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Site risk analysis for nuclear installations—Nordic method developments and pilot studies
Published in Stein Haugen, Anne Barros, Coen van Gulijk, Trond Kongsvik, Jan Erik Vinnem, Safety and Reliability – Safe Societies in a Changing World, 2018
J.-E. Holmberg, O. Bäckström, E. Cederhorn, C. Sunde, T. Tyrväinen
Risk metrics for level 1 PSA can include the following CDF metrics: Single-Unit Core Damage Frequency (SUCDF) – frequency of a reactor accident involving core damage on one and only one reactor unit per site calendar-year.Multi-Unit Core Damage Frequency (MUCDF) – frequency of an accident involving core damage on two or more reactor units concurrently per site calendar-yearSite Core Damage Frequency (SCDF) - frequency of a reactor accident involving core damage on one or more reactor units concurrently per site calendar-year.
Nuclear reactor safety politics in the USA
Published in David Toke, Geoffrey Chun-Fung Chen, Antony Froggatt, Richard Connolly, Nuclear Power in Stagnation, 2021
David Toke, Geoffrey Chun-Fung Chen, Antony Froggatt, Richard Connolly
Probabilistic Risk Analysis (PRA) is applied to examine the likelihood of accidents and, according to the NRC (NRC 2004, 13), ‘regulatory initiatives involving new requirements to prevent core damage should result in a reduction of at least 1.0 × 10−5 in the estimated mean value CDF’ (core damage frequency). PRA is itself a contested concept; according to nuclear critics, it can artificially limit the assessments of risk, given that many risks are simply unknown.
Severe Accident Phenomena: A Comparison Among the NuScale SMR, Other Advanced LWR Designs, and Operating LWRs
Published in Nuclear Technology, 2020
Scott J. Weber, Etienne M. Mullin
Throughout the history of the nuclear industry, protection of workers, the public, and the environment has been a significant priority. Accordingly, the reactors comprising the existing nuclear fleet have been designed with multiple safety systems and layers of barriers against radioactive release. Severe accidents require multiple successive failures to occur and as such are very rare. The U.S. Nuclear Regulatory Commission (NRC) evaluates the risk for operating plants in the United States against a core damage frequency (CDF) goal of less than 1 × 10−4/year (Ref. 1). Nevertheless, there have been three prominent occurrences of severe accidents worldwide: Three Mile Island Unit 2 (TMI-2), Chernobyl, and Fukushima Daiichi. Since any incident at a nuclear plant has the potential to endanger public safety, the primary focus of reactor design is on prevention of accidents occurring. However, reactors also include features that are designed to manage the progression of a severe accident and limit off-site consequences in the unlikely event that one occurs. This paper focuses on the design features and safety systems that can mitigate the effects of a postulated severe accident.
Use of Dynamic Event Trees and Deep Learning for Real-Time Emergency Planning in Power Plant Operation
Published in Nuclear Technology, 2019
Ji Hyun Lee, Alper Yilmaz, Richard Denning, Tunc Aldemir
Probabilistic risk assessments (PRAs) are used to estimate the core damage frequency and containment failure frequency of nuclear power plants (NPPs) in case of an accident and the possible subsequent risk of radioactive exposure of the public to radiation. PRAs have three levels of classification1: