Systematic Analysis Method for Radioactive Wastes Generated from Nuclear Research Facilities

Abstract

Analytical methods have been developed for the simple and rapid determination of radioactive nuclides, which are selected as important nuclides for the safety assessment of the disposal of wastes generated from research facilities. We advanced the development of a high-e‹ciency nondestructive measurement technique for g ray-emitting nuclides, simple and rapid methods for the pretreatment of hard-to-dissolve samples and subsequent radiochemical separation, and rapid determination methods for long-lived nuclides. In order to establish a system to analyze the important nuclides in various kinds of sample, actual radioactive wastes such as concentrated liquid waste, activated concrete, and metal pipes were analyzed by the present method. The results showed that the present method was well suited for a rapid and simple determination of low-level radioactive wastes generated from research facilities.

Design of Microchannel Suitable for Packing with Anion Exchange Resins: Uranium Separation from Seawater Containing a Large Amount of Cesium

“…Therefore, separation of U from various matrix elements is necessary to avoid the matrix effect and the radioactive contamination. Ion exchange and extraction chromatography were reported [3][4][5][6][7][8] as conventional bulk-scale methods of U separation from interfered Cs-137 and matrix metal ions. However, these methods are disadvantageous as they are manually operated, have long separation periods, and generate high volumes of waste solutions, increasing the risk of radiation exposure for analysis workers while generating a large amount of secondary radioactive wastes (e.g., consumable supplies and solutions).…”