Types Of Waste Streams Research Articles

Improvements on radiochemical method for the determination of Am and Cm in typical waste streams from nuclear power plants

The determination of Am and Cm in typical waste streams from nuclear power plants using anion exchange chromatography has some drawbacks like the contamination by Pu and Po. This improved procedure solves these problems, and it has been applied with success to the analysis of Am and Cm in nuclear waste samples: ion exchange resins, ion exchange resins solidified with cement and evaporator concentrates.

Inventory and characterization of important radionuclides for the safety of storage and disposal. Correlation with key radionuclides in typical waste streams

Beginning in 1991 (and continuing until 1995) a research program has been undertaken involving the participation of six Western European countries, focusing on the following main objectives: (i) comparison of operational analytical methods for long-lived radionuclides and application to real waste samples; (ii) improvement of existing procedures and/or development of some alternative analytical methods; (iii) computation of correlation factors between long-lived radionuclides and easily-measured key radionuclides, through the analysis of some of the main waste streams from the participants' countries. Some preliminary and significant results that have been obtained in the framework of this project are presented and discussed.

Radiochemical methods for the determination of plutonium, americium and curium in typical waste streams

Accurate and reliable analytical methods have been developed for the measurement of Pu, Am and Cm in typical waste streams from nuclear power plants. Pu, Am and Cm were separated using anion exchange and coprecipitation techniques. The solution of Am and Cm was electrodeposited and measured by α-particle spectrometry. In the case of Pu the solution was divided into two aliquots, one for liquid scintillation counting and the other for electrodeposition followed by α-particle spectrometry. To determine the chemical recovery of α emitters of the Pu fraction and the Am and Cm fraction, the sample was spiked with 236Pu and 243Am. The chemical recovery of 241Pu was calculated using two different methods which gave reliable results. Analysis of every sample was carried out twice to examine the reproducibility of the analytical methods. The radiochemical yields of Pu and Am ranged from 80% to 100% and from 60% to 80% respectively.

Actinide recovery from radioactive liquid wastes by CMPO

The use of a special mixed solvent (tributylphosphate plus a carbamoyl-methyl phosphinoxide derivative diluted in chlorinated or aliphatic hydrocarbons) in nuclear plant liquid waste decontamination is demonstrated. Related experiments on some typical waste streams from fabrication and reprocessing plants and developed treatment processes are reported.