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目前世界上已探明的具有开采价值的钍资源几乎与铀相等。Th/U燃料循环的主要优点在于~(233)U,相对于U/Pu燃料循环中的~(239)Pu,有更高的中子产额。事实上只有用钍作为再生燃料,热堆才可能实现增殖。作为钍基核燃料利用的基础研究的一部分,我们制订了一个从辐照二氧化钍中分离~(233)U(+~(232)U)的阴离子交换程序。每个辐照样品压成小药丸状、重80 mg的核纯ThO_2。装入辐照管中,在国内热功率为12.5万千瓦的高通量工程试验堆的铍反射层中辐照。热中子通量为2×10~(14)中子/cm~2·s,快热中子比为1:1。热中子积分通量约为1×10~(20)—1×10~(21)中子/cm~2。照好后的样品移至水池冷却,数月后处理。二氧化钍用含NH_4F及AlCl_3的浓HCl加热迥流溶解,然后将料液调至8 mol/1 HCl
The world has proven that the exploitation of thorium resources are almost equal to uranium. The main advantage of the Th / U fuel cycle is the ~ (233) U, which has a higher neutron yield relative to ~ (239) Pu in the U / Pu fuel cycle. In fact, only using thorium as a renewable fuel, thermal reactor is possible to achieve proliferation. As part of the basic research on the utilization of thorium-based nuclear fuel, we developed an anion exchange procedure for the separation of ~ (233) U (+ ~ (232) U) from irradiated thorium dioxide. Each irradiated sample was pelleted and weighted 80 mg of nuclear-pure ThO 2. Loaded into the irradiated tube and irradiated in the beryllium reflector layer of a domestic high-throughput engineering test reactor with a heating power of 125,000 kW. Thermal neutron flux is 2 × 10 ~ (14) neutrons / cm ~ 2 · s, fast neutron ratio is 1: 1. The thermal neutron fluence is about 1 × 10 ~ (20) -1 × 10 ~ (21) neutron / cm ~ 2. According to the sample after the move to the pool cooling, a few months after treatment. Thorium dioxide with NH_4F and concentrated HCl containing AlCl_3 heated reflux dissolve, and then the liquid was adjusted to 8 mol / 1 HCl