Nowadays, nuclear reactor safety simulations of real nuclear plants are still performed using approximated system codes which rely on one-dimensional lumped-parameters or subchannel methods.

Many of these one-dimensional codes are not able to fully simulate intrinsic multi-dimensional effects that occur within a nuclear reactor.

On the other hand, Computational Fluid Dynamics (CFD) codes, thanks to the recent advances in computer technology, are now capable of tackling complex multi-dimensional fluid-dynamics problems for a large variety of nuclear and non-nuclear applications.

The neutronics code Point Kinetics Multi-Purpose Online Neutronic code (PoKiMON), has been developed in order to provide realistic 1-D neutronics feedbacks to the CFD one.

The goal of this work is then to extend the range of applications of coupled neutronics/CFD simulations towards boron ingress shutdown scenarios in light water small modular reactors.

The coupled system was also verified considering two fuel assembly-level calculations against the code SUBCHANFLOW, a heat decay calculation against classic decay heat equation and was validated considering the IFA-507 experiment performed at the Halden reactor facility.

时至今日，仍使用近似的系统代码（基于一维集总参数或子通道方法）对实际核电厂进行核反应堆安全仿真。

这些一维代码中的许多代码无法完全模拟核反应堆内部发生的固有多维效应。

另一方面，由于计算机技术的最新发展，计算流体动力学（CFD）代码现在能够解决各种核和非核应用中复杂的多维流体动力学问题。

开发中子学代码点动力学多用途在线中子学代码（PoKiMON）是为了向CFD提供逼真的一维中子学反馈。

然后，这项工作的目标是将中子学/ CFD耦合模拟的应用范围扩展到轻水小型模块化反应堆中的硼进入停工场景。

还考虑了代码SUBCHANFLOW的两个燃料组件级计算，经典衰减热方程式的热衰减计算，验证了耦合系统，并考虑了在Halden反应堆设施进行的IFA-507实验进行了验证。