摇摆运动下多环路主冷却剂系统自然循环流量的稳定性分析

海洋核动力平台因其突出的安全性已成为当今核能领域热点研究问题之一，但在海洋等非惯性条件下会使一回路系统的热工特性发生变化。针对此问题，本文对几种典型的一回路系统在摇摆条件下的自然循环流量波动特性进行计算分析。分别建立典型的双环路、三环路、四环路的一回路系统模型布置方案，并同时考虑摇摆中心的位置，根据流体动量守恒方程，得到不同状态下一回路系统内的流量变化规律。对于单堆双环路系统，摇摆中心在船上/中/下部位置时，环路流量波动幅度分别为13.2%/11.2%/9.5%，堆芯流量波动幅度分别为0.9%/0.8%/0.6%；对于单堆三环路系统，摇摆中心在船下部时，环路流量和堆芯流量波动幅度分别为9.2%和0.8%；对于单堆四环路系统，摇摆中心在船下部时，布置方案1和方案2的环路流量波动幅度分别为9.5%和9.2%，堆芯流量波动幅度分别为0.9%和0.7%。计算结果表明：采用单堆双环路的设计布置方案是最有利于系统稳定性的。

Stability Analysis of Natural Circulation Flow of Multi-loop Primary System in Rolling Motion Condition

Marine nuclear power platform is one of the main topic research in the field of nuclear energy due to its outstanding safety, but the thermal-hydraulic characteristics are influenced when primary loop and non-inertial conditions operate in natural circulation. Aiming to this problem, several typical primary loop systems were designed to calculate and analyze flow fluctuation characteristics in rolling motion on natural circulation. The scheme designs of double-loop, three-loop and four-loop system models were established respectively. And the position of the rolling center was considered at the same time. According to the momentum conservation equation, the change law of flow was obtained in different states. Flow fluctuation ranges of the loop are 13.2%/11.2%/9.5%, and flow fluctuation ranges of the reactor core are 0.9%/0.8%/0.6% in the double-loop respectively when rolling center is in upper/middle/lower part. Flow fluctuation ranges of the loop and the reactor core are 9.2% and 0.8% respectively in the three-loop when rolling center is in lower part of the ship. Flow fluctuation ranges of the loop and the core are 9.5% and 0.9% respectively for scheme design 1, and 9.2% and 0.7% respectively for scheme design 2 in four-loop. The design scheme with double-loop is most beneficial to the stability of the system.