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Journal Articles

Structural integrity assessments of helium components in the primary cooling system during the safety demonstration test using the HTTR

Sakaba, Nariaki; Tachibana, Yukio; Nakagawa, Shigeaki; Hamamoto, Shimpei

Transactions of 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT-18), p.4499 - 4511, 2005/08

Safety demonstration tests using the HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for the VHTR, which is one of the Generation IV reactor candidates. The coolant flow reduction test by running down gas circulators, which is one of the safety demonstration tests, is a simulation test of anticipated transients without scram. During the coolant flow reduction test, temperature of the high-temperature helium components and chemistry in the primary circuit are changed rapidly. This paper describes the structural integrity assessments of helium components, e.g. helium pipes, heat exchangers, during the coolant flow reduction test. From the result of this evaluation, it was found that the helium components were kept their structural integrity during temperature and chemistry transient condition in the coolant flow reduction test from the reactor power at 30%. It was also confirmed by this assessment that the coolant flow reduction test will be able to perform with its enough safety margins from the reactor power at 100%.

Journal Articles

Air vent in water chamber and surface coating on liner slides concerning auxiliary cooling system for the high temperature engineering test reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; Okubo, Minoru; *

Nucl. Eng. Des., 185(2-3), p.229 - 240, 1998/00

 Times Cited Count:12 Percentile:68.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Seizure and wear characteristics of Hastelloy XR and titanium nitride coating in high temperature condition

Takeda, Takeshi; Kunitomi, Kazuhiko; *; *; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.417 - 420, 1995/00

no abstracts in English

Journal Articles

Thermal performance test of a coaxial double-tube hot-gas duct

Ioka, Ikuo; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Suzuki, Kunihiro

Nuclear Technology, 105, p.293 - 299, 1994/02

 Times Cited Count:2 Percentile:37.25(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal performance test of coaxial double tube hot gas duct

Ioka, Ikuo; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Shimomura, Hiroaki

Nihon Genshiryoku Gakkai-Shi, 32(12), p.1221 - 1223, 1990/12

 Times Cited Count:0 Percentile:0.32(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal diffusivity of internal insulation layer of HENDEL hot gas duct

; ; ; ; ; Sanokawa, Konomo

JAERI-M 85-056, 18 Pages, 1985/05

JAERI-M-85-056.pdf:0.43MB

no abstracts in English

JAEA Reports

Test Results of the Hot Gas Ducts of HENDEL

; ; *; ; ; ; Sanokawa, Konomo

JAERI-M 85-008, 20 Pages, 1985/02

JAERI-M-85-008.pdf:0.54MB

no abstracts in English

Journal Articles

Thermal performance test of the hot gas ducts of HENDEL

; ; ; Sanokawa, Konomo

Nucl.Eng.Des., 83, p.91 - 103, 1984/00

 Times Cited Count:4 Percentile:45.52(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Temperature Distribution Measurement in the Hot Gas Duct of HENDEL

; ; *; ; ; ; Sanokawa, Konomo

JAERI-M 83-082, 55 Pages, 1983/06

JAERI-M-83-082.pdf:2.31MB

no abstracts in English

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