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Journal Articles

Upgrading Program of the Experimental Fast Reactor Joyo

; Yogo, Shizuhide

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), (487), 492 Pages, 2001/04

The experimental fast reactor Joyo finished its operation as an irradiation core in June, 2000. Throughout the operation of MK-I (breeder core)and MK-II (irradiation core),the net operation time has exceeded 60,000 hours. During these operations there were no fuel failures or serious plant problems. The MK-III modification program will improve irradiation capability to demonstrate advanced technologies for commercial Fast Breeder Reactor (FBR). When the MK-III core is complete, it will support irradiation tests in feasibility studies for reactor for reactor and related fuel cycle research and development in Japan.

Journal Articles

Reaction rate distribution measurement and the core performance evaluation in the prototype FBR Monju

Usami, Isao; Suzuoki, Zenro; ; Nakashima, Fumiaki

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

Adiabatic Flame Temperature of Sodium Combustion and Sodium-Water Reaction

Okano, Yasushi; Yamaguchi, Akira

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

A Study on Corrosion Mechanism of FBR Structural Material in Small Sodium Leak under Insulator

Furukawa, Tomohiro; Rosanval, S.*; Latge, C.*

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

ACE-3D code analyses of multi-dimensional boiling flow in horizontal PCCS water pool

Onuki, Akira; Nakamura, Hideo; Anoda, Yoshinari; Obata, Hiroyuki*; Saishu, Sadanori*

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 10 Pages, 2001/00

A passive containment cooling system (PCCS) is under planning to use in a next-generation-type BWR for long-term cooling by condensing steam using horizontal heat exchangers. Heat transfer behavior in a secondary water pool is one of important phenomena governing heat removal performance of the PCCS. Boiling and condensation can be supposed under high heat flux regions and the two-phase natural circulation might enhance the heat transfer due to an increase of flow rate and a flow agitation. However, some heat transfer tubes might be covered only by steam and the heat transfer is degraded in such region (Steam-blanket effect). This study evaluated the characteristics of the heat transfer behavior in the secondary water pool by multi-dimensional two-fluid model code ACE-3D. It was found from the analyses that no any heat transfer tubes are covered only by steam and the heat transfer is enhanced due to the nucleate boiling and the increase of local liquid flow rate.

Journal Articles

Simulation of two-phase flows and numerical evaluation of interfacial area

Watanabe, Tadashi; Ebihara, Kenichi

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 10 Pages, 2001/00

no abstracts in English

Journal Articles

THE REACTION RATEN DISTRIBUTION MEASUREMENT AND THE CORE PERFORMANCEEVALUATION IN THE PROTOTYPE FBR MONJU

Usami, Isao; ; Nakashima, Fumiaki;

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

Mechanistic SIMMER-3 Analyses of Severe(ADS)Transients in Accelerator Driven Systems

Yamano, Hidemasa; ; ; Fujita, Satoshi

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

Modeling of Thinning Process of Structures in Temperature Analysis and its Verification

Tsukimori, Kazuyuki

Vol.2 ICONE-9 No.711, 2(711), 0 Pages, 2001/00

None

Journal Articles

None

Hasegawa, Misao

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), , 

None

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