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Calculation of Sodium Fire Test-I (Run-E6) using sodium combustion analysis code ASSCOPS version 2.0
Nakagiri, Toshio; Ohno, Shuji; Miyake, Osamu
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)1997
Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)1997
AbstractAbstract
[en] The calculation of Sodium Fire Test-I (Run-E6) was performed using the ASSCOPS (Analysis of Simultaneous Sodium Combustions in Pool and Spray) code version 2.0 in order to determine the parameters used in the code for the calculations of sodium combustion behavior of small or medium scale sodium leak, and to validate the applicability of the code. The parameters used in the code were determined and the validation of the code was confirmed because calculated temperatures, calculated oxygen concentration and other calculated values almost agreed with the test results. (author)
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Nov 1997; 175 p
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Report
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ALKALI METALS, BREEDER REACTORS, CHEMICAL REACTIONS, COMPUTER CODES, COOLING SYSTEMS, ELEMENTS, EPITHERMAL REACTORS, EVALUATION, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATHEMATICS, METALS, OXIDATION, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SODIUM COOLED REACTORS, TESTING
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