论文标题
中子传输方程的蒙特卡洛方法
Monte-Carlo Methods for the Neutron Transport Equation
论文作者
论文摘要
本文继续我们对[ARXIV：1809.00827V2]，[ARXIV：1810.01779V4]和[ARXIV：1901.00220V3]的工作中的中子传输方程（NTE）构建的治疗方法，描述了通过不合美的Fissile fissile媒介的中子的磁素。我们的目的是分析现有和新颖的蒙特卡洛（MC）算法，旨在模拟与基础模型相关的铅特征值。在核监管行业中，该数量至关重要，在核监管行业中，必须在与核反应堆核心，辐射性医院设备，食品辐照设备等相对应的复杂的无骨域中解决。我们包括对此类MC算法的复杂性分析，并指出以前在文献中没有任何事业出现。新的MC算法具有准确性成本的各种优势和缺点，以及更方便的计算并行化的可能性。
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [arXiv:1809.00827v2], [arXiv:1810.01779v4] and [arXiv:1901.00220v3], which describes the flux of neutrons through inhomogeneous fissile medium. Our aim is to analyse existing and novel Monte Carlo (MC) algorithms, aimed at simulating the lead eigenvalue associated with the underlying model. This quantity is of principal importance in the nuclear regulatory industry for which the NTE must be solved on complicated inhomogenous domains corresponding to nuclear reactor cores, irradiative hospital equipment, food irradiation equipment and so on. We include a complexity analysis of such MC algorithms, noting that no such undertaking has previously appeared in the literature. The new MC algorithms offer a variety of advantages and disadvantages of accuracy vs cost, as well as the possibility of more convenient computational parallelisation.
