Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
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Lida Amanelahi Dorcheh
Abstract
An ingenious design, Traveling Wave Reactor (TWR) has been suggested for full exploitation of uranium resources in next generation of nuclear reactors. This design involves the slow propagation of a nuclear fission wave through a long initially subcritical core and the transmutation of nuclear fuel. It has been widely proven that the initiation and propagation of fission waves are feasible prompting the Terra Power Company to conduct preliminary commercialization studies on this project. In equilibrium state, the shapes of the neutron flux, nuclide densities and power density distribution remain constant but the burning region moves in axial (or radial) directions. In this case the in situ fissile material production and consumption drives the operation. Only natural or depleted uranium is required for fresh fuel region. However, in equilibrium state, the burning region contains a spectrum of fission products as well as higher actinides whose are not easily available for initial TWR core construction. One solution is based on the use of enriched uranium in the first cycle to ignite the fission wave and then employment of the composition in subsequent cycles up to the equilibrium state. The main objective of this work is the feasibility study of forming a fission wave as well as the neutronic analysis of a Gas-Cooled Traveling Wave Reactor in various cycles up to the equilibrium one. The MCNP Monte Carlo code was utilized for the analysis of criticality and burn-up calculation. In each cycle, the axial fresh fuel loading and spent fuel discharge, were subjected to analysis. Results showed that the equilibrium state can be obtained by using special arrays of absorbers, from the third cycle where the shape of neutron flux and the power density distribution in axial direction remain unchanged.
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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Articles in the same Issue
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
Articles in the same Issue
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
