Numerical investigation of thermal gasification in enclosed screw-conveyor reactor for removal of 14C from irradiated graphite waste
Creators
- 1. Department of Environmental Engineering, Kongju National University, Gongju (Korea, Republic of)
- 2. Department of Chemical Engineering, Kyonggi University, Suwon (Korea, Republic of)
Description
Investigated numerically are the effects of the rotational speed of the screw conveyor and the reactor temperature on the changes in the diameter of graphite particles passing through a laboratory-scale enclosed screw-conveyor reactor. Also investigated experimentally are a thermal gasification of graphite particles to carbon-oxygen compounds to determine a kinetic reaction model and kinetic parameters. The non-Newtonian fluid-like flow of graphite particles in the enclosed screw-conveyor reactor is numerically simulated by solving the momentum equation using a recently developed viscoplastic model with a rotating reference frame. The numerical approach coupled with the determined kinetic model of the gasification reaction of graphite powder successfully predicted the motion of the graphite particles and changes in their diameter flowing through the reactor. For a reactor temperature of 1073 K, the size of the feed graphite particles was predicted to decrease by 2% to 30% depending on the rotational speed of the screw conveyor. The predictions of the numerical simulations can be used to optimize the operating conditions of the enclosed screw-conveyor reactor for decontaminating irradiated graphite waste by removing the radiocarbons, which are located mainly on the graphite surface. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/00223131.2020.1728413Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 57
- Journal Issue
- 7
- Journal Page Range
- p. 839-851
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 52050495
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CARBON 14; COMPUTERIZED SIMULATION; CONVEYORS; CORIOLIS FORCE; GASIFICATION; GRAPHITE; IRRADIATION; MASS TRANSFER; NUCLEAR FACILITIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVITY; REACTOR MATERIALS; REGRESSION ANALYSIS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON; CARBON ISOTOPES; ELEMENTS; EQUIPMENT; EVEN-EVEN NUCLEI; HAULAGE EQUIPMENT; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; MATERIALS; MATERIALS HANDLING EQUIPMENT; MATHEMATICS; MINERALS; NONMETALS; NUCLEI; PROCESSING; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; SIMULATION; STATISTICS; THERMOCHEMICAL PROCESSES; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 27 refs., 10 figs., 1 tab.