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JAEA Reports

Estimation of heat removal characteristics for air-cooler in HTTR

Tochio, Daisuke; Nakagawa, Shigeaki; Takada, Eiji*; Sakaba, Nariaki; Takamatsu, Kuniyoshi

JAERI-Tech 2003-097, 55 Pages, 2004/01

JAERI-Tech-2003-097.pdf:3.34MB

In high temperature engineering test reactor (HTTR) of 30 MW, the generated heat at reactor core is finally dissipated at the air-cooler (ACL) by way of the heat exchangers of the primary pressurized water cooler (PPWC) and the intermediate heat exchanger (IHX). Therefore, air temperature (secondary-side condition at ACL) is important factor for the heat removal capability of the reactor. Coping with the air temperature, stable reactor inlet temperature control is achieved by adjusting of ACL coolant temperature with coolant (pressurized water and air) flow rate. ACL heat removal characteristic was based on the previous operation data in rise-to-power test and in-service operation at HTTR. And evaluate heat removal capability at summertime air temperature as the most severe condition was estimated. As the result, it was confirmed that the rated power of 30 MW can be removed at the condition of summertime air-temperature.

Journal Articles

Rise-to-power test of the HTTR (High Temperature Engineering Test Reactor)

Fujikawa, Seigo; Okubo, Minoru; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.361 - 372, 2002/12

no abstracts in English

JAEA Reports

Irradiation tests report of the 35th cycle in "JOYO"

JNC TN9440 2000-008, 79 Pages, 2000/08

JNC-TN9440-2000-008.pdf:2.33MB

This report summarizes the operating and irradiatlon data of the experimental reactor "JOYO" 35th cycle. Irradiation tests in the 35th cycle are as follows: (1)C-type irradiation rig (C4F) (a)High burnup performance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (2)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (3)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (4)Structure Materials Irradiation Rigs (SMIR) (a)Decision of material design base standard of structure materials for prototype reactor and large scale reactor (5)Upper core structure irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect (6)SurVeillance un-instrument Irradiation Rig (SVIR) (a)Confimation of surveillance irradiation condition for "JOYO" (b)Material irradiation tests (based on a contract with universities) The maximum burnup driver assembly "PFD253" reached 67,600 MWd/t (pin average).

Journal Articles

Design study of helium turbine for the 300MW HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; Fukuyama, Yoshitaka*; Okumoto, Junji*; Kishibe, Tadaharu*; Yamada, Seiya*

Proceedings of 45th ASME International Gas Turbine & Aeroengine Technical Congress, Exposition and Users Symposium (CD-ROM), 8 Pages, 2000/00

no abstracts in English

JAEA Reports

None

Terano, Toshihiro; ; Terunuma, Seiichi

PNC TN9410 91-325, 71 Pages, 1991/10

PNC-TN9410-91-325.pdf:1.74MB

None

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN9360 91-002, 110 Pages, 1991/08

PNC-TN9360-91-002.pdf:4.67MB

no abstracts in English

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN9360 91-001, 83 Pages, 1991/01

PNC-TN9360-91-001.pdf:3.6MB

no abstracts in English

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