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Journal Articles

Phenix to Monju; FBR development and Japan role, 1; Incident in development of FBR and its effect on the development

Konomura, Mamoru

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 53(3), p.211 - 214, 2011/03

It is not too much to say that R&D people have common sense to manage incidents in development of FBR with a method of risk analysis. In order to avoid an accident from some incidents, a reactor plant is designed with a way of defense in depth and a concept of multiple function and diversity in the design phase and is constructed and operated with enhancement of its reliability. Actually it is impossible to avoid any mechanical incidents. But the reliability can be enhanced by these incidents with appropriate risk management. In this sense, incidents are valuable for development of FBR. We should pay attention to developer's attitude how he understand incidents and how he improve his system on condition that he keeps transparency of information to public.

Oral presentation

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 6; Isothermal temperature coefficient measurement

Mori, Tetsuya; Morohashi, Yuko; Maruyama, Shuhei; Kasahara, Hideyuki; Yabuki, Kentaro; Okawachi, Yasushi

no journal, , 

no abstracts in English

Oral presentation

Development of advanced component toward the demonstration reactor of JSFR

Shimazaki, Masanori; Hayafune, Hiroki; Futagami, Satoshi; Enuma, Yasuhiro*; Kawamura, Masaya*; Ogumo, Shinya*

no journal, , 

no abstracts in English

Oral presentation

Systematic analysis of (d,xn) and (d,xp) breakup reactions for energies up to 100 MeV

Watanabe, Yukinobu*; Ye, T.*; Hashimoto, Shintaro; Ogata, Kazuyuki*; Yahiro, Masanobu*

no journal, , 

no abstracts in English

Oral presentation

Development of elevated temperature materials technology toward the demonstration reactor of JSFR, 3; Development of tube sheet and double wall tube made of high chrome steel for JSFR steam generator

Futagami, Satoshi; Nagae, Yuji; Wakai, Takashi; Kurome, Kazuya*; Toyoshi, Akira*; Enuma, Yasuhiro*; Koyama, Yoichi*; Kajikawa, Koji*; Aizawa, Taiki*; Miki, Kazuhiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of Super-COPD code for plant dynamics, 8; Development of Monju safety analytical model

Yamada, Fumiaki; Minami, Masaki*

no journal, , 

A computational model to simulate integrated behaviors of a reactor core and the connected heat transport system was built and verified by trial calculations on a set of representative anomaly transient event, in order for application of the plant dynamics analysis code Super-COPD to evaluation of the cooling capability of Monju reactor core.

Oral presentation

Study on evaluation of confinement capability of fuel cycle facility

Abe, Hitoshi; Kashima, Takao; Tashiro, Shinsuke; Uchiyama, Gunzo; Tsuchino, Susumu*; Ishibashi, Takashi*

no journal, , 

In Japan Atomic Energy Agency, to contribute on confirmation of safety of fuel cycle facilities, evaluation method for soundness of confinement capability of the facilities under fire accident has been investigated. Panel materials of Glove-box and cable sheath materials were considered to be an examination object as the representative organic materials in the facilities. Combustion property data, such as mass loss rate of the materials and soot generation ratio, and clogging property data of HEPA filter with combustion of the materials were measured as a parameter with radiation heat given to the materials, supply flow rate to the materials and oxygen concentration in the supply flow. Furthermore, progress of rising differential pressure of HEPA filter under concrete scenario of fire accident was evaluated by connecting these data mutually.

Oral presentation

Radiation-induced radical reaction at the interface between water and silica

Kumagai, Yuta; Nagaishi, Ryuji; Yamada, Reiji; Muroya, Yusa*; Katsumura, Yosuke*

no journal, , 

In the coexistent system of water and solid oxides, change in the radiation effect on water has been observed. To understand the characteristic reaction leading to the peculiar radiation effect, the transient behavior ob radicals produced in water radiolysis was measured in aqueous solution containing colloidal silica particles by pulse radiolysis technique. The time-resolved measurement on the kinetics of the reaction of OH radical with ferrocyanide ion revealed that a scavenging reaction of OH radical occurs in the presence of colloidal silica. The reactivity of the OH radical scavenging increased approximately in proportion to the surface area of the colloidal silica and was dependent on pH of aqueous solution. These results suggest that OH radical scavenged at the interface between water and silica. Therefore the reaction pathway of OH radical at the interface is expected to be different from that in bulk water.

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 1; Summary

Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 2; Criticality, control rod worth measurement

Yabuki, Kentaro; Kitano, Akihiro; Fukushima, Masahiro; Miyagawa, Takayuki; Okawachi, Yasushi

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 3; Evaluation of neutron source

Kato, Yuko; Miyagawa, Takayuki; Kageyama, Takeshi; Okimoto, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 4; Neutron instrumentation soundness measurement

Takano, Kazuya; Miyagawa, Takayuki; Ikegami, Kazunori; Kitano, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 5; Applicability of sub-criticality measurement methods

Kitano, Akihiro; Mori, Tetsuya; Nagata, Akito*; Saito, Kosuke; Misawa, Tsuyoshi*; Tamagawa, Yoichi*

no journal, , 

no abstracts in English

Oral presentation

Source term evaluation in containment vessel during late phase of severe accident, 18; Experiment on organic leach from paint in the containment vessel

Moriyama, Kiyofumi; Chiba, Noriaki; Tashiro, Shinsuke; Nakamura, Hideo; Nakamura, Koichi*

no journal, , 

Regarding the organic iodine production during a severe accident of light water reactors, the organic solvent leaching from paints has drawn attention as an important organic source. We measured the amount of organic solvent leaching from epoxy paint as time series data and examined its dependence on temperature, paint thickness and age. We developed also a leach behavior model considering equilibrium between the concentrations in the paint matrix and in the solution.

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 7; Coolant flow coefficient measurement

Morohashi, Yuko; Mori, Tetsuya; Maruyama, Shuhei; Kasahara, Hideyuki; Yabuki, Kentaro; Okawachi, Yasushi

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 8; Feedback reactivity measurement

Miyagawa, Takayuki; Kitano, Akihiro; Muranaka, Makoto; Kato, Mitsuya*; Okawachi, Yasushi

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 9; Summary of calculation results

Hazama, Taira; Kageyama, Takeshi; Hikichi, Takuo*; Okawachi, Yasushi; Suzuki, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Thermal-hydraulic tests for downward vapor-water two-phase flow in large diameter pipe, 2; Measurement of void fraction distribution by wire-mesh sensor

Katono, Kenichi; Nagayoshi, Takuji; Tamai, Hidesada; Takase, Kazuyuki; Ito, Takashi

no journal, , 

no abstracts in English

364 (Records 1-20 displayed on this page)