發(fā)布時間：2018-03-01 19:18

  本文關(guān)鍵詞： 非能動 新型安全殼 熱工水力 melcor　出處：《哈爾濱工程大學(xué)》2013年碩士論文　論文類型：學(xué)位論文

【摘要】：安全殼作為反應(yīng)堆安全和包容放射性物質(zhì)的最后一道屏障，其完整性對于核電站及環(huán)境安全來說至關(guān)重要。而諸如大破口失水事故等冷卻劑喪失事故可能會威脅到安全殼的完整性。因此，研究安全殼內(nèi)可能發(fā)生的各種設(shè)計基準(zhǔn)事故，模擬所釋放的質(zhì)量能量在殼內(nèi)的行為變化，，計算安全殼內(nèi)溫度壓力等參數(shù)隨質(zhì)能不斷釋放而隨時間的變化情況尤其必要。 本文采用集總參數(shù)法，通過自主編制程序計算假想基準(zhǔn)事故下安全殼內(nèi)工質(zhì)參數(shù)隨時間的變化規(guī)律，程序的編制過程包括物理模型的建立、數(shù)值求解方案的確定、程序的調(diào)試以及編寫輸入卡利用melcor程序?qū)τ嬎愠绦蜻M(jìn)行可靠性驗證，驗證的結(jié)果證明自編制程序?qū)τ诎踩珰?nèi)工質(zhì)的行為模擬是可靠的。隨后分析了事故中可能產(chǎn)生的氫氣對于計算的影響、模擬了發(fā)生冷卻劑管道冷段雙端斷裂大破口失水事故、主蒸汽管道雙端斷裂事故時安全殼內(nèi)工質(zhì)的行為變化等。 將自編制程序與安全殼非能動冷卻系統(tǒng)(PCCS)程序進(jìn)行耦合，驗證開式非能動冷卻系統(tǒng)能夠有效排出事故下殼內(nèi)熱量，降低事故后殼內(nèi)壓力，維持安全殼完整性。計算并分析了不同初始條件下，PCCS與安全殼之間的換熱所受到的影響，以及安全殼內(nèi)工質(zhì)的行為變化。
[Abstract]:Safety shell as the final barrier to reactor safety and containment of radioactive material, its integrity is essential for the nuclear power plant and environmental safety. Such as loca and loss of coolant accident may be a threat to the integrity of the containment. Therefore, various design basis accident may occur on the containment of the behavior, the quality of energy the simulation of the release in the shell of the change, calculating the containment parameters such as temperature and pressure with the matter can continue to release and change with time are particularly necessary.
In this paper, using the lumped parameter method for computing through independent variation in containment of imaginary working fluid parameters with time base accident, establish procedures for the preparation process including the physical model, determine the numerical scheme, debugging program and write the input card to verify the reliability of the calculation program using the program MELCOR, verify the results since the proof of program for refrigerant containment behavior simulation is reliable. Then analyzes the possible accident of hydrogen for the calculation of the effect, simulated the coolant pipe cooling section doubletalk break loca, main steam pipe double end rupture accident of refrigerant containment and behavior change.
Since the program and the passive containment cooling system (PCCS) program for coupling, verify open passive cooling system can effectively discharge heat shell accident, reduce the pressure in the shell after the accident, to maintain the integrity of the containment. Calculated and analyzed under different initial conditions, the influence of heat transfer between PCCS and security. The shell, and the refrigerant inside the containment of behavioral changes.

【學(xué)位授予單位】：哈爾濱工程大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2013
【分類號】：TL364.3

【參考文獻(xiàn)】

相關(guān)期刊論文 前3條

1 俞冀陽,李坤,賈寶山;AC600非能動安全殼冷卻系統(tǒng)長期效應(yīng)分析[J];核動力工程;2002年03期

2 俞冀陽,賈寶山,鄭成武;非能動安全殼冷卻系統(tǒng)的一維分析程序PCCSAC-1D[J];核動力工程;1998年06期

3 卞洪興 ,駱偉;壓水堆核電站安全殼研究[J];核動力工程;1986年01期

本文編號：1553226