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Journal Articles

Thermal-hydraulic analyses of the High-Temperature engineering Test Reactor for loss of forced cooling at 30% reactor power

Takamatsu, Kuniyoshi

Annals of Nuclear Energy, 106, p.71 - 83, 2017/08

The HTTR, which is the only HTGR having inherent safety features in Japan, conducted a safety demonstration test involving a loss of both reactor reactivity control and core cooling. The paper shows thermal-hydraulics during the LOFC test at an initial power of 30% reactor power (9 MW), when the insertion of all control rods was disabled and all gas circulators were tripped to reduce the coolant flow rate to zero. The analytical results could show that the downstream of forced convection caused by the HPS pushes down the upstream by natural convection in the fuel assemblies; however, the forced convection has little influence on the core thermal-hydraulics without the reactor outlet coolant temperature. As a result, the three-dimensional thermal-phenomena inside the RPV during the LOFC test could be understood qualitatively.

Journal Articles

Effect of air-oxidation on the thermal diffusivity of the nuclear grade 2-dimensional carbon fiber reinforced carbon/carbon composite

Sogabe, Toshiaki; Ishihara, Masahiro; Baba, Shinichi; Tachibana, Yukio; Yamaji, Masatoshi*; Iyoku, Tatsuo; Hoshiya, Taiji*

Materials Science Research International, 9(3), p.235 - 241, 2003/09

2D-C/C composite is one of the promising materials as a next-generation core material in gas-cooled reactors. Effect of air-oxidation on the thermal diffusivity up to 1673K of the 2D-C/C composite was investigated. The C/C composite specimens for measurement of thermal diffusivity were oxidized from 1 to 11 percent weight loss in air at 823K. Thermal diffusivity at room temperature declined 10$$sim$$20 percent for parallel to lamina direction and 5$$sim$$9 percent for that of perpendicular within 11 percent weight loss by oxidation. Thermal diffusivity tended to decrease gradually as the increase of oxidation loss in parallel to lamina, however, it decreased in the beginning of oxidation pretty much and not so changed by further oxidation loss in perpendicular to lamina. Change in thermal conductivity under oxidation condition was also estimated.

JAEA Reports

Study on impurity radiation and transport of JT-60U plasmas

Ishijima, Tatsuo

JAERI-Research 2000-015, p.94 - 0, 2000/03

JAERI-Research-2000-015.pdf:3.4MB

no abstracts in English

JAEA Reports

JAEA Reports

Thermal-hydraulic conceptual design of the multiple purpose research reactor MEX-15

M.A.Lucatero*; Kaminaga, Masanori

JAERI-M 94-006, 38 Pages, 1994/02

JAERI-M-94-006.pdf:1.27MB

no abstracts in English

Journal Articles

Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3

Hirano, Masashi; Sudo, Yukio

Journal of Nuclear Science and Technology, 23(4), p.352 - 368, 1986/00

 Times Cited Count:20 Percentile:86.58(Nuclear Science & Technology)

no abstracts in English

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