Abstract

The Purdue Advanced Reactor Core Simulator (PARCS) three-dimensional neutron kinetics code and the TRACE nuclear systems analysis code were interfaced. This provides a best-estimate coupled code system for performing transient plant calculations with reactivity feedback from a detailed core model, significantly contributing to nuclear power plant safety analyses. This study performed steady-state and transient simulations of Peach Bottom 2 Turbine Trip Test 2 (PB2 TT2) using the CASMO5/TRACE/PARCS coupled code. Consequently, CASMO5/TRACE/PARCS simulates the rapid positive reactivity addition caused by the sudden closure of the turbine stop valve. Specifically, the discrepancy in the maximum total power during the transient condition was within 3% compared with the PB2 TT2 experimental data. Furthermore, the sensitivity of the thermal-hydraulic channel (CHAN) component modeling in the coupled CASMO5/TRACE/PARCS code revealed that the number of CHAN components influenced the assembly radial power peaking factor in the PB2 TT2 transient calculation.

摘要

Purdue Advanced Reactor Core Simulator (PARCS) 三维中子动力学代码和 TRACE 核系统分析代码进行了交互。这为使用来自详细堆芯模型的反应性反馈执行瞬态电厂计算提供了最佳估计耦合代码系统，显着有助于核电厂安全分析。本研究使用 CASMO5/TRACE/PARCS 耦合代码对 Peach Bottom 2 Turbine Trip Test 2 (PB2 TT2) 进行了稳态和瞬态模拟。因此，CASMO5/TRACE/PARCS 模拟了由涡轮截止阀突然关闭引起的快速正反应性增加。具体来说，与PB2 TT2实验数据相比，瞬态条件下最大总功率的差异在3%以内。此外，