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題 名 | IIST設施自發式爐心冷卻系統設計及事故分析研究=The Design and Accident Analysis for the IIST Facility with the Passive Core Cooling System |
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作 者 | 李堅雄; 張建業; 黃一鳴; 劉泰健; 張欽章; 洪文堂; | 書刊名 | 核子科學 |
卷 期 | 36:3 1999.06[民88.06] |
頁 次 | 頁178-196 |
分類號 | 449.2 |
關鍵詞 | 自發式爐心冷卻系統; 核能安全; 壓水式反應器; Passive core cooling system; Reactor safety; Pressurized water reactor; |
語 文 | 中文(Chinese) |
中文摘要 | 研究發展自發式爐心冷卻系統增進反應器運轉安全為廿一世紀核能電廠的主流。 本文首先陳述壓水式比例縮小安全測試設施 (IIST) 自發式爐心冷卻系統 (Passive Core Cooling System, PCCS) 之設計,其中包括爐心補水槽之安裝以替代傳統核能電廠之高壓注 水系統及自動降壓系統 (Automatic Depressurization System, ADS) 用來提供反應器冷卻 系統排汽降壓。其次,探討以 IIST 自發式爐心冷卻系統的熱流特性,及其處理核電廠冷管 與調壓槽小破口冷卻水流失事故 (SBLOCA) 及喪失二次側熱沉暫態事故,對爐心安全之影響 。實驗結果顯示 IIST 自發式爐心冷卻系統能有效的處理上述事故,使爐心維持長期冷卻。 最後本文以 RELAP5/MOD3.2 程式預估 IIST 自發式爐心冷卻系統處理冷管 SBLOCA 事故之 熱流現象。經由此對程式計算值與實驗量測值,可深入了解 RELAP5/MOD3.2 程式分析 PCCS 之能力。 |
英文摘要 | The passive design of nuclear power plant strikes a balance between the use of proven technology and new approaches. It can meet safety regulations and reliablity reguirements, and promote public confidence in nuclear energy. This paper describes the design of Passive Core Cooling System (PCCS) for INER Integral System Test (IIST) facility. It includes the core makeup tanks (CMT), which replace the high pressure injection system, and the automatic depressurization system, which consists of a series of valves that open in stages as the level in the core makeup tank drop. The small break LOCAs and loss of feedwater experiments were conducted at the IIST facility for investigating the thermal-hydraulic behaviors and accident management of the passive core cooling system. The experimental results show that the IIST facility passive core cooling system has the capability to maintain long term core cooling during the mentioned accidents. Finally, this paper presents the evaluation of the thermal-hydraulic code RELAP5/MOD3.2 against the IIST SBLOCA data to realize the code capability in analyzing the behavior of the passive core cooling system. |
本系統中英文摘要資訊取自各篇刊載內容。