Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
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Fitria Miftasani
,
Nuri Trianti
Abstract
TRISO fuel particle using ZrC has better strength and resistance to high temperatures than SiC. Previous studies show that the ZrC layer, as a substitution of SiC within the TRISO layer of coated fuel particles, has an insignificant difference in the performance of the neutronic aspect. Further neutronic studies are required to obtain the best combination of thorium-based fuel with ZrC coating for HTGR. This study analyzed the neutronic performance of three types of thorium-based fuels, oxide, carbide, and nitride, for HTGR. The reactor design refers to the High-Temperature Test Reactor with some axial and radial fuel configuration adjustments. This reactor is designed to operate at 200 MWt and has been modified to use a ZrC layer as a substitute for the SiC layer on the coated fuel particles. The neutronic study is carried out using SRAC2006 code with JENDL 4.0 nuclear data library. Neutronic parameters analyzed include multiplication factor, power peaking factor, and neutron spectrum. Neutronic analysis results show that thorium nitride fuel’s multiplication factor (keff) is better than other compared fuel types with k-eff 1.050, higher than thorium carbide, 1.004. At the same time, thorium oxide has been sub-critical. The power-peaking value of all materials is close to the ideal peaking value that is one. Other neutronic aspects, such as the neutron spectrum for three compared fuel types, have a similar trend.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: The research is funded by the Indonesian National Research and Innovation Agency.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions
- Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC
- Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
- Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
- Optimization of divertor design for Pakistan spherical tokamak
- Role of impurity and thermal noise on the radiation sources in ITER using DT fuel
- An investigation of multistream plate-fin heat exchanger modelling and design: a review
- Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
- Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels
- Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
- Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface
- Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
- Heat transfer enhancement of heat exchanger using rectangular channel with cavities
- Calendar of events
