田灣核電站線功率密度保護(hù)參數(shù)計(jì)算
發(fā)布時(shí)間：2019-05-10 02:55
【摘要】：田灣核電站(TNPS)堆內(nèi)核測量系統(tǒng)的54個(gè)中子溫度測量通道分成4組,每組通道將自給能探測器電流轉(zhuǎn)換為功率并通過擴(kuò)展計(jì)算獲得全堆芯的功率分布。電流轉(zhuǎn)換為功率的系數(shù)等參數(shù)由堆內(nèi)測量系統(tǒng)上層服務(wù)器計(jì)算獲得并傳遞給下層服務(wù)器。每個(gè)燃料組件最大線功率密度由周邊影響區(qū)域內(nèi)的4個(gè)中子溫度測量通道計(jì)算的線功率密度值加權(quán)平均得到,權(quán)重系數(shù)與自給能探測器到周邊影響區(qū)域內(nèi)燃料組件的距離有關(guān)。本文闡述這種由自給能探測器電流計(jì)算線功率密度保護(hù)參數(shù)的方法。該方法簡易、響應(yīng)及時(shí),且誤差小于5.7%,已成功應(yīng)用在田灣核電站運(yùn)行機(jī)組的實(shí)時(shí)在線保護(hù)中。
[Abstract]:The 54 neutron temperature measurement channels of the (TNPS) core measurement system of Tianwan Nuclear Power Station are divided into 4 groups, each group of channels converts the self-sufficient detector current into power and obtains the power distribution of the whole core by expansion calculation. The parameters such as the coefficient of current conversion to power are calculated by the upper server of the in-reactor measurement system and transferred to the lower server. The maximum linear power density of each fuel assembly is obtained by the weighted average of the linear power density calculated by the four neutron temperature measurement channels in the surrounding affected area, and the weight coefficient is related to the distance between the self-contained energy detector and the fuel assembly in the surrounding affected area. In this paper, the method of calculating linear power density protection parameters from the current of self-sufficient energy detector is described. This method is simple, timely and the error is less than 5.7%. It has been successfully applied to the real-time on-line protection of operating units in Tianwan Nuclear Power Station.
【作者單位】： 江蘇核電有限公司;
【基金】：國家國際科技合作專項(xiàng)資助項(xiàng)目(2011DFR60730)
【分類號】：TM623
[Abstract]:The 54 neutron temperature measurement channels of the (TNPS) core measurement system of Tianwan Nuclear Power Station are divided into 4 groups, each group of channels converts the self-sufficient detector current into power and obtains the power distribution of the whole core by expansion calculation. The parameters such as the coefficient of current conversion to power are calculated by the upper server of the in-reactor measurement system and transferred to the lower server. The maximum linear power density of each fuel assembly is obtained by the weighted average of the linear power density calculated by the four neutron temperature measurement channels in the surrounding affected area, and the weight coefficient is related to the distance between the self-contained energy detector and the fuel assembly in the surrounding affected area. In this paper, the method of calculating linear power density protection parameters from the current of self-sufficient energy detector is described. This method is simple, timely and the error is less than 5.7%. It has been successfully applied to the real-time on-line protection of operating units in Tianwan Nuclear Power Station.
【作者單位】： 江蘇核電有限公司;
【基金】：國家國際科技合作專項(xiàng)資助項(xiàng)目(2011DFR60730)
【分類號】：TM623
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1 邱德瑜;;讀者來信[J];化學(xué)學(xué)報(bào);1987年07期
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3 鄭\，
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