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JAEA Reports

Development of quick-response area-averaged void fraction meter; Application to BWR condition

Iguchi, Tadashi; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Research 2001-032, 111 Pages, 2001/05

JAERI-Research-2001-032.pdf:4.14MB

no abstracts in English

JAEA Reports

Development and validation of Multi-DimensionaI sodium combustion analysis code AQUA-SF

Takata, Takashi; Yamaguchi, Akira

JNC TN9400 2000-065, 152 Pages, 2000/06

JNC-TN9400-2000-065.pdf:6.26MB
JNC-TN9400-2000-065(errata).pdf:0.12MB

ln the liquid metal fast reactor (LMFR) using liquid sodium as a coolant, it is important to evaluate the effect of the sodium combustion on the structure, etc. Most of the previous analytical works are based on a zone model, in which the principal variables are treated as volume-average quantities. Therefore spatial distribution of gas and structure temperatures, chemical species concentration are neglected. Therefore, a multi-dimensional sodium combustion analysis code AQUA-SF (Advanced simulation using Quadratic Upstream differencing Algorithm - Sodium Fire version) has been developed for the purpose of analyzing the sodium combustion phenomenon considering the multi-dimensional effect. This code is based on a multi-dimensional thermal hydraulics code AQUA that employs SIMPLEST-ANL method. Sodium combustion models are coupled with AQUA; one is a liquid droplet model for spray combustion, and the other is a flame sheet model for pool combustion. A gas radiation model is added for radiation heat transfer. Some other models necessary for the sodium combustion analysis, such as a chemical species transfer, a compressibility, are also added. ln AQUA-SF code, bounded QUICK method in space scheme and bounded three-point implicit method in time scheme are implemented. Verification analyses of sodium combustion tests shown in the following have been carried out. (1)pool combustion test (RUN-D1) (2)spray combustion test (RUN-E1) (3)sodium leakage combustion test (Sodium Fire Test-II) (4)smaII-scale leakage combustion test (RUN,F7-1) ln each verification analysis, good agreements are obtained and the validity of AQUA-SF code is confirmed.

Journal Articles

Development of standard components for remote handling

*; Kakudate, Satoshi; Nakahira, Masataka; *

J. Robot. Mechatron., 10(2), p.133 - 138, 1998/00

no abstracts in English

Journal Articles

Development of remote handling tools and equipment

Nakahira, Masataka; Oka, Kiyoshi; *; *; *; Oda, Yasushi*; Kajiura, Soji*; Yamazaki, Seiichiro*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.54 - 68, 1997/01

no abstracts in English

Journal Articles

Discharge of a laminar argon jet into stagnant air

Fumizawa, Motoo

Kerntechnik, 58(5), p.269 - 272, 1993/10

no abstracts in English

JAEA Reports

Numerical simulation on the Marangoni convection in the molten metal pool

Yokokawa, Mitsuo

JAERI-M 92-038, 69 Pages, 1992/03

JAERI-M-92-038.pdf:1.48MB

no abstracts in English

Journal Articles

Quick replacement technology using SMA driver for high load core elements of fusion reactor

*; *; *; *; *; *; Iida, Hiromasa; Hoshiya, Taiji; *; *; et al.

Fusion Technology 1988, p.1806 - 1810, 1989/00

no abstracts in English

Journal Articles

Compacting and element-quick-replaceable design of high power density fusion reactor

*; *; *; Okamoto, Yoshizo*; Hoshiya, Taiji; Takahashi, Akito*; *; *; *; *; et al.

Koshutsuryoku Mitsudo Kaku Yugoro Niokeru Yoso Kokan Gijutsu No Kiso Sekkei, 147 Pages, 1988/03

no abstracts in English

Journal Articles

The dose evaluation method emergency by using puff model combined with three-dimensional wind field

;

Nihon Genshiryoku Gakkai-Shi, 26(10), p.897 - 904, 1984/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Oral presentation

In situ observation of uranyl solution photoreduction reaction

Shiwaku, Hideaki; Kobayashi, Toru; Suzuki, Shinichi; Yaita, Tsuyoshi

no journal, , 

no abstracts in English

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