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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Myoung-Suk Kang, Gyunyoung Heo, Young-Seok Lee, Hyuck Jong Kim
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 1-8
doi.org/10.13182/FST11-A12397
Articles are hosted by Taylor and Francis Online.
This paper surveyed the safety issues and the related engineered safety features for designing Korean demonstration fusion power plant. Since the design process was staying at a conceptual stage and regulatory requirements were not fully matured, it was significant to investigate the broad options and select feasible candidates. In order to straddle system's performance and risk, the study followed the principles of Axiomatic Design (AD) and Fault Tree Analysis (FTA). The interplay of AD and FTA facilitates developing the design of fusion power plants for enhancing performance (power generation) and reducing risk (radiation hazard). While AD is a synthesis process in the success domain to compromise functional requirements and design options in terms of a functional hierarchy tree, FTA considers a safety analysis process in the failure domain. The functional hierarchy tree, which is also named as a functional requirement and design parameter tree, showed the entire fusion power plant with multiple design candidates in a hierarchic manner. This tree can be transformed into a fault tree. While developing the fault tree, the list of DBAs which are the failure modes for the leaves of the fault tree could be recognized, and the associated engineered safety features were proposed depending on the consequences of a DBA. As a demonstration for analyzing a DBA, the mass and energy release calculation for in-vessel loss of coolant accident was described.