Calculation of core neutronic parameters in electron accelerator driven subcritical TRIGA reactor
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Nafise Yazdani
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Mohammad Mehdi Firoozabadi
Abstract
Investigating the dependence of reactor core neutronic parameters on the accelerator related parameters such as source multiplication coefficient (K s ), beam profile and electron beam energy (E e ), have a significant impact on the design of future ADS reactors and the cost of their construction. Using the MCNPX code, core neutronic parameters were calculated for three eigenvalues levels (k s ) such as axial and radial distributions of neutron flux, effective multiplication coefficient (K eff), photoneutron yield (Y n/e ), net neutron multiplication (M), energy gain (G), energy constant gain (G 0), power peaking factor (P max/P ave), and importance of neutron source (φ*) for the tungsten target in the core of TRIGA reactor which was driven by an electron accelerator. According to the results, when K s increases safety margin and the required accelerator current (I e ) decrease, but the parameters G and φ* increase. Also, using the parabolic spatial distribution for the electron source instead of the uniform spatial distribution, the parameters Y n/e , G and M increase. In addition, by increasing E e from 100 to 500 MeV, Y n/e and G are improved, and I e and accelerating power (p acc) decrease. Therefore, these results suggest that the dependence of reactor core neutronic parameters on accelerator related parameters is necessary to optimize the design cost of an ADS reactor.
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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: None declared.
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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
- A study of RCS depressurization strategy of CPR1000 SAMG
- Drones application scenarios in a nuclear or radiological emergency
- Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site
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- Calculation of core neutronic parameters in electron accelerator driven subcritical TRIGA reactor
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- Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control
- Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly
- Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids
- Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor
- Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector
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