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Journal Articles

Progress of demonstration experiment on irradiation of vibro-packed MOX fuel assemblies in the BN-600 reactor

Mayorshin, A. A.*; Skiba, O. V.*; Bychkov, A. V.*; Kisly, V. A.*; Shishalov, O. V.*; Krukov, F. N.*; Novoselov, A. E.*; Markov, D. V.*; Green, P. I.*; Funada, Toshio; et al.

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 11 Pages, 2012/00

The paper presents progress results, including fabrication of vibropac MOX fuel pins and 21 FAs for fast reactor BN-600, irradiation parameters and PIE results. It is shown, that no violations of safe operation limits take place. The activities within the framework of the Demonstration experiment is based on the international cooperation and have been performed with the support and participation Russian and Japanese organizations RIAR, IPPE, OKBM, BNPP, MEXT, JAEA, PESCO. The goal of the experiment is to validate possibility of using vibropac MOX FA for weapon plutonium disposition.

Journal Articles

The Current status of the Russian surplus weapons plutonium disposition and its Japanese contribution

Funada, Toshio; Kawata, Norio; Senzaki, Masao

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 50(11), p.711 - 715, 2008/11

no abstracts in English

Journal Articles

The Current Status of Collaboration with Russian Institutes for Russian Surplus Weapons Plutonium Disposition

Funada, Toshio; Aratani, Kiyonori

Nihon Genshiryoku Gakkai-Shi, 44(6), p.473 - 480, 2002/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

None

Journal Articles

None

; Odo, Toshihiro; ; ;

Donen Giho, (83), P. 1, 1992/00

None

JAEA Reports

Preliminary experiment of boiling detection in the reactor vessel by acoustic method

*; ; ; ; Fukami, Akihiro*; *; Igawa, Kenichi*

PNC TN9410 91-175, 52 Pages, 1991/05

PNC-TN9410-91-175.pdf:0.75MB

An acoustic detection method is one of the FBR reactor core malfunction detection methods, and is regarded as being promising. In this study, the preliminary experiment of boiling detection by acoustic method was conducted at JOYO to measure the acoustic signal level and to investigate the applicability of the acoustic method. The experiment was performed on June 13 and 14, 1990 during the 8th periodic inspection of JOYO. The results obtained though the experiment are as follows: (1)Sodium bubbling (boiling) induced by the electric heater was detected as the fluctuation of temperature single of the thermocouple attached to surface of the electric heater. (2)Bubbling single of the acoustic detector could not be identified cleary because of the high background noise caused by the primary main pump vibration, sodium flow in the reacter vessel and the electric supply in the containment vessel. (3)The correlation between the signal of the acoustic detector or the fluctuation of temperature signal of the thermocouple and the flow rate of the primary loops was not ascertained. It became clear through this study that the validity of the reactor core malfunction detction by acoustic method depend on the peculiar noise level in the reactor vessel, and the reduction of noise is the subject for a future study.

JAEA Reports

Preliminary report on experiments, analyses and evaluations performed in reactor technology section, experimental reactor division; Quarterly report Vol.7, No.1

*; *

PNC TN9410 90-112, 76 Pages, 1990/07

PNC-TN9410-90-112.pdf:2.43MB

This report su㎜arizes results on experiments, analyses and evaluations performed by Reactor Technology Section, Experimental Reactor Division during April through June, 1990. Each result described in this report was reported as the internal memoranda of Reactor Technology Section, for further analyses, evaluations, and/or discussions. This report contains the following items. (1)Results of measurements, analyses and evaluations for nuclear characteristics of JOYO. (2)Results of measurements and analyses for the plant characteristics of JOYO. (3)Production and/or arrangements of analyses codes and their manual. (4)Analyses and evaluations on MK- III Core. (5)Miscellaneous results. The final report will be published for each program after further discussions, analyses and evaluations.

JAEA Reports

Preliminary report on experiments, analyses and evaluations performed in reactor technology section, experimental reactor division; Quarterly report Vol.6, No.1

Odo, Toshihiro; Arii, Yoshio*; *; *; *; Sone, Toru; *

PNC TN9410 89-118, 153 Pages, 1989/08

PNC-TN9410-89-118.pdf:3.32MB

This report summarizes results on experiments, analyses and evaluations performed by Reactor Technology Section, Experimental Reactor Division during April through June, 1989. Each result described in this report was reported as the internal memoranda of Reactor Technology Section, for further analyses, evaluations, and/or discussions. This report contains the following items. (1)Results of measurements, analyses and evaluations for nuclear characteristics of JOYO. (2)Results of measurements and analyses for the plant characteristics of JOYO. (3)Results of measurements and analyses of neutron flux, gamma ray and decay heat of JOYO. (4)Preparation of Construction Permit Amendment for the operational reliability tests of FBR fuel assembly. (5)Preparation of Construction Permit Amendment for spent fuel strage facility. (6)Results of study and development for analytical technic. (7)Production and/or arrangements of analyses codes and their manual. (8)Analyses and evaluations on MK-III Core. (9)Miscellaneous results. The final report will be published for each program after further discussions, analyses and evaluations.

JAEA Reports

Preliminary report on experiments, analyses and evaluations performed in reactor technology section, Experimental reactor division; Quarterly Report Vol.5, No.4

Odo, Toshihiro; Arii, Yoshio*; *; *; *; Sone, Toru; *

PNC TN9410 89-089, 185 Pages, 1989/05

PNC-TN9410-89-089.pdf:3.9MB

This report summarizes results on experiments, analyses and evaluations performed by Reactor Technology Section, Experimental Reactor Division during January through March, 1989. Each result described in this report was reported as the internal memoranda of Reactor Technology Section, for further analyses, evaluations, and/or discussions. This report contains the following items. (1)Results of measurements, analyses and evaluations for nuclear characteristics of JOY0. (2)Results of analyses and evaluations for core mechanics. (3)Results of measurements and analyses for the plant characteristics of JOYO. (4)Results of measurements and analyses of neutron flux, gamma ray and decay heat of JOYO. (5)Preparation of Construction permit Amendment for the operational reliability tests of FBR fuel assembly. (6)Preparation of Construction Permit Amendment for spent fuel strage facility. (7)Results of study and development for analytical technic. (8)Production and/or arrangements of analyses codes and their manual. (9)Analyses and evaluations oh MK-III Core. (10)Miscellaneous results. The final report will be published for each program after further discussions, analyses and evaluations.

JAEA Reports

None

Fukami, Akihiro*; *; *; *; *

PNC TN9520 89-025, 86 Pages, 1989/04

PNC-TN9520-89-025.pdf:1.91MB

None

Oral presentation

The Current status of the Russian surplus weapons plutpnium disposition and its Japanese contribution

Suzuki, Mitsutoshi; Funada, Toshio

no journal, , 

no abstracts in English

Oral presentation

The Status of the US and Russian surplus weapons plutonium disposition and its Japanese contribution

Funada, Toshio; Senzaki, Masao

no journal, , 

no abstracts in English

Oral presentation

Present status and future plan of the collaboration with Russia concerning vipac fuel

Funada, Toshio; Suzuki, Mitsutoshi; Senzaki, Masao

no journal, , 

The outline of the collaboration concerning to the plutonium disposition with Russian institutes on vipac fuels and the future plan will be presented in the conference. (one of the four series presentations)

12 (Records 1-12 displayed on this page)
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