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RECOVERY AND TRANSMUTATION OF IODINE-129 IN AN ACCELERATOR-DRIVEN TRANSMUTATION SYSTEM

机译:加速器驱动嬗变系统中碘-129的恢复和嬗变

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Extensive repository system performance analyses have been carried out in the course of evaluating the feasibility of the proposed Yucca Mountain repository. These studies have shown that the primary contributors to public radiation dose as a consequence of release of radionuclides from the repository are isotopes of iodine, technetium and neptunium (129I, 99Tc, and 237Np). The United States Department of Energy is presently conducting a science-based R&D program, the Advanced Accelerator Applications Program, that addresses the technical issues associated with the transmutation of transuranic elements and long-lived fission products contained in the U.S. inventory of commercial Light Water Reactor (LWR) spent fuel. One of the main issues is the recovery and transmutation of iodine. The two fuels from which the iodine must be extracted are quite different, one (the LWR fuel) being an oxide fuel with zirconium alloy cladding, and the other most likely being a dispersion of metallic transuranics in a metallic zirconium matrix with stainless steel cladding. An aqueous solvent extraction process similar to the PUREX process will probably be used for LWR spent fuel processing, while a pyrochemical process seems to be most appropriate for the transmuter fuel. An overall system recovery target for iodine of 95% has been set as an initial goal of the program. Prior experience with iodine recovery in the PUREX process, both domestic and international, suggests that a satisfactory means can be developed for recovering the iodine contained in the LWR spent fuel. Iodine recovery in the less well-defined pyrochemical process for transmuter fuel appears to be feasible, but experimental verification and validation of the recovery steps is required. It is possible that the form of the recovered iodine from the two fuel types will be different, so it then remains to develop processes for incorporating the iodine in a standard target form, expected to be sodium iodide. Target design will also take into account means for accommodating the products of iodine and sodium transmutation.
机译:在评估所提出的尤卡卡山区储存库的可行性过程中,已经进行了广泛的存储库系统性能分析。这些研究表明,由于来自储存库的放射性核素释放的后果,公共辐射剂量的主要贡献者是碘,技术和Neptunium(129i,99Tc和237NP)的同位素。美国能源部目前正在进行一项基于科学的研发计划,先进的加速器应用程序,解决了与经过阵挛元素的嬗变相关的技术问题,以及商业光水反应堆美国库存中包含的长寿裂变产品(LWR)燃料。主要问题之一是碘的恢复和嬗变。必须提取碘的两种燃料是完全不同的,一种(LWR燃料)是具有锆合金包层的氧化物燃料,另一个最可能是金属锆基质中金属过生素的分散与不锈钢包层。类似于purex工艺的水性溶剂萃取过程可能用于LWR花费燃料加工,而猪油化学过程似乎最适合透射燃料。 95%碘的整体系统恢复目标被设定为程序的初始目标。在国内和国际上,PureX过程中碘恢复的经验表明,可以开发出令人满意的手段,以便回收LWR废燃料中包含的碘。在透射仪燃料的较少明确定义的猪肉过程中碘恢复似乎是可行的,但需要实验验证和验证恢复步骤。从两种燃料类型中回收的碘的形式是不同的,因此仍然是为了制定以标准靶形式掺入碘的方法,预期是碘化钠。目标设计还将考虑容纳碘和钠嬗变产品的方法。

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