Neutronic design and analysis of the accident-tolerant fuel (ATF) application to VVER-1000 nuclear reactor as well as evaluation of dynamic parameters

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-30 DOI:10.1016/j.nucengdes.2024.113814

S. Nasiri, G.R. Ansarifar

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Abstract

In order to improve the safety of commercial nuclear reactors, this paper presents neutronic design and analysis of the accident-tolerant fuels (ATF) application to VVER-1000 nuclear reactor. The study commences by simulating a fuel assembly containing 2.4% enriched uranium.

The simulation of a VVER-1000 reactor core loaded with standard uranium dioxide (UO₂) fuel was then conducted using the MCNPX 2.6 code. This simulation yielded various neutronic and dynamic parameters, including the multiplication factor, excess reactivity, delayed neutron fraction, fuel and coolant temperature reactivity feedbacks, power peaking factor, and fuel burn-up. These values were subsequently compared with existing reference data.

Finally, the reactor core was simulated using accident-tolerant fuel. The resulting data was analyzed to identify the optimal combination of fuel and cladding. Throughout the study, the MCNPX 2.6 software was employed for neutronic core analysis. Comparative analysis revealed that uranium carbide (UC) offers superior safety margins in both neutronic and dynamic aspects, outperforming uranium dioxide (UO₂) and uranium mononitride (UN).

Simulations exploring the use of silicon carbide (SiC) and FeCrAl as alternative cladding materials within the reactor core demonstrated potential advantages over traditional Zirconium (Zr). Results indicate that application of ATF can improve cycle length, temperature reactivity feedbacks and power peaking factor compare to the reference core (UO₂ + Zr), significantly.

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VVER-1000核反应堆容错燃料（ATF）的中子设计与分析及动态参数评价

为了提高商用核反应堆的安全性，本文对应用于VVER-1000核反应堆的容错燃料进行了中子设计与分析。研究从模拟含有2.4%浓缩铀的燃料组件开始。然后，使用MCNPX 2.6代码对装载标准二氧化铀（UO2）燃料的VVER-1000堆芯进行了模拟。该模拟得到了各种中子和动态参数，包括倍增因子、过量反应性、延迟中子分数、燃料和冷却剂温度反应性反馈、功率峰值因子和燃料燃耗。随后将这些值与现有参考数据进行比较。最后，采用耐事故燃料对堆芯进行了模拟。分析了得到的数据，以确定燃料和包壳的最佳组合。在整个研究过程中，使用MCNPX 2.6软件进行中子核分析。对比分析表明，碳化铀（UC）在中子和动力学方面都具有优越的安全边际，优于二氧化铀（UO2）和单氮化铀（UN）。利用碳化硅（SiC）和铁铁（FeCrAl）作为反应堆堆芯内替代包层材料的模拟研究表明，它们比传统的锆（Zr）具有潜在的优势。结果表明，与参考磁芯（UO2 + Zr）相比，ATF的应用可以显著改善循环长度、温度反应性反馈和功率峰值因子。

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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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.