【摘要】：乏燃料池作為過渡期暫時(shí)性的乏燃料儲(chǔ)存方式，在2011年3月11日本福島核泄漏事故后，其安全性作為新的議題引起人們廣泛關(guān)注，因此需要對(duì)核電廠乏燃料池喪失事故進(jìn)行細(xì)致的研究。 本文以系統(tǒng)程式RELAP5/MOD3為分析工具，建立核電廠乏燃料池模式，模擬全池?zé)崴餍袨椤ＤＪ礁鶕?jù)退出燃料的周期來劃分節(jié)點(diǎn)，詳細(xì)分析了包含最新退出燃料的格架區(qū)域并加入輻射傳熱模式。按美國(guó)核管會(huì)標(biāo)準(zhǔn)審查方案附的衰變熱功率計(jì)算式ABS-92計(jì)算核電廠乏燃料池中燃料產(chǎn)生的衰變熱。 基于已建立的乏燃料池模型，模擬了乏燃料池及冷卻系統(tǒng)正常運(yùn)轉(zhuǎn)下的穩(wěn)態(tài)工況，以及乏燃料池冷卻喪失下的瞬態(tài)工況。估算喪失冷卻事故發(fā)生后燃料裸露及包殼溫度升至2200°F的時(shí)間。分析了輻射傳熱模式、在放射性物質(zhì)外泄前灑水以及細(xì)分hot channel、格架外bypass區(qū)節(jié)點(diǎn)數(shù)劃分對(duì)燃料溫度變化趨勢(shì)的影響。 分析計(jì)算結(jié)果顯示，模式能夠模擬乏燃料池及其冷卻系統(tǒng)正常運(yùn)行下的穩(wěn)態(tài)工況，建立乏燃料池內(nèi)的自然對(duì)流冷卻機(jī)制；事故發(fā)生后燃料裸露所需的時(shí)間為17.87天，燃料包殼溫度達(dá)到2200°F的時(shí)間為19.14天；輻射傳熱模式將燃料包殼溫度到達(dá)2200°F的時(shí)間延遲了8.97小時(shí)；NEI06-12所建議的200gpm灑水量需要8630（s2.4hour）將燃料溫度由726.9°C降到100°C，如果將灑水量減至100gpm則需要遠(yuǎn)大于兩倍時(shí)間的36170s（10.05hour）將燃料溫度由726.9°C降到100°C；功率密度最高的區(qū)域節(jié)點(diǎn)劃分更細(xì)時(shí)，燃料包殼溫度到達(dá)2200°F的時(shí)間會(huì)提前6.3小時(shí)；格架外bypass區(qū)節(jié)點(diǎn)劃分更細(xì)時(shí)，燃料包殼溫度到達(dá)2200°F的時(shí)間會(huì)延后0.89小時(shí)。
[Abstract]:As a temporary storage mode of spent fuel during the transitional period, the safety of spent fuel pool has aroused widespread concern after the Fukushima nuclear accident on March 11, 2011. Therefore, it is necessary to study the loss of spent fuel pool in nuclear power plant. In this paper, the model of spent fuel pool in nuclear power plant is established by using the system program RELAP5/MOD3 as an analysis tool, and the hot water prevalence of the whole pool is simulated. The model is divided into nodes according to the period of exit fuel, the grid region including the latest exit fuel is analyzed in detail and the radiation heat transfer mode is added. The decay heat produced by the spent fuel cell of nuclear power plant is calculated by ABS-92 formula according to the decay heat power formula attached to the standard review program of the American Nuclear Regulatory Commission. Based on the established model of spent fuel tank, the steady state of spent fuel tank and cooling system under normal operation and the transient condition of spent fuel tank under cooling loss are simulated. The time of fuel exposure and cladding temperature rising to 2200 擄F after the loss of cooling accident was estimated. The effects of radiation heat transfer model, sprinkling water before radioactive material release and subdivision of bypass node points on fuel temperature change are analyzed. The results show that the model can simulate the steady state of the spent fuel tank and its cooling system under normal operation and establish the natural convection cooling mechanism in the spent fuel tank. After the accident, the time of fuel exposure is 17.87 days, the time of fuel cladding temperature reaching 2200 擄F is 19.14 days, the time of fuel cladding temperature reaching 2200 擄F is delayed by radiation heat transfer mode, the time of fuel cladding temperature reaching 2200 擄F is delayed by 8.97 hours. The 200gpm sprinkler recommended by NEI06-12 requires 8630 (s2.4hour) to reduce the fuel temperature from 726.9 擄C to 100 擄C. if the sprinkler is reduced to 100gpm, it will take 36170s (10.05hour) of much more than twice the time to reduce the fuel temperature from 726.9 擄C to 100 擄C. The time of fuel cladding temperature reaching 2200 擄F will be advanced by 6.3 hours when the highest power density zone node is further divided, and the time of fuel cladding temperature reaching 2200 擄F will be delayed by 0.89 hours when the node division of bypass zone outside the grid is more detailed.
【學(xué)位授予單位】：上海交通大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2013
【分類號(hào)】：TL364.4

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本文編號(hào)：2308345