This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage cask intended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks are designed to be stored in a new “closed” type interim storage facility, with the capacity to store up to 202 CONSTOR® RBMK-1500/M2 casks. In 2016 y, the “hot trials” of this new facility were conducted and 10 CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicated storage places in this facility. During “hot trials”, the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must be below design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics, the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with this particular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computer code with very detailed geometrical representation of the cask and the fuel. The obtained modeling results were compared with the measurement results and it was revealed, that modeling results are generally in good agreement with the measurements.

本文介绍了新型CONSTOR®RBMK-1500 / M2储存桶的中子剂量率分析，该储存桶用于立陶宛伊格纳利纳核电站的乏核燃料储存。这些桶被设计为存储在新的“封闭式”临时存储设施中，最多可存储202个CONSTOR®RBMK-1500 / M2桶。在2016年，对该新设施进行了“热试验”，并将装满乏核燃料的10个CONSTOR®RBMK-1500 / M2桶运输到该设施的专用存储场所。在“热试验”期间，对CONSTOR®RBMK-1500 / M2桶进行剂量率测量，因为剂量率是控制的关键参数之一，并且必须低于设计（和安全）标准。因此，有了乏核燃料特性的实际数据，还对装有这种特殊燃料的CONSTOR®RBMK-1500 / M2桶进行了中子剂量率建模。使用MCNP 5计算机代码进行中子剂量率建模，并非常详细地表示容器和燃料的几何形状。将获得的建模结果与测量结果进行比较，结果表明，建模结果通常与测量结果吻合良好。