the use of halogen acids.

Oral presentation

Development of measurement method of $$^{236}$$U using ICP-MS/MS

Tanaka, Yasuyuki; Do, V. K.; Motoki, Yoshiaki*; Ota, Yuki; Iwahashi, Hiroyuki; Kurosawa, Kiyoko*; Furuse, Takahiro

no journal, , 

We examined the measurement method of $$^{236}$$U using triple-quadrupole inductively coupled plasma-mass spectrometry (ICP-MS/MS, Agilent 8900). The measurable mass to charge ratio (m/z) is expanded up to 275, the device can measure $$^{236}$$U$$^{16}$$O$$^{16}$$O (m/z = 268) generated by the reaction with $$^{16}$$O, which was used as a reaction gas. This mass shift mode decreased the interference from hydride of $$^{235}$$U compared to the previously reported analytical method, which improved limit of detection of $$^{236}$$U using ICP-MS/MS. In this presentation, the optimized measurement condition of $$^{236}$$U measured at m/z = 268 by ICP-MS/MS is reported.

Oral presentation

Development of analytical method of $$^{129}$$I and $$^{36}$$Cl for radioactive rubbles

Ota, Yuki; Kurosawa, Kiyoko*; Motoki, Yoshiaki*; Do, V. K.; Furuse, Takahiro

no journal, , 

We have developed an analytical method of $$^{129}$$I (half-life: 1.57x10$$^{7}$$ years) and $$^{36}$$Cl (half-life: 3.01x10$$^{5}$$ years) in various radioactive rubbles generated by decommissioning of the Fukushima Daiichi Nuclear Power Plant (1F). A sequential chemical separation procedure has been developed to isolate the nuclides from the sample matrix, followed by the quantification by inductively coupled plasma-mass spectrometry (ICP-MS/MS) and liquid scintillation counting (LSC), respectively.

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