利用 VVER 型核反应堆随时间变化的泄漏模型改进短寿命放射性同位素放射性浓度的测定方法

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Csongor Kristóf Szarvas , Gábor Radócz , Anita Gerényi , Péter Jakab Rozmanitz , Imre Szalóki
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引用次数: 0

摘要

在每个核反应堆循环的整个过程中,无泄漏运行是一项基本要求。虽然燃料故障导致的物理和化学过程通常不会影响反应堆的安全运行,但会对运行和经济造成直接影响。反应堆堆芯的无泄漏运行状态是通过一次冷却剂的伽马能谱测量进行在线监测的。通过采用相关泄漏模型进行计算,可以估算出缺陷燃料元件的燃耗和泄漏参数。本文提出了一种评估随时间变化的样品延迟时间的新方法,该方法用于根据随时间变化的泄漏模型计算出的核子数量,计算初级冷却剂中裂变产物随时间变化的放射性浓度。我们对三种具有不同基本假设的模型的性能进行了单独和集体研究。新的样品延迟时间模型可以更准确地估计随时间变化的放射性浓度,特别是初级冷却剂中寿命较短的 137Xe、138Xe、138Cs 和 134I 同位素的浓度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Improvement of the determination of radioactivity concentrations of short-lived radioisotopes with the time-dependent leakage model of VVER-type nuclear reactor
The leak-free operation is a fundamental necessity for the entire duration of each nuclear reactor cycle. While the physical and chemical processes resulting from fuel failures typically do not avert the safe operation of the reactor, they can have direct operational and economic consequences. The state of leak-free operation in the reactor core is monitored on-line by gamma spectra measurements of the primary coolant. Estimating the burnup and leakage parameters of defective fuel elements is achieved through calculations employing relevant leakage models. This paper presents a novel approach to assessing the time-dependent sample delay time, which is used to calculate the time-dependent radioactivity concentrations of the fission products in the primary coolant from their number of nuclei calculated by the time-dependent leakage model. The performance of three models with different basic assumptions was individually and collectively investigated. The new sample delay time model allows a more accurate estimation of the time-dependent radioactivity concentration, especially of the short-lived 137Xe, 138Xe, 138Cs, and 134I isotopes in the primary coolant.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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