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The fuel-self-sustaining RBWR-Th core concept and parametric studies

机译:燃料自给自足的RBWR-Th核心概念和参数研究

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This study searches for the optimal fuel assembly design for the RBWR-Th core - a reduced-moderation BWR which is fuel-self-sustaining. Except for the initial fuel loading, it is charged with only thoria and discharges only fission products, recycling all actinides (with the exception of actinide impurities that end up in the waste streams). The design is a variant of the RBWR-AC core proposed by Hitachi, which arranges its fuel in a hexagonal tight-lattice, has a high outlet void fraction, axially segregates seed and blanket regions, and fits within the ABWR pressure vessel. The RBWR-Th shares these characteristics but replaces depleted urania with thoria as the primary fertile fuel, eliminates the internal blanket while axially elongating the seed region, and eliminates absorbers from the axial reflectors. The simulation is performed using MCNP6.1 for neutron transport, ORIGEN2.2 for transmutation, and a single-channel heat balance and void fraction correlation for a self-consistent neutronics thermal hydraulic solution. These three computational modules are iteratively executed by the MocDown driver code developed to automatically search for the equilibrium core composition and cycle length. The design variables of the parametric studies include the length of the seed and blanket zones, fuel rod diameter, lattice pitch, and concentration distribution of the recycled transfertile (TRF) isotopes in the seed. MocDown searches for the cycle length that will result in an end-of-cycle fissile inventory ratio of 1.0 along with estimated five batch core end-of-cycle keff value of 1.0. It was found that using thoria for the makeup fuel it is not possible to meet the shutdown margin constraint. Mixing in 25 to 30% depleted urania into the thoria makeup for the seed allows reduction of the magnitude of the negative void coefficient of reactivity so that adequate shutdown margin could be achieved along with adequate stability against two-phase coolant density oscillations. Promising designs arrived at so far are described. The performance of the RB WR-Th core is highly sensitive to modeling assumptions. Using the assumptions and correlations Hitachi used for the design of their RBWR-AC, the RBWR-Th average discharge burnup is 61 GWd/t versus 45 GWd/t of the depleted uranium fueled RBWR-AC.
机译:这项研究寻求用于RBWR-Th型堆芯的最佳燃料组件设计,RBWR-Th型堆芯是一种燃料自给自足的减量型BWR。除了最初的燃料负载外,它仅填充氧化ria,仅释放裂变产物,从而循环使用所有act系元素(最终流至废物流中的act系元素杂质除外)。该设计是日立公司(Hitachi)提出的RBWR-AC堆芯的一种变体,该堆芯将燃料布置在六角形的紧密晶格中,具有较高的出口空隙率,轴向隔离种子和覆盖层区域,并适合安装在ABWR压力容器内。 RBWR-Th具有这些特性,但用二氧化ria代替枯竭的尿素作为主要的可肥燃料,消除了内部覆盖层,同时轴向延长了种子区域,并消除了轴向反射器的吸收剂。使用MCNP6.1用于中子传输,使用ORIGEN2.2用于trans变,以及使用单通道热平衡和空隙率相关性来进行自洽中子电子热力液压解决方案来进行模拟。这三个计算模块由MocDown驱动程序代码迭代执行,该代码被开发为自动搜索平衡核心组成和循环长度。参数研究的设计变量包括种子和覆盖区的长度,燃料棒直径,晶格间距以及种子中循环可转移(TRF)同位素的浓度分布。 MocDown搜索周期长度,这将导致周期末裂变库存比率为1.0,以及估计的五批核心周期末keff值为1.0。已经发现,使用氧化ria作为补充燃料是不可能满足关闭裕度约束的。将25%至30%的贫化尿素混入种子的氧化ria组成中,可以降低反应性的负空洞系数的大小,从而可以实现足够的停机裕量以及对两相冷却剂密度振荡的足够稳定性。描述了到目前为止已经有希望的设计。 RB WR-Th磁芯的性能对建模假设高度敏感。使用Hitachi用于其RBWR-AC设计的假设和相关性,RBWR-Th的平均放电燃耗为61 GWd / t,而贫铀燃料RBWR-AC的平均排放燃耗为45 GWd / t。

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