Monte Carlo N-Particle (MCNP) transport code accelerated by AutomateD VAriaNce reducTion Generator (ADVANTG) code was used to simulate the transport of delayed gamma particles emitted from irradiated TRIGA fuel. At the first step, this method was verified on a simple experiment where irradiated fuel was packed inside a transport cask. The calculated dose rate field in the vicinity of the transport cask was compared to the measurements. Due to an acceptable agreement, the method was later used to analyse Loss of Water Event (LOWE) for the JSI TRIGA research reactor main and spent fuel pool.

Main results of the analysis show that in the case of LOWE for the reactor pool, the reactor building has to be evacuated since dose rates exceed 2 mSv/h. The highest dose rates are expected at the reactor platform. The radiation from the core is backscattered from the ceiling and affects the dose rates inside the whole reactor hall and control room. In the worst case scenario, the operating personnel can start with corrective actions 10 days after the last reactor operation, when dose rates at the reactor platform drop below 20 mSv/h.

If LOWE occurs for the spent fuel pool, the reactor building has to be evacuated. However, the corrective actions by the operating personnel can be started immediately after the accident. This is due to the fact, that the fuel can only be transported into the spent fuel pool after a three-month cooling period inside the main reactor pool, resulting in a lower fuel activity.

由AutomateD VAriaNce减少生成器（ADVANTG）代码加速的蒙特卡罗N粒子（MCNP）传输代码用于模拟从辐照的TRIGA燃料发出的延迟γ粒子的传输。第一步，在一个简单的实验中验证了该方法，在该实验中，将辐照的燃料装在运输桶内。将在运输桶附近计算出的剂量率场与测量值进行比较。由于达成了可接受的协议，该方法后来用于分析JSI TRIGA研究堆主燃料池和乏燃料池的失水事件（LOWE）。

分析的主要结果表明，对于反应堆池的低浓水，由于剂量率超过2 mSv / h，必须将反应堆建筑物撤离。预计在反应堆平台上的最高剂量率。来自堆芯的辐射从天花板反向散射，并影响整个反应堆大厅和控制室内部的剂量率。在最坏的情况下，当反应堆平台上的剂量率降至20 mSv / h以下时，操作人员可以在最后一次反应堆运行10天后采取纠正措施。

如果乏燃料池发生渗漏，则必须将反应堆建筑物撤离。但是，事故发生后，操作人员可以立即采取纠正措施。这是由于这样的事实，即燃料只能在主反应器池内部经过三个月的冷却期后才能输送到乏燃料池中，从而导致燃料活动性降低。