Review on Selection and Experiment Method of Commonly Studied Simulated Radionuclides in Researches of Nuclear Waste Solidification
Creators
- 1. Shandong Engineering Laboratory for Solid Waste Green Materials, National Engineering Laboratory for Reducing Emissions from Coal Combustion, Engineering Research Center of Environmental Thermal Technology of Ministry of Education, Shandong Key Laboratory of Energy Carbon Reduction and Resource Utilization, School of Energy and Power Engineering, Shandong University, Jinan 250014, China
- 2. School of Civil Engineering, Shandong Jianzhu University, Jinan 250101, China
Description
Although many types of simulated radionuclides have been widely used as a substitute for actual nuclear waste in the studies of nuclear waste solidification, the understanding of the applicability and validity of simulated radionuclides is still insufficient. In particular, the selection and use of simulated radionuclides, which can play a decisive role in the accuracy of the experimental results, still lack unified or integrated references. This paper provides a critical review on the selection, experimental methods, and applicability of the most commonly studied simulated radionuclides, followed by a careful discussion and recommendation of simulated radionuclides suitable for different solidified bodies. The main factors (e.g., temperature, pH, and atmosphere) affecting the choice of simulated radionuclides were analyzed in detail. This work helps to integrate the selection and use of simulated radionuclides, and it will be beneficial for improving the effectiveness of nuclide solidification research.
Files
10.1155_2020_3287320.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2020/3287320;
- Crossref Funder ID
- 10.13039/100009108;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2020
- Journal Page Range
- 1-13
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ACCURACY; CHEMICAL WASTES; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; NONRADIOACTIVE WASTE DISPOSAL; PH VALUE; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; RADIOISOTOPES; RECOMMENDATIONS; REVIEWS; SIMULATION; SOLID WASTES; SOLIDIFICATION; STRONTIUM 90
- Descriptors DEC
- ALKALINE EARTH ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DOCUMENT TYPES; EVEN-EVEN NUCLEI; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; NONRADIOACTIVE WASTE MANAGEMENT; NONRADIOACTIVE WASTES; NUCLEI; PHASE TRANSFORMATIONS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; RADIOISOTOPES; STRONTIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- © Author(s)
- Contract/Grant/Project number
- 2017YFC0703100
- Notes
- Record automatically processed
- Funding organization
- Shandong University, National Key Research & Development Program of China