基于确定论的 ADANES 堆芯稳态中子学分析及瞬态事故模拟研究

[Background] At present, in the key stage of the construction of China Initiative Accelerator Driven System, various research institutes have also put forward corresponding core schemes for different purposes, including the accelerators drive advanced nuclear energy system (ADANES) proposed by Institute of Modern Physics, Chinese Academy of Sciences. Detailed calculation and analysis of its scheme can provide strong technical support for the sustainable development of nuclear energy and the national energy security strategy. [Purpose] This study aims to analyze the steady-state neutronics characteristics of ADANES reactor with emphasis on the preliminary typical transient analysis under the typical accident conditions of fast reactor. [Methods] The NECP-SARAX (Nuclear Engineering Computational Physics Laboratory, System for Advanced Reactor Analysis at Xi'an Jiaotong University) code system, which was based on deterministic neutron transport theory, was applied to perform the detailed analysis. The main design parameters, including core length, neutron spectrum and reactivity feedback coefficients, were calculated under various fuel types, coolant types, and reactor geometry parameters. In addition, the primary transient characteristics were simulated, including unprotected transient over power and unprotected loss of flow transient. The changes of reactor power and the maximum fuel/coolant temperature were obtained and analyzed. [Results & Conclusions] The steady-state calculation results show that ADANES could achieve 10 effective full power year for each selected case. The reactivity feedback coefficients reach −5.4×10⁻⁵ K⁻¹ in total so that the core has inherent safety under typical accident condition conditions during the simulated transient.