Abstract
The article considers computation methods of the kinetics of changes of fuel nuclide composition vs. fuel burnup. Calculations were carried out at different intervals of operating time at a constant level of power of the IRT-T research reactor for different types of fuel assemblies. The analysis of the reaction rate of absorption for the isotopes included in the fuel composition is given. It is shown that the use of piecewise linear interpolation is the most preflerred in order to calculate the long fuel campaigns as there is a high convergence of calculation data.
| Original language | English |
|---|---|
| Pages (from-to) | 449-452 |
| Number of pages | 4 |
| Journal | Journal of Industrial Pollution Control |
| Volume | 32 |
| Issue number | 2 |
| Publication status | Published - 2016 |
Keywords
- Burnup
- Fuel nuclide composition
- IRT-T reactor
- Isotopes
- Neutron
ASJC Scopus subject areas
- Water Science and Technology
- Ocean Engineering
- Pollution
- Fluid Flow and Transfer Processes
- Atmospheric Science
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Naymushin, A., Anikin, M., Lebedev, I., Busygin, A., Dmitriev, S., & Zolotykh, D. (2016). Features of fuel burnup calculations for IRT-T reactor using MCU-PTR code. Journal of Industrial Pollution Control, 32(2), 449-452.