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PNC TN9410 94-061, 126 Pages, 1994/02
The computer code TRACER has been developed to evaluate the species and quantities of fission products (FPs) released into the cover gas in an LMFBR during the fuel pin failure accidents (In-vessel source term). In this fiscal year, analytical models for the following key phenomena were developed and were coded in the code, which had been proposed from the results of sample calculations in last fiscal year. (a)Aerosol behavior in a bubble, (b)bubble behavior near the surface between cover gas and coolant, and (c)behavior of coolant temperature change. The fundamental functions of these models were validated by conducting sample calculations for the analyses of MOL7C/6 in-pile source term experiment and out-of-pile experiment for xenon-iodine mixed gas bubble behavior in liquid sodium. However, the calculational results by the above models could not reproduce the iodine decrease behavior within the bubble during the bubble rising in the out-of-pile experiment. Therefore, it is necessary to consider another mechanism in transport phenomena of iodine from the xenon-iodine mixed gas bubble into the sodium.
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PNC TN9410 93-015, 163 Pages, 1993/01
To evaluate the species and quantities of fission products (FPs) released into the cover gas in an LMFBR during the fuel pin failure accidents (In-vessel Source Term), the computer code TRACER (Transport phenomena of Radionuclides for Accident Consequence Evaluation of Reactor) has been developed. The code can analyze mechanistically the physical and chemical phenomena of FPs release and transport behavior from the failed fuel to the cover gas through sodium coolant. The code validation was performed through the sample calculations for the results of Mo17C/6 in-pile source term experiment. In the beginning of this study, the production and transport phenomena of bubbles of the noble gas and volatile FPs in the coolant, and mass transfer between the bubble and coolant were investigated, and the functions needed for the code were clarified. After that, several mechanistic models for the bubble behavior were developed, and the programs were coded. From the results of the sample calculations, it was confirmed that the code was capable of simulating the FP transport phenomena in the primary system.
Seino, Hiroshi; Ohno, Shuji; Miyahara, Shinya; ; Miyake, Osamu
Int.Top.Mtg.on Sodium Cooled Fast Reactor, ,
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; Miyahara, Shinya
Technical Committee Meeting on "Evaluation of Radioactive Materials and Sodium Fires in Fast Reactor", ,
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