Abstract
In this study, the dynamic characteristics of accelerator-driven subcritical reactor (ADSR) under beam transients with high heterogeneity of neutron flux in time-space are investigated. Multi-mode core few-group constants are generated by three kinds of neutron fluxes: steady state of ADSR, λ-eigenvalue fundamental wave, and α-eigenvalue fundamental wave. The proposed few-group constants overcome the limitation of single few-group constant generated by two-step method that cannot consider the variation in neutron flux density and neutron energy spectrum with time and space. Compared to the existing few-group constants generated by two-step method under different operating conditions, the self-adapting multi-mode core few-group constants exhibit higher accuracy in the case of following two modes: steady-state mode of ADSR in the starting process and λ-eigenvalue mode in the beam trip condition. Overall, this research provides useful insights on neutron kinetics and can boost the development of ADSRs.
Highlights
With the increasing utilization of nuclear power, the disposal of accumulated nuclear waste has become a critical issue globally
To overcome the limitations of the existing models, in this study, the multi-mode core few-group constants with beam transients and time-space heterogeneity were generated by three kinds of neutron fluxes: steady state of accelerator-driven subcritical reactor (ADSR), fundamental wave with eigenvalue λ, and fundamental wave with eigenvalue α
The multi-mode core few-group constants of ADSR with beam transients and time-space heterogeneity of neutron flux were generated by three kinds of neutron fluxes: steady state of ADSR, λ-eigenvalue fundamental wave, and α-eigenvalue fundamental wave
Summary
With the increasing utilization of nuclear power, the disposal of accumulated nuclear waste has become a critical issue globally. To overcome the limitations of the existing models, in this study, the multi-mode core few-group constants with beam transients and time-space heterogeneity were generated by three kinds of neutron fluxes: steady state of ADSR, fundamental wave with eigenvalue λ, and fundamental wave with eigenvalue α. The three modes: λ mode, prompt α mode, and fixed source mode, of few-group constants obtained above are linked and correspond to the quasi-static core diffusion code for neutron kinetics of under beam transients This helps in establishing a method for the analysis of neutron kinetics of ADSR with self-adapting multi-mode core few-group constants for arbitrary beam transient conditions. We discuss the results of neutron kinetics obtained using multi-mode core few-group constants and IQS methods under various sub-criticalities, locations, and beam transient conditions. By comparing the relative errors of neutron kinetics results at various positions, it can be inferred that the relative error of multi-mode s_λ is the smallest under the beam transient conditions
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