模块化设计
计算机科学
软件部署
可靠性工程
集合(抽象数据类型)
失水事故
编码(集合论)
轻水反应堆
系统工程
核工程
机械工程
工程类
软件工程
冷却液
操作系统
程序设计语言
作者
Palash Kumar Bhowmik,Carlos E. Estrada Perez,Joshua D. Fishler,Silvino A. Balderrama Prieto,Isaac D. Reichow,Justin T. Johnson,Piyush Sabharwall,James E. O’Brien
标识
DOI:10.1016/j.pnucene.2023.104697
摘要
This study reviews previous experimental facilities and test programs relevant to water-cooled reactor system design and analysis to meet regulatory compliances. This study aims to find the best solution for designing the required experiments, obtaining necessary test data, and verifying the developed computer code/models to support the new reactor design and development while minimizing cost and time while leveraging experiences from previous facilities to minimize. Nuclear reactor licensing requires supportive design, analysis, and experimental results to ensure the safety of the full-scale prototype reactor in regular operation, as well as during postulated accident scenarios. These reactor design analyses are generally performed using system codes and other associated simulation tools that require assessment, verification and validation using an appropriate experimental dataset. Experimental facilities used for reactor system safety analysis and system code assessments are categorized into integral effects test (IET) and separate effects test (SET) facilities. These IET and SET experiments and studies use geometrically scaled systems to reproduce the prototype system behavior at a reasonable cost, albeit with some scaling-related distortions. The design challenge of these model facilities is to identify and minimize scaling distortions while reproducing the most important operational phenomena in steady-state operation and in postulated accident scenarios. Lessons learned from previous experimental facilities, models, and correlations can support the development of new multipurpose, scaled, hybrid, integrated, and modular experimental facilities for advanced light water-cooled small modular reactors (SMRs). Successful operation of these facilities can significantly reduce upfront reactor development and demonstration costs and time to deployment.
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