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JAEA Reports

The Second periodic safety review report of Tokai Reprocessing Plant

Shirai, Nobutoshi; Miura, Yasushi; Tachibana, Ikuya; Omori, Satoru; Wake, Junichi; Fukuda, Kazuhito; Nakano, Takafumi; Nagasato, Yoshihiko

JAEA-Technology 2016-007, 951 Pages, 2016/07

JAEA-Technology-2016-007-01.pdf:11.93MB
JAEA-Technology-2016-007-02.pdf:4.7MB

The periodic safety review of TRP is to confirm the safety activities and get effective additional measures the facility safety and its reliability. We implemented 4 items; for (1) evaluation of safety activity implementation, we confirmed we are adequately expanding its safety activities by the necessary documents and schemes. For (2) evaluation of status of safety activities reflecting the latest technical knowledges, we confirmed we reflect latest knowledges for improvement of safety and reliability. For (3) technical evaluation about aging degradation, we can keep the safety of the facilities important to safety and the sea discharge line, under assumption of the present maintenance, because of "focuses for aging degradation". For (4) planning measures about a 10-years-plan that the operator shall implement to keep the facility condition, by the technical evaluation, we found no additional safety plans into maintenance strategies.

Journal Articles

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake

Nakano, Takafumi; Sato, Fuminori; Shirozu, Hidetomo; Nakanishi, Ryuji; Fukuda, Kazuhito; Tachibana, Ikuya

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 57(1), p.14 - 20, 2015/01

no abstracts in English

JAEA Reports

The Periodic safety review report of Tokai Reprocessing Plant

Fukuda, Kazuhito; Tomioka, Kenichiro*; Omori, Satoru; Nakano, Takafumi; Nagasato, Yoshihiko

JAEA-Technology 2014-032, 566 Pages, 2014/11

JAEA-Technology-2014-032.pdf:32.45MB
JAEA-Technology-2014-032(errata).pdf:9.54MB

The Periodic Safety Review of TRP is assessment of the validity of safety activities in order to get assurance for continuous operation by adding effective items to extract and to execute for TRP safety. We performed 4 items; for (1) evaluation of safety activity at TRP, as we confirmed organization was ordered and managed. For (2) evaluation of status of safety activities reflecting the latest knowledge, we confirmed improvement of safety was continued adequately reflecting from the experience for safety. For (3) technical review on aging for the safety related structures, systems and components, we evaluated the guaranty of safety under assumption of continuous maintenance till the next Periodic Safety Review. For (4) establishment of long term maintenance program, we found no additional activities into maintenance programs, however, for several installations we established a plan and utilized them for reliability.

Journal Articles

High spatial resolution ZnO scintillator for an in situ imaging device in EUV region

Arita, Ren*; Nakazato, Tomoharu*; Shimizu, Toshihiko*; Yamanoi, Kohei*; Empizo, M.*; Hori, Tatsuhiro*; Fukuda, Kazuhito*; Minami, Yuki*; Sarukura, Nobuhiko*; Maruyama, Momoko; et al.

Optical Materials, 36(12), p.2012 - 2015, 2014/10

 Times Cited Count:7 Percentile:38.97(Materials Science, Multidisciplinary)

A single shot image of a ZnO crystal excited by the EUV laser of Kansai Photon Science Institute was captured. The evaluated EUV beam waist radii from the ZnO emission pattern along the horizontal and vertical axes are 5.0 and 4.7$$mu$$m, respectively. The expected focal spot size of EUV laser and the spatial resolution of the magnifier (including the Schwarzschild objectives and lenses) are however 1 and 4$$mu$$m, respectively. The discrepancy on the spatial resolutions is attributed to exciton diffusion. We estimated the ZnO exciton diffusion length from the effective decay time which is shortened by exciton-exciton collision quenching and which is dependence on excitation energy density. Our results indicate that the short lifetime of ZnO is required to improve the spatial resolution.

Journal Articles

Optimization for removal of ruthenium from nitric acid solution by volatilizing with electrochemical oxidation

Sato, Soichi; Endo, Noboru; Fukuda, Kazuhito; Morita, Yasuji

Journal of Nuclear Science and Technology, 49(2), p.182 - 188, 2012/02

 Times Cited Count:8 Percentile:58.08(Nuclear Science & Technology)

Electrochemical oxidation method, to oxidize nitrosyl ruthenium to the tetra-oxide and then to remove ruthenium to the gas phase, was studied to separate Ru from the high-level liquid waste (HLLW). We carried out the experiments to clarify the effects following fundamental conditions to the electric oxidation, which are (a) electrolyte temperature, (b) presence of promoter elements, (c) evaporation or reflux of condensed phase and (d) using or not using of diaphragm at counter electrode. We found the fast oxidation conditions as follows; (1) higher temperature; 95$$^{circ}$$C, (2) Ce coexistence; 3000 ppm and (3) usage of a diaphragm for counter electrode. However evaporation or reflux conditions do not directly affect the electrochemical oxidation efficiency. Electric oxidation rate was increased 3 times compared with 25$$^{circ}$$C, without Ce and diaphragm for counter electrode.

JAEA Reports

Criticality safety evaluation in Tokai Reprocessing Plant; High burn up LWR UO$$_{2}$$ spent fuel and ATR MOX spent fuel

Shirai, Nobutoshi; Inano, Masatoshi; Fukuda, Kazuhito; Kosaka, Ichiro; Yamanaka, Atsushi

JAEA-Research 2011-005, 95 Pages, 2011/03

JAEA-Research-2011-005.pdf:2.46MB

This report presents criticality safety evaluation of each equipment in Tokai Reprocessing Plant for two types of spent fuels, High burn up 4.2% enrichment U oxide spent fuel for light water reactor and U-Pu mixed oxide spent fuel for advanced thermal reactor. As a result, it was confirmed that the equipments were safe enough for two types of the spent fuels from view point of criticality safety of single unit and multiple units.

JAEA Reports

Inventories of high burn up LWR UO$$_{2}$$ spent fuel and ATR MOX spent fuel in Tokai Reprocessing Plant

Shirai, Nobutoshi; Inano, Masatoshi; Fukuda, Kazuhito; Kosaka, Ichiro; Yamanaka, Atsushi

JAEA-Research 2011-004, 60 Pages, 2011/03

JAEA-Research-2011-004.pdf:1.79MB

This report describes calculated results of inventory of radioactivity in the Tokai Reprocessing Plant with calculation code, based on initial conditions and nuclear data library. The inventories were compared with three types of spent fuels, High burn up U oxide for light water reactor, U-Pu mixed oxide for advanced thermal reactor and the design based fuel for Tokai Reprocessing Plant.

Journal Articles

Operating Experience and Future Plan of the Operation Testing Laboratory in The Tokai Reprocessing Plant

Fukuda, Kazuhito; Tanabe, Yoji; Nojiri, Ichiro

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.115 - 118, 2003/00

Operation Testing Laboratory (OTL) is an examination laboratory located in the Tokai Reprocessing Plant (TRP). It has provided many research results since 1972 and contributed to TRP in order to safety operation, troubleshooting, and new technology for future reprocessing. In this report, we present facility outline of the laboratory,the several experimental results and future plan.

JAEA Reports

The 4th technological meeting of Tokai Reprocessing Plant

; Maki, Akira; ; ; ; ; Fukuda, Kazuhito

JNC TN8410 2001-023, 188 Pages, 2001/11

JNC-TN8410-2001-023.pdf:30.98MB

"The 4th technological meeting of Tokai Reprocessing Plant (TRP)" was held in JNFL Rokkasyo site on octorber 11$$^{th}$$, 2001. The report contains the proceedings, transparancies and questionnaires of themeetin. This time, we reported about "Maintenance and repair results of Tokai Reprocessing Plant" based on technology and knowledge accumulated in Tokai Reprocessing Plant.

Journal Articles

None

Fukuda, Kazuhito; Ogata, Yoshiaki; Maki, Akira; ; ;

Donen Giho, (96), p.71 - 75, 1995/12

None

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 3; Volatilizing ruthenium with electrochemical oxidation

Fukuda, Kazuhito; Tomioka, Kenichiro; Endo, Noboru; Sato, Soichi; Yamagishi, Isao; Morita, Yasuji

no journal, , 

no abstracts in English

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 15; Separation of Ru by volatilizing with electrochemical oxidation

Fukuda, Kazuhito; Sato, Soichi; Moriya, Yoichiro; Tomioka, Kenichiro; Morita, Yasuji

no journal, , 

None

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 18; Recovery of RuO$$_{4}$$ gas by wet or dry process

Fukuda, Kazuhito; Endo, Noboru; Sato, Soichi; Moriya, Yoichiro; Morita, Yasuji

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 3; Detailed checkup and comprehensive evaluation of installations in TRP

Fukuda, Kazuhito; Tomioka, Kenichiro*; Tachibana, Ikuya; Shirai, Nobutoshi; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Integrity check of Tokai Reprocessing Plant after the Tohoku Region Pacific Coast Earthquake, 1; Background and outline

Nakano, Takafumi; Fukuda, Kazuhito; Sato, Fuminori; Kosaka, Ichiro; Nagasato, Yoshihiko

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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