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Sudoh, Takashi; Murao, Yoshio; Iguchi, Tadashi; Sudo, Yukio; Sugimoto, Jun
Japan Atomic Energy Research Inst., Tokyo1979
Japan Atomic Energy Research Inst., Tokyo1979
AbstractAbstract
[en] To develop an analysis code, the purpose of the series 6 reflood experiment was as follows: 1) Overall reflood phenomena in a 4 x 4 array indirectly heated heater rod bundle. Sheathed thermocouples were completely embedded in the heater rod cladding. 2) Quench characteristics at low flooding rate. 3) Differential pressure response in the core. 4) Heat transfer coefficients downstrem of the quench point. 5) Water effluence behavior at outlet of the core. 6) Effect of non-heated rod in the core. 7) System response under intermittent-flow-rate core forced injection. The tests were in three groups, according to the water injection methods to the core: 1) constant-flow-rate core forced injection, 2) intermittent-flow-rate core forced injection, and 3) system effect test. By the tests, effects were studied of the core power, initial rod temperature, system pressure, inlet water subcooling, flooding rate and un-heated rod. This report presents the results of intermittent-flow-rate core forced injection tests and system effect tests. (author)
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Mar 1979; 270 p
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Report
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Numerical Data
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