Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
Reactor Physics and Thermal hydraulic Laboratory, Paul Scherrer Institut, Villigen, Switzerland.
Reactor Physics and Thermal hydraulic Laboratory, Paul Scherrer Institut, Villigen, Switzerland.
J Hazard Mater. 2018 Sep 5;357:384-392. doi: 10.1016/j.jhazmat.2018.05.041. Epub 2018 Jun 15.
In this paper, a new method is proposed to systematically calculate at the same time canister loading curves and radiation sources, based on the inventory information from an in-core fuel management system. As a demonstration, the isotopic contents of the assemblies come from a Swiss PWR, considering more than 6000 cases from 34 reactor cycles. The CSM approach consists in combining four codes: CASMO and SIMULATE to extract the assembly characteristics (based on validated models), the SNF code for source emission and MCNP for criticality calculations for specific canister loadings. The considered cases cover enrichments from 1.9 to 5.0% for the UO assemblies and 4.8% for the MOX, with assembly burnup values from 7 to 74 MWd/kgU. Because such a study is based on the individual fuel assembly history, it opens the possibility to optimize canister loadings from the point-of-view of criticality, decay heat and emission sources.
本文提出了一种新方法，该方法基于堆芯燃料管理系统的存量信息，能够同时系统地计算罐装载曲线和辐射源。作为示例，组件的同位素含量来自一座瑞士压水堆，考虑了34个反应堆循环中的6000多个案例。CSM方法包括结合四个代码：用于提取组件特性的CASMO和SIMULATE（基于经过验证的模型）、用于源发射的SNF代码以及用于特定罐装载临界计算的MCNP。所考虑的案例涵盖UO组件1.9%至5.0%的富集度以及MOX组件4.8%的富集度，组件燃耗值为7至74MWd/kgU。由于此类研究基于单个燃料组件历史，因此从临界性、衰变热和发射源的角度为优化罐装载提供了可能性。
