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Atlanta, GA|Atlanta Marriott Marquis
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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.