Internal Dose Assessment of Worker by Radioactive Aerosol Generated During Mechanical Cutting of Radioactive Concrete
- 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
Description
Removing radioactive concrete is crucial in the decommissioning of nuclear power plants. However, this process generates radioactive aerosols, exposing workers to radiation. Although large amounts of radioactive concrete are generated during decommissioning, studies on the internal exposure of workers to radioactive aerosols generated from the cutting of radioactive concrete are very limited. In this study, therefore, we calculate the internal radiation doses of workers exposed to radioactive aerosols during activities such as drilling and cutting of radioactive concrete, using previous research data. The electrical-mobility-equivalent diameter measured in a previous study was converted to aerodynamic diameter using the Newton–Raphson method. Furthermore, the specific activity of each nuclide in radioactive concrete 10 years after nuclear power plants are shut down was calculated using the ORIGEN code. Eventually, we calculated the committed effective dose for each nuclide using the IMBA software. The maximum effective dose of 152Eu constituted 83.09% of the total dose; moreover, the five highest-ranked elements (152Eu, 154Eu, 60Co, 239Pu, 55Fe) constituted 99.63%. Therefore, we postulate that these major elements could be measured first for rapid radiation exposure management of workers involved in decommissioning of nuclear power plants, even if all radioactive elements in concrete are not considered
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Fuel Cycle and Waste Technology
- Journal Volume
- 18
- Journal Issue
- 2
- Series
- 30 refs, 5 figs, 4 tabs
- Journal Page Range
- p. 157-167
- ISSN
- 1738-1894
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 53091749
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COBALT 60; CONCRETES; CUTTING; DECOMMISSIONING; DRILLING; EFFECTIVE RADIATION DOSES; EUROPIUM 152; EUROPIUM 154; IRON 55; NEWTON METHOD; NUCLEAR POWER PLANTS; O CODES; PLUTONIUM 239; RADIOACTIVE AEROSOLS
- Descriptors DEC
- ACTINIDE NUCLEI; AEROSOLS; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BETA-PLUS DECAY RADIOISOTOPES; BUILDING MATERIALS; CALCULATION METHODS; COBALT ISOTOPES; COLLOIDS; COMPUTER CODES; DISPERSIONS; DOSES; ELECTRON CAPTURE RADIOISOTOPES; EUROPIUM ISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRON ISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; ITERATIVE METHODS; MACHINING; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; ODD-ODD NUCLEI; PLUTONIUM ISOTOPES; POWER PLANTS; RADIATION DOSES; RADIOISOTOPES; RARE EARTH NUCLEI; SOLS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL POWER PLANTS; YEARS LIVING RADIOISOTOPES