Radioactive Concentrate Cementation Research

According to the requirement of cement solidification of radioactive concentrated waste liquid,the laboratory formula research,lab hot test certificate,200 L barrel enlargement test and 400 L barrel enlargement test were carried out to obtain the cement solidification formula of radioactive concentrated waste liquid.Then certificate cold test and hot test in the nuclear power engineering cement solidified line,and finally get the cement solidified formula be used for nuclear facilities radioactive concentrated waste disposal.Concentrate cement solidified formula design mainly consider the calcium-boron ratio,poly-boron ratio,water-cement ratio,volume concentration of concentrate and zeolite dosage.Through the preparation of concentrated liquid,cement solidification molding,characterization of cement solidified,we recommend formulas is B-Al1-3 and B-Al2-2.Laboratory hot test using the formulas B-Al1-3 and B-Al2-2.In the experiment,the Low Activity Liquid Scintillation Analyzer was used to determine the radionuclide Sr,and the Low Activity NaI Spectrometer was used to determine the radionuclides Cs and Co.The test results show that the 42 days leaching rate and leaching fraction of the two formulations are lower than the standard limit,to meet the requirements of GB14569.1-2011 and GB / T 7023-2011.Meanwhile,the 42-day Cs-137 leaching rate of formulation B-Al1-3 was 1.54 × 10-2 cm,the 42-day Cs-137 leaching rate of formulation B-Al2-2 was 9.86 × 10-3 cm,so the formulation B-Al2-2 is better.The 42-day Sr-90 leaching rate of formulation B-Al1-3 was 1.76 × 10-2 cm.The 42-day Sr-90 leaching rate of formulation B-Al2-2 was 2.28 × 10-2 cm.Formulation B-Al1-3 was slightly excellent.For the Co-60 leaching rate,the difference between B-Al2-2 and B-Al1-3 is small.Comprehensive analysis,the formula B-Al2-2 is better.The formula 200-Al2-2 and 400-Al2-2 were respectively used for 200 L barrel enlargement test and 400 L barrel enlargement test.The tests includ temperature rise,fluidity,free liquid,mechanical properties(28 days compression,9 meters drop),anti-soaking property and anti-freezing and thawing.The results show that the performance indicators meet GB14569.1-2011 and EJ1186-2005 requirements for the solidification of concentrated liquid prepared by 200 L and 400 L barrels.Engineering scale cold test was carried out in the nuclear power plant cement solidification line,the tests includ the free liquid,compressive strength,impact resistance,anti-freeze-thaw resistance,anti-soaking,gamma irradiation and cured body uniformity and other properties.The results show that the performance indicators meet GB14569.1-2011 and EJ1186-2005 requirements.Six 400 L Engineering Scale Hot Tests cement solidification drums were prepared using the real concentrated waste fluid in the cement solidification line of nuclear power plant and tested using samples prepared in a standard small test mold(? 50 mm × 50 mm).The results show that all the performance indexes such as compressive strength,impact resistance,freeze-thaw resistance,anti-soaking property and anti-leaching property of cement solidification meet GB14569.1-2011 and GB / T 7023-2011 requirements.The research shows that the cement solidification formula of the preferred waste radioactive liquid concentrate containing boron can be applied to nuclear power projects to realize the solidification goal of "low leaching rate and high reduction ratio".