Method for Evaluating Leaching From LSA-111 Material

Year
1989
Author(s)
H. Abe - Central Research Institute of Electric Power Industry, Japan
Koichi Satoh - Central Research Institute of Electric Power Industry, Japan
S. Ozaki - Central Research Institute of Electric Power Industry
N. Watabe - Central Research Institute of Electric Power Industry
T. Iida - Central Research Institute of Electric Power Industry, Japan
H. Akamatsu - Central Research Institute of Electric Power Industry
File Attachment
1475.PDF1.71 MB
Abstract
The IAEA transport regulations ( 1985 edition) are scheduled to be introduced in Japan. New regulations are supposed to be set forth for low specific activity (LSA) material and industrial packaging (IP) as solidified concentrated waste water should correspond to the LSA material. Solidified concentrated waste water should be transported in accordance with the new transport regulations which reflect the IAEA transport regulations. As one of the regulations for LSA material, the \"leaching test\" for LSA- ill materials states that the radioactive loss due to leaching without the packaging should not exceed 0. 1A2 when left in the water for 7 days. This test method is called \"Transport regulations\" hereafter. Since the test had not been conducted in Japan be fore now, there was no available data. Consequently, it is necessary to make an assessment on whether the current solidified concentrated waste water can satisfy the leaching amount of radioactive nuclide specified in the IAEA transport regulations. If the test is performed 'in accordance with the IAEA transport regulations, however, it is necessary to measure the amount of radioactive nuclide actually .leached from the solidified concentrated waste water. Since the solidified concentrated waste water is put in a drum cam, it is necessary to prepare large-scale hot test equipment. Terefore it is difficult to perform such a measurement by using ordinary equipment.