| Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation. | |
| Tentner, A. M. ; Parma, E. ; Wei, T. ; Wigeland, R. ; Nuclear Engineering Division ; SNL ; INL | |
| 关键词: ACCIDENTS; DESIGN; EVALUATION; FAST REACTORS; LIQUID METALS; MANAGEMENT; MITIGATION; PERFORMANCE; SAFETY; SAFETY MARGINS; SODIUM; US DOE; | |
| DOI : 10.2172/973483 RP-ID : ANL-GENIV-128 PID : OSTI ID: 973483 Others : TRN: US1001920 |
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| 美国|英语 | |
| 来源: SciTech Connect | |
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【 摘 要 】
An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.
【 预 览 】
| Files | Size | Format | View |
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| RO201704240002805LZ | 2385KB |
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