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An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering: Part Ⅰ: Flux and Eigenvalue Solutions

机译:下散射的中子博尔特扎曼运输分析基准:第Ⅰ部分:通量和特征值溶液

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Computing in the energy dimension is one of the greatest challenges confronting present-day deterministic neutron transport solvers. Accurately resolving the neutron flux as neutrons downscatter across resonances in the nuclear cross sections currently requires considerable computing power and suffers from approximation errors. Flux uncertainty resulting from the uncertainty of the resonance structure is the single-largest cause of reactivity uncertainty. Any additional reference solution for the critical neutron downscattering problem with resonance phenomena would be a boon to verification and validation of neutronics codes. This paper establishes a benchmark to verify the accuracy of neutron transport criticality solvers along the energy dimension. For the first time, the analytic solution of the flux amplitude is derived in the particular case of an infinite homogeneous medium with isotropic scattering in the center of mass and an arbitrary number of no-threshold, neutral particle reaction resonances (e.g., radiative capture, fission, and resonance scattering). Original analytic expressions are established to quantify the discrepancy between the ψk(E) and ψα(£) flux amplitudes, respective solutions of the multiplication factor k or the exponential time-evolution frequency α eigenproblems. The physical study of these relations led to analysis of their first-order relative difference near the criticality condition α= 0. Finally, numerical solutions are provided to a benchmark problem constituted of the first resonance of ~(239)Pu, the 6.67-eV resonance of ~(238)U, and a scattering isotope with a flat cross section, allowing for the computational verification of the energy resolution of current neutron transport criticality codes. Through these novel results, this analytic benchmark can serve as a reference to verify the energy resolution and sensitivity analysis of neutron transport criticality calculations.
机译:在能量维度中计算是当今确定的中子传输溶剂的最大挑战之一。作为中子磁通量在核横截面中的共振越野中的中子磁通量目前需要相当大的计算能力并且遭受近似误差。由共振结构的不确定性产生的助焊剂不确定性是反应性不确定性的最大原因。对于谐振现象的临界中子下散射问题的任何额外参考解决方案都是扫描和验证中子码的福音。本文建立了沿着能量尺寸验证中子传输临界求解器的准确性的基准。首次,在具有各向同性散射的无限均质介质的特定情况下,磁通幅度的分析溶液在质心和任意数量的无阈值,中性颗粒反应共振(例如,辐射捕获,裂变和共振散射)。建立原始分析表达式以量化ψk(e)和ψα(£)通量幅度的差异,乘法因子k的各个解或指数时间evolution频率α特征问题。这些关系的物理研究导致其在临界条件α= 0附近的一阶相对差异分析。最后,提供了由〜(239)PU,6.67-EV的第一个共振的基准问题的数值解决方案〜(238)U的共振,以及具有扁平横截面的散射同位素,允许计算电流中子传输临界码的能量分辨率的计算验证。通过这些新颖的结果,该分析基准可以作为参考验证中子传输临界计算的能量分辨率和灵敏度分析。

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