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Journal Articles

Cooling performance of cooling panel in modular HTGR

Takada, Shoji; Inagaki, Yoshiyuki; Suzuki, Kunihiro; ; Wada, Hozumi*; *

Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants, p.P1.2-1 - P1.2-7, 1993/00

no abstracts in English

Journal Articles

Thermal transient analysis for structural integrity of high temperature components in HTTR

Hada, Kazuhiko; Fujimoto, Nozomu; Sudo, Yukio; Wada, Hozumi*

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.291 - 298, 1991/00

no abstracts in English

JAEA Reports

Two-dimensional thermal analysis code "TAC-NC" for high temperature engineering test reactor and its verification

Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Suzuki, Katsuo; Wada, Hozumi*; Hirano, Mitsumasa

JAERI-M 89-001, 34 Pages, 1989/02

JAERI-M-89-001.pdf:0.86MB

no abstracts in English

JAEA Reports

JOYO 75MWt Start-up test report; PT-12 Heat transfer characteristics of IHX and DHX

Doi, Motoo*; Endo, Masayuki*; *; *; *; Wada, Hozumi*; Hirose, Tadashi*

PNC TN941 80-65, 269 Pages, 1980/05

PNC-TN941-80-65.pdf:48.51MB

The purpose of this test is to confirm that the heat transfer characteristics of the intermediate heat exchangers (IHX) and the dump heat exchangers (DHX) satisfy their design values. Each primary and secondary heat transport systems has two loops (A&B) and each secondary loop has two DHX's as terminal heat exchangers. The IHX/DHX heat transfer characteristics are measured under normal steady-state operating conditions (at 25, 40, 50, 65 and 75MWt), and also under special steady-state conditions (low sodium temperature, low secondary sodium flow rate) The major test results were : (1)The heat transfer coeffients of the IHX's and the DHX's measured in the reactor power range of 50 to 75 MWt closely matched predicted values. (2)The pressure drop in the DHX air flow, duct based on measured blower outlet pressure was less than the predicted value. This report presents the results of these plant tests.

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