VVER反应堆冷却剂流量变化对堆芯监测系统自供电中子探测器响应的影响：PRIM-AES软件包中的瞬态模式模拟

IF 0.3 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2025-08-21 DOI:10.1007/s10512-025-01247-3

D. A. Gornostaev, A. Yu. Kurchenkov, A. M. Musikhin, Yu. M. Semchenkov

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引用次数: 0

摘要

在本文中，我们使用计算模拟来研究自供电中子探测器（spnd）对被测燃料组件（FA）冷却剂流速变化的响应。考虑了在几个测量FAs中降低冷却剂流量的模型问题。对它们的响应进行了评估，包括引入由通过FA的流量减少引起的扰动前后SPND电流的差异。在某些情况下，岩心内监测系统spnd的读数可用于诊断通过FA的流量下降。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Effects of changes in the coolant flow rate of the VVER reactor to the response from the self-powered neutron detectors of the in-core monitoring system: simulation of transient modes in the PRIM-AES software package

In the present paper, we use computational simulation to investigate the response of self-powered neutron detectors (SPNDs) to changes in the coolant flow rate of the measured fuel assembly (FA). A model problem of reducing the coolant flow rate in several measured FAs is considered. Their response is assessed, including the difference in the SPND current before and after introducing a disturbance caused by a decrease in the flow rate through the FA. In some cases, readings of in-core monitoring system SPNDs can be used to diagnose a decrease in the flow rate through the FA.

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来源期刊

Atomic Energy 工程技术-核科学技术

CiteScore

1.00

自引率

20.00%

发文量

100

审稿时长

4-8 weeks

期刊介绍： Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.