规模对压水反应堆堆芯设计、燃料成本和乏燃料量的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

摘要

通过模块化、制造和批量生产来提高核能的经济竞争力和部署速度的愿望导致了小型反应堆的发展。由于压水堆(PWR)主要采用标准的 17x17 燃料技术,这就意味着堆芯中的燃料组件数量减少,有时燃料高度也会降低。为了评估堆芯设计的这种规模变化对燃料循环成本和乏燃料量的影响,我们开发了一个范围分析工具,该工具基于无限晶格计算、泄漏、燃料管理减少模型和平准化单位电力成本(LCOE)估算。因此,成本动态由燃料比功率、燃耗、堆芯泄漏、进料、循环长度、燃料组件高度以及铀市场数据驱动,并通过一套一致的假设和分析方法加以捕捉。评估和比较了具有代表性的 5 个压水堆设计。追求更高的比功率和最佳燃耗是降低燃料成本的主要驱动力,但必须对实际限制和机会进行评估,以确定增强燃料运行的可行性。因此,我们使用 SIMULATE3 代码对 5 种压水堆变化进行了详细的堆芯设计,包括自然冷却剂循环模式和强制冷却剂循环模式、两种反应堆规模、73、112 和 123 kW/l 的功率密度以及更高的放电燃耗。设计和优化在晶格级、反射器级和堆芯装料级进行。本文分析并报告了令人满意的稳态运行,包括功率分配、冷却剂运行限制和反应性要求。详细堆芯设计的燃料经济性证实了范围分析的结论。尽管小型压水堆的解锁功率有所提高,但在给定燃料比功率下可达到的燃烧度需要更高的浓缩度,而且较短的燃料高度会导致单位燃料质量的制造成本更高,这使得缩小堆芯尺寸在燃料循环方面的成本更加昂贵。本文报告了所设计压水堆的乏燃料量。无论考虑的规模如何,这些乏燃料量都是由堆芯平均排出燃耗驱动的。本文还研究了与重反射器增益、燃料-反射器替代以及美国处置成本政策有关的其他成本和堆芯性能方面的问题。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Scale effects on core design, fuel costs, and spent fuel volume of pressurized water reactors

The desire to improve the economic competitiveness and deployment pace of nuclear energy through modularization, manufacturing, and series production had led to the development of smaller size reactors. As the standard 17x17 fuel technology is mainly maintained in the pressurized water reactors (PWRs) category, this translates into a lower number of fuel assemblies in the core and sometimes a reduced fuel height. To assess the impact of such scale change in core design on fuel cycle cost and spent fuel volume, a scoping analysis tool is developed based on infinite lattice calculations, leakage, fuel management reduced models, and levelized unit cost of electricity (LCOE) estimate. As such, cost dynamics driven by fuel specific power, burnup, core leakage, feed, cycle length, fuel assembly height as well as uranium market data are captured with consistent set of assumptions and analysis methods. A selection of 5 reactor designs representative of leading PWR developers is assessed and compared. Pursuing higher specific powers and optimal burnups are highlighted as the main fuel cost reduction drivers, nevertheless, practical limitations and opportunities must be evaluated to establish the feasibility of such enhanced fuel operation. In consequence, a detailed core design is performed using SIMULATE3 code for 5 PWR variations including natural and forced coolant circulation modes, two reactor scales, power densities of 73, 112, and 123 kW/l and higher discharge burnups. Design and optimization are performed at the lattice level, for the reflector, and at the core loading level. Satisfactory steady-state operation including power distribution, coolant operating limits, and reactivity requirements are analyzed and reported in this paper. The fuel economics of the detailed core designs confirm the scoping analysis findings. Despite the unlocked power uprates in small PWRs, the achievable burnup for a given fuel specific power requires more enrichment and shorter fuel height results in higher fabrication costs per mass of fuel, which makes scaling down core size a more expensive endeavor on the fuel cycle front. Spent fuel volumes are reported for the PWRs designed in this paper. These volumes are driven by the core average discharge burnup regardless of the scale in consideration. Additional cost and core performance aspects related to heavy reflector gains, fuel-reflector substitution, and disposal cost policy in the U.S. are examined.

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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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