Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 42

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute (FY2020)

Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi; Miyakoshi, Hiroyuki; Takamatsu, Misao; Sakamoto, Naoki; Isozaki, Ryosuke; Onishi, Takashi; et al.

JAEA-Review 2021-020, 42 Pages, 2021/10

JAEA-Review-2021-020.pdf:2.95MB

The disposal of radioactive waste from the research facility need to calculate from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Agency Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2020 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.

Journal Articles

Deexcitation dynamics of muonic atoms revealed by high-precision spectroscopy of electronic $$K$$ X rays

Okumura, Takuma*; Azuma, Toshiyuki*; Bennet, D. A.*; Caradonna, P.*; Chiu, I. H.*; Doriese, W. B.*; Durkin, M. S.*; Fowler, J. W.*; Gard, J. D.*; Hashimoto, Tadashi; et al.

Physical Review Letters, 127(5), p.053001_1 - 053001_7, 2021/07

 Times Cited Count:15 Percentile:79.06(Physics, Multidisciplinary)

We observed electronic $$K$$X rays emitted from muonic iron atoms using a superconducting transition-edge-type sensor microcalorimeter. The energy resolution of 5.2 eV in FWHM allowed us to observe the asymmetric broad profile of the electronic characteristic $$K$$$$alpha$$ and $$K$$$$beta$$ X rays together with the hypersatellite $$K$$$$alpha$$ X rays around 6 keV. This signature reflects the time-dependent screening of the nuclear charge by the negative muon and the $$L$$-shell electrons, accompanied by electron side-feeding. Assisted by a simulation, this data clearly reveals the electronic $$K$$- and $$L$$-shell hole production and their temporal evolution during the muon cascade process.

Journal Articles

Current status of the technology development on lithium safety handling under IFMIF/EVEDA

Furukawa, Tomohiro; Hirakawa, Yasushi; Kato, Shoichi; Iijima, Minoru; Otaka, Masahiko; Kondo, Hiroo; Kanemura, Takuji; Wakai, Eiichi

Fusion Engineering and Design, 89(12), p.2902 - 2909, 2014/12

 Times Cited Count:10 Percentile:59.32(Nuclear Science & Technology)

For the irradiation test of the candidate materials for the fusion DEMO reactor, Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) are performed under the Broader Approach Activities. As a major Japanese activity on the target facility of the IFMIF, the engineering validation using the EVEDA Lithium Test Loop which is the largest scale liquid lithium test loop has been started in 2012. In parallel with the design and fabrication, the research on the technology establishment for the lithium safety handling was started in 2008, as one of the related technologies under the IFMIF-EVEDA. In the research, experiments of lithium chemical reaction, experiments on lithium fire, establishment of chemical analysis of impurities in lithium and experiments on advanced lithium leak detection system were carried out. This paper describes the results of these experiments.

Journal Articles

Development of a high current H$$^{-}$$ ion source for cyclotrons

Eto, Haruhiko*; Aoki, Yasushi*; Mitsubori, Hitoshi*; Arakawa, Y.*; Mitsumoto, Toshinori*; Yajima, S.*; Sakuraba, Junji*; Kato, Takanori*; Okumura, Yoshikazu

Review of Scientific Instruments, 85(2), p.02B107_1 - 02B107_3, 2014/02

 Times Cited Count:10 Percentile:41.75(Instruments & Instrumentation)

High current hydrogen negative ion source is required to increase the accelerated beam current of the cyclotrons for many medical applications such as cancer therapy and medical radioisotope production. A new negative ion source has been designed and fabricated. The ion source is a multi-cusp type. Optimization of the ion source is in progress, such as the optimization of the magnetic filter which prevents high temperature electrons from entering into the negative ion production region, improvement of the extraction electrode's shape and configuration of dipole magnets etc. A small quantity of Cs has been introduced into the ion source to enhance the negative ion beam current. The ion source produced 16mA of DC hydrogen negative ion beam with the Cs-seeded operation at a low arc discharge power of 2.8 kW.

Journal Articles

Development of microwave ion source for industrial applications

Takahashi, Nobuaki*; Murata, Hirohiko*; Mitsubori, Hitoshi*; Sakuraba, Junji*; Soga, Tomohiro*; Aoki, Yasushi*; Kato, Takanori*; Saito, Yuichi; Yamada, Keisuke; Ikenaga, Noriaki*; et al.

Review of Scientific Instruments, 85(2), p.02C306_1 - 02C306_3, 2014/02

 Times Cited Count:2 Percentile:10.84(Instruments & Instrumentation)

Journal Articles

Corrosion of austenitic steel in leakage lithium

Furukawa, Tomohiro; Hirakawa, Yasushi; Kato, Shoichi

Fusion Engineering and Design, 88(9-10), p.2502 - 2505, 2013/10

 Times Cited Count:7 Percentile:47.83(Nuclear Science & Technology)

Lithium, which is used as the neutron source of the IFMIF, reacts with oxygen, nitrogen and moisture in atmosphere in case of the leakage accident. In this study, fundamental corrosion test was performed in order to obtain the corrosion behavior of austenitic stainless steel in the estimated lithium compounds. In the experiment, the lithium compounds were filled with the steel into the Tammann pipe made from Al$$_{2}$$O$$_{2}$$, and heated up to 850$$^{circ}$$C. After the test, the specimen was cleaned by alcohol, and then the weight loss measurement and metallurgical examination were performed. Intense corrosion was observed at the environmental conditions containing lithium peroxide. No corrosion was observed in Li$$_{2}$$O environment. According to the consideration based on thermodynamics, Li$$_{2}$$O cannot oxidize iron and lithium is reducing agent. Slight corrosion was observed in LiOH and Li$$_{3}$$N environments.

JAEA Reports

Monju system startup test report control rod reactivity worth measurements

Kato, Yuko; Yabuki, Kentaro*; Okawachi, Yasushi

JAEA-Technology 2013-018, 118 Pages, 2013/07

JAEA-Technology-2013-018.pdf:3.73MB

The prototype fast breeder reactor MONJU resumed the system startup test (SST) on May 6th 2010 after fourteen years and five months shutdown since the sodium leakage of the secondary heat transport system in December 1995 and reached criticality on May 8th. Core confirmation test (CCT) is the first step of SST which consists of three steps, and finished on July 22nd after 78 days test. Control rod reactivity worth measurements were carried out in order to calibrate the reactivity worth of control rods and back-up rods. In addition, we also aimed at a basic data acquisition for the control rod reactivity worth calibration.

Journal Articles

Safety concept of the IFMIF/EVEDA lithium test loop

Furukawa, Tomohiro; Kondo, Hiroo; Hirakawa, Yasushi; Kato, Shoichi; Matsushita, Izuru*; Ida, Mizuho; Nakamura, Kazuyuki

Fusion Engineering and Design, 86(9-11), p.2433 - 2436, 2011/10

 Times Cited Count:12 Percentile:65.69(Nuclear Science & Technology)

In order to obtain the engineering data on the lithium target system, which is the neutron source of the International Fusion Material Irradiation Facility (IFMIF), the design and fabrication of the IFMIF/EVEDA Lithium Test Loop are being carried out under the Engineering Validation and Engineering Design Activity (EVEDA). The loop will hold 2.5 tons of lithium. Since lithium is specified by Japanese law as a dangerous substance, countermeasures which assumed a lithium leak incident and various abnormal issues are indispensable. This paper describes about the safety principles and measures for lithium leaks of the IFMIF/EVEDA lithium test loop decided under the detailed design process.

Journal Articles

Update on lithium safety handling work

Furukawa, Tomohiro; Hirakawa, Yasushi; Kato, Shoichi; Kondo, Hiroo; Nakamura, Kazuyuki

Proceedings of 3rd IFMIF/EVEDA Workshop (Internet), 4 Pages, 2010/09

The object of this task, Development of Li safety handing technology in EVEDA LF-5, is to dedicate data needed for design relating safety and Li treatment and impurity monitoring. This task consists of (a) experiments of lithium fire, (b) chemical analysis of impurity in lithium and (c) experiments of lithium chemical reaction. The validation test on the lithium fire and the preliminary tests on lithium impurity and lithium chemical reaction were started in 2009. This paper describes the current status of the lithium safety handling task.

Journal Articles

Experimental study on fire-extinguishing of lithium

Furukawa, Tomohiro; Kato, Shoichi; Hirakawa, Yasushi; Kondo, Hiroo; Nakamura, Hiroo

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 6 Pages, 2010/05

The EVEDA lithium test loop is constructed at the Oarai Research and Development Center, Japan Atomic Energy Agency. Since lithium is specified as a dangerous substance by a Japanese law, the countermeasure which assumed the lithium combustion incident is indispensable. In this experimental study, the fire-extinguishing behavior of four kinds of fire extinguishers - dryness sand, pearlite, Natrex-L and Natrex-M - to burning lithium was examined. In addition, the effect of depth of lithium pool on the fire-extinguishing performance of the candidate fire extinguisher was investigated to determine the amount of the fire extinguisher placed at the EVEDA lithium test loop.

JAEA Reports

Basic experiment on fire-extinguishing of lithium

Kato, Shoichi; Furukawa, Tomohiro; Hirakawa, Yasushi; Kondo, Hiroo; Nakamura, Hiroo

JAEA-Technology 2009-059, 42 Pages, 2009/12

JAEA-Technology-2009-059.pdf:19.39MB

In order to obtain the engineering data of the lithium target system which is the neutron source of the International Fusion Material Irradiation Facility (IFMIF), design and fabrication of the liquid lithium test loop are carrying out under the Engineering Validation and Engineering Design Activity (EVEDA). Since lithium is specified as the dangerous substance by the Japanese law, the countermeasure which assumed the lithium combustion incident is indispensable. This report summarizes the results of basic experiment on fire-extinguishing of the lithium. In this experiment, the fire-extinguishing behavior of the fire extinguishers to the lithium was experimentally confirmed, and the fire extinguisher for the liquid lithium test loop is proposed. In addition, the fire-extinguishing performance for the determination of the amount of dispositions of the fire extinguisher was experimentally estimated.

JAEA Reports

Handling of HTTR second driver fuel elements in assembling and storage working

Tomimoto, Hiroshi; Kato, Yasushi; Owada, Hiroyuki; Sato, Nao; Shimazaki, Yosuke; Kozawa, Takayuki; Shinohara, Masanori; Hamamoto, Shimpei; Tochio, Daisuke; Nojiri, Naoki; et al.

JAEA-Technology 2009-025, 29 Pages, 2009/06

JAEA-Technology-2009-025.pdf:21.78MB

The first driver fuel of the HTTR (High Temperature Engineering test Reactor) was loaded in 1998 and the HTTR reached first criticality state in the same year. The HTTR has been operated using the first driver fuel for a decade. In Fuel elements assembling, 4770 of fuel rods which consist of 12 kinds of enrichment uranium are loaded into 150 fuel graphite blocks for HTTR second driver fuel elements. Measures of prevention of fuel rod miss loading, are employed in fuel design. Additionally, precaution of fuel handling on assembling are considered. Reception of fuel rods, assembling of fuel elements and storage of second driver fuels in the fresh fuel storage rack in the HTTR were started since June, 2008. Assembling, storage and pre-service inspection were divided into three parts. The second driver fuel assembling was completed in September, 2008. This report describes concerns of fuel handling on assembling and storage work for the HTTR fuel elements.

JAEA Reports

Ultrasonic test results for the reactor pressure vessel of the HTTR; Longitudinal welding line of bottom dome

Nojiri, Naoki; Owada, Hiroyuki; Kato, Yasushi

JAEA-Technology 2008-045, 38 Pages, 2008/06

JAEA-Technology-2008-045.pdf:6.95MB

This paper describes the inspection method, the measured area, etc. of the ultrasonic test of the in-service inspection (ISI) for welding lines of the reactor pressure vessel of the HTTR and the inspection results of the longitudinal welding line of the bottom dome. The pre-service inspection (PSI) results for estimation of occurrence and progression of defects to compare the ISI results is described also.

Journal Articles

Report of meetings of ITPA (International Tokamak Physics Activity), 19

Sasao, Mamiko*; Kusama, Yoshinori; Kawano, Yasunori; Kawahata, Kazuo*; Mase, Atsushi*; Sugie, Tatsuo; Fujita, Takaaki; Fukuda, Takeshi*; Fukuyama, Atsushi*; Sakamoto, Yoshiteru; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 83(9), p.779 - 782, 2007/09

This is a report of highlights from 2007 spring meetings of seven Topical Groups (TG) of International Tokamak Physics Activity (ITPA). In each meeting, high priority issues in physics of International Thermonuclear Experimental Reactor (ITER) and other burning plasma experiments have been discussed and investigated. Twenty-seven scientists from Japan have participated in those meetings. Dates and places of the meetings are shown below. (1) Diagnostics TG: 26-30 March, Princeton (USA), (2) Transport Physics TG: 7-10 May, Lausanne (Switzerland), (3) Confinement Database and Modeling TG: 7-10 May, Lausanne (Switzerland), (4) Edge Pedestal Physics TG: 7-10 May, Garching (Germany) (5) Steady State Operation TG: 9-11 May, Daejeon (South Korea), (6)MHD TG: 21-24 May, San Diego (USA), (7) Scrape-off-layer and Divertor Physics TG: 7-10 May, Garching (Germany).

Journal Articles

Design of pencil beam formation system for high-accuracy carbon-ion microsurgery

Arakawa, Kazuo; Oikawa, Masakazu*; Shimada, Hirofumi*; Kamiya, Tomihiro; Nakano, Takashi*; Yusa, Ken*; Kato, Hiroyuki*; Sato, Takahiro; Agematsu, Takashi; Kashiwagi, Hirotsugu; et al.

Proceedings of 4th Annual Meeting of Particle Accelerator Society of Japan and 32nd Linear Accelerator Meeting in Japan (CD-ROM), p.279 - 281, 2007/00

no abstracts in English

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meetings, 17

Asakura, Nobuyuki; Kato, Takako*; Nakano, Tomohide; Takamura, Shuichi*; Tanabe, Tetsuo*; Iio, Shunji*; Nakajima, Noriyoshi*; Ono, Yasushi*; Ozeki, Takahisa; Takechi, Manabu; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 82(7), p.448 - 450, 2006/07

no abstracts in English

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meeting, 15

Ninomiya, Hiromasa; Asakura, Nobuyuki; Kato, Takako*; Takamura, Shuichi*; Tanabe, Tetsuo*; Nakano, Tomohide; Iio, Shunji*; Ozeki, Takahisa; Ono, Yasushi*; Sugihara, Masayoshi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 81(11), p.960 - 961, 2005/11

no abstracts in English

Journal Articles

RDB system in J-PARC LINAC and its application to commissioning

Sako, Hiroyuki; Sakaki, Hironao; Takahashi, Hiroki; Yoshikawa, Hiroshi; Ito, Yuichi*; Kato, Yuko*; Kamikubota, Norihiko*; Sugimoto, Makoto*; Watanabe, Kazuhiko*; Ikeda, Hiroshi*; et al.

Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.462 - 464, 2005/07

Current status of the RDB system in J-PARC LINAC is presented. The machine database records static data of devices and the control system, whereas the operation log database records a history of operation parameters. The overall design of control flow among high-level applications, simulators, and database is described. Then results of a control test of the power supply for DTQ, and a prototype test of the operation log database in MEBT1 test bench at KEK are reported. In the end, a scheme to generate simulation configuration files from RDB is shown.

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meeting, 13

Kawano, Yasunori; Kawahata, Kazuo*; Kusama, Yoshinori; Sasao, Mamiko*; Sugie, Tatsuo; Mase, Atsushi*; Asakura, Nobuyuki; Kato, Takako*; Takamura, Shuichi*; Tanabe, Tetsuo*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 81(2), p.128 - 130, 2005/02

no abstracts in English

42 (Records 1-20 displayed on this page)