基于离散截面法的快堆气溶胶动力学代码的改进与验证

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI:10.1016/j.pnucene.2024.105457

Shikha Sivakumar, A Jasmin Sudha, V. Subramanian, B. Venkatraman

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引用次数: 0

摘要

研究严重事故期间产生的气溶胶的动态对于钠冷快堆的安全分析至关重要。严重事故发生后，钠泄漏到安全壳中可能导致钠气溶胶和裂变产物气溶胶的产生。安全壳内的放射源项取决于裂变产物气溶胶的沉降行为，这些气溶胶会与钠火气溶胶共同聚集。因此，深入了解安全壳内气溶胶的动态和沉降对 SFR 的安全评估至关重要。目前的工作使用基于离散-截面（DS）方法的开源代码来求解与快堆相关的气溶胶的通用动力学方程（GDE）简化形式。本研究考虑了二氧化锰、二氧化 CeO2 和钠的气溶胶。对 DS 代码进行了修改和进一步改进，加入了重力凝结、湍流凝结、布朗沉积、重力沉积和热泳沉积，从而使代码能够处理钠着火后导致气溶胶沉积的不同过程。此外，还通过修改库珀方程增强了代码的功能，以考虑相对湿度的影响。改进后的代码通过在印度气溶胶测试设施（ATF）、印度小型钠火灾设施（MINA）和芬兰 AHMED（气溶胶和传热测量装置）进行的不同实验进行了验证。来自不同设施的验证证实了代码在各种情况下的适用性。结果发现，修改后的 DS 代码能够以合理的精度预测不同围护结构中悬浮气溶胶质量浓度的衰减。

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Improvement and validation of discrete-sectional method based code for fast reactor aerosol dynamics

The study of the dynamics of aerosols produced during a severe accident is vital to the safety analysis of a Sodium-cooled Fast Reactor (SFR). Sodium leakage into the containment following a severe accident may result in the production of sodium aerosols along with fission product aerosols. The in-containment radioactive source term depends upon the settling behaviour of fission product aerosols, which co-agglomerate with sodium fire aerosols. Hence, an in-depth understanding of the dynamics and deposition of aerosols within the containment is essential for the safety assessment of an SFR. The current work uses an open-source code based on the Discrete-Sectional (DS) method to solve the simplified form of General Dynamics Equation (GDE) for aerosols relevant to fast reactors. Aerosols of SrO₂, CeO₂ and sodium are considered in the present work. The DS code has been modified and further improved by including gravitational coagulation, turbulent coagulation, Brownian deposition, gravitational deposition and thermophoretic deposition so that the code can handle the different processes leading to the deposition of aerosols following a sodium fire. The code is also enhanced to account for the effect of relative humidity through the modified Cooper's equation. The improved code is then validated with different experiments conducted in the Aerosol Test Facility (ATF), India; Mini Sodium Fire Facility (MINA), India; and AHMED (Aerosol and Heat Transfer Measurement Device), Finland. Validation from different facilities confirms the applicability of the code to various scenarios. It is found that the modified DS code could predict the decay of suspended mass concentration of aerosols in different enclosures with reasonable accuracy.

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.