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題名 | The Thermal-Hydraulic Analysis of a Passive Heat Removal System in Pool-Type Sodium Cooled Fast Reactors=被動式衰變熱移除系統應用於池式鈉冷卻反應器之熱流分析 |
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作者 | 洪祖全; 王曉剛; | 書刊名 | 核子科學 |
卷期 | 34:1 1997.02[民86.02] |
頁次 | 頁9-22 |
分類號 | 449.2 |
關鍵詞 | 被動式衰變熱移除系統; 池式鈉冷卻反應器; 熱流分析; RACS; DSNP; Passive decay heat removal; |
語文 | 英文(English) |
英文摘要 | Passive safety characteristics to increase performance margin have been widely applied in the design of advanced nuclear reactors. The first objective of this study is to model a system that rejects hear from a high temperature environment via the combination of thermal conduction, convection and rediation. During the shutdown heat removal mode, the temperature could be higher than 700 ℃. Several parameters are studied to assess the effect of uncertainty in reactor air cooling system (RACS) design variables on heat removal. The emissivity of the structure material and the ambient air temperature are such design variables. The greatest temperature gradient exists between the outer wall of the guard vessel and the air stream. It has been found that both of the material emissivity and gap width, between reactor and guard vessels, are the two most sensitive parameters to the heat removal of RACS. The Dynamic Simulator for Nuclear Power Plants (DSNP) code was successfully modified and employed to execte simulations of performance during decay heat removal in an advanced fast reactor. When RACS is the only system in heat rejection, the hot pool has a maximum temperature of 700 ℃ at 43 hours after scram. This tem perature is about 30 ℃ below the ASME service D condition. This DSNP result is ocmpared with that of Thermal Analyzer Program(TAP) code. The overall trend and result are nearly coincident. Emissivity of material and height of the fins were selected as parameters for the sensitivity study. Results indicate that safety requirement will not be met unless adequate value of these parameters were selected. |
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