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Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR)

机译:Thor基先进CANDU反应堆(TACR)的热工水力设计和分析

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The application of thorium fuel in advanced CANDU (CANadian Deuterium Uranium) reactors is an economic solution to sustainable development of nuclear energy. In this paper, the thermal hydraulic design and transient analysis of Thorium-based Advanced CANDU Reactor (TACR) heat transport system are conducted using self-programmed code CANTHAC (CANDU Thermal Hydraulic Analysis Code). In the code CANTHAC, the single channel model and the point kinetics model are adopted to simulate the core thermal hydraulic and neutronic behaviors. A distributed parameter model is adopted in the simulation of integral economizer U-tube steam generator (IEUTSG). Multi-region non-equilibrium model is applied to simulate the pressurizer. The characteristics of heat transport pumps were simulated by four-quadrant analogy curves. The code is verified with ACR-700 steady-state analysis. The calculation results agreed well with ACR-700 design values and the relative errors are all within 2%. With CANTHAC steady-state module, the preliminary thermal hydraulic design of TACR is conducted. A 1000 MW double loop reactor with 520 fuel channels is designed. Single loop mass flow rate was designed to be 3202 kg/s. Under the design scheme, the maximum cladding temperature and the maximum temperature are 340.2 degrees C and 1369.9 degrees C, which satisfied the design requirements. The transient analysis of TACR heat transport system was performed with CANTHAC transient module. SG feed water temperature reduction accident, and complete loss of Class IV accident were conducted. In the SG feed water temperature reduction accident, a new balance of neutron and thermal hydraulic is reached and the core power increases by 5% at last. In the complete loss of Class IV accident, the maximum fuel temperature reaches peak value at 1172 degrees C and still has some safety margin. The ROH (Reactor Outlet Header) pressure does not exceed 105% of the design value, which meet the safety criterion demand.
机译:advanced燃料在先进的CANDU(加拿大氘铀)反应堆中的应用是核能可持续发展的经济解决方案。本文利用自编程代码CANTHAC(CANDU热工水力分析代码)进行了Thor基高级CANDU反应堆(TACR)传热系统的热工水力设计和瞬态分析。在CANTHAC代码中,采用单通道模型和点动力学模型来模拟堆芯的热液和中子行为。整体节能器U型管蒸汽发生器(IEUTSG)的仿真采用分布式参数模型。应用多区域非平衡模型模拟增压器。通过四象限类比曲线模拟了传热泵的特性。该代码已通过ACR-700稳态分析验证。计算结果与ACR-700设计值非常吻合,相对误差均在2%以内。使用CANTHAC稳态模块,进行了TACR的初步热工液压设计。设计了具有520个燃料通道的1000 MW双回路反应堆。单回路质量流量设计为3202 kg / s。根据设计方案,最高包层温度和最高温度分别为340.2℃和1369.9℃,满足了设计要求。 TACR传热系统的瞬态分析是使用CANTHAC瞬态模块进行的。进行了SG给水温度降低事故和IV级事故的完全损失。在SG给水降温事故中,中子和热工水力达到了新的平衡,堆芯功率最终增加了5%。在完全丧失IV类事故的情况下,最高燃油温度在1172摄氏度时达到峰值,但仍具有一定的安全裕度。 ROH(反应器出口接头)压力不超过设计值的105%,符合安全标准要求。

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