本文選題：空間反應(yīng)堆 + 熱管　； 參考：《核動(dòng)力工程》2016年05期

【摘要】：以典型熱管冷卻空間反應(yīng)堆(SAIRS)為對(duì)象,針對(duì)其各個(gè)模塊進(jìn)行建模,研制了基于SAIRS的系統(tǒng)瞬態(tài)計(jì)算程序(TAPIRS),并用該程序分析了反應(yīng)堆的3種典型瞬態(tài)工況。計(jì)算結(jié)果表明:在控制鼓故障引入極大反應(yīng)性、堿金屬熱電轉(zhuǎn)換裝置(AMTEC)部分失效和散熱板喪失部分散熱面積事故工況下,燃料溫度控制在安全限值以內(nèi),驗(yàn)證了反應(yīng)堆系統(tǒng)在事故工況下具有應(yīng)對(duì)單一故障和自穩(wěn)自調(diào)的能力。
[Abstract]:Taking the typical heat pipe cooled space reactor (SAIRS) as an object, the system transient calculation program based on SAIRS was developed, and three typical transient conditions of the reactor were analyzed. The calculation results show that the fuel temperature is controlled within the safety limit under the condition of introducing great reactivity into the control drum fault, partial failure of the alkali metal thermoelectric conversion device AMTECs and the loss of part of the heat dissipation area of the heat exchanger. It is verified that the reactor system has the ability to deal with single fault and self-stabilization and self-adjustment under the accident condition.
【作者單位】： 中國(guó)核動(dòng)力研究設(shè)計(jì)院核反應(yīng)堆系統(tǒng)設(shè)計(jì)技術(shù)重點(diǎn)實(shí)驗(yàn)室;西安交通大學(xué)核科學(xué)與技術(shù)學(xué)院;
【分類號(hào)】：TL364.4
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本文編號(hào)：1923127