Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 12 of 12 for “"Severe accident"”.
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Detector integration of severe accident management instrumentation for robotic applications at nuclear reactor facilities
In the aftermath of a nuclear accident, robots can be used to monitor and assess radiological contamination, preventing harmful exposure to plant personnel. In this work, several detectors were evaluated to be supplemented onto the Husky UGV. Specifically, the RadEye Gamma Survey Meter, the …
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Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
… is a state-of-the-art code used to simulate the severe accident progression of a nuclear power plant. The first objective was developing the capabilities in Thermochimica to handle the Ionic Two-sublattice Liquid Model in order to leverage the Thermodynamics of Advanced Fuels – International …
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Effects of thermal stresses on Pressurised Water Reactor nuclear containment vessels following a Loss of Coolant Accident with assimilated containment filtered venting system
… power plant, the last barrier under normal and accident operations is the containment building. This is normally constructed from concrete reinforced with steel bars, which are prestressed to enhance the overall capability to withstand thermodynamic stresses like over-pressurisation and high …
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An analysis of the spreading of radionuclides from a vent of an offshore floating nuclear power plant
… This design will minimize the probability of a severe accident leading to a release of radioactive material, but as always a release must still be planned for. The offshore siting of an OFNP allows for increased distance to human populations in addition to extra filtering of released radioactive …
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Numerical Simulation of Corium Jet Fragmentation
Severe accident studies have become important for understanding the environmental impact of nuclear power following the Three Mile Island (TMI) accident. Severe accident phenomena are interdisciplinary since they can include the interaction of molten corium with reactor structures and water, and …
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First Order Assessment of Heat Transfer due to the Loss of Inventory in a Spent Fuel Pool
The Fukushima Daiichi Nuclear Power Plant accident created renewed international interest in the behaviour of spent fuel subsequent to a complete loss of water inventory in a spent fuel pool (SFP). The study conducted in this dissertation serves as a starting point in gaining an understanding of …
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Integrating geographic information systems with the Level 3 Probabilistic Risk Assessment of nuclear power plants to advance modeling of socio-technical infrastructure in emergency response applications
… about population response from a radiological accident such as the one that occurred at the Fukushima Daiichi Nuclear Power Plant in 2011, understanding the implications of the social makeup of the population in the vicinity of an NPP has the potential to give decision makers information about …
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Reforming EPZ framework for new nuclear reactors (SMR): an open-source and climate-aware approach
… geographical conditions. The analysis examined severe accident such as Long- term Station Blackout (LSTBO), focused on how climate change increases risks related to things like flooding and severe snowfall. This study evaluates fixed-radius EPZ models because it conducts radiological dispersion …
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Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors
… of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, employed in Advanced Light Water Reactors, was investigated. A model simulating the two-phase flow and heat transfer on the reactor vessel outer surface quantified the increase in decay power that can be removed …
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Exclusions Zones for Small Modular Reactors
… to dilute any radioactive releases during an accident, to a level below the safe regulated radiation dose for the public. A hypothetical severe accident is considered for a generic SMR, and the whole-body radiation dose associated with the accident was estimated at various distances and …
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System dynamics modeling for human performance in nuclear power plant operation
… or can be amplified and may result in a severe accident finally. This research expanded ORSIM (Nuclear Power Plant Operations and Risk Simulator) model, which is a quantitative computer model built by system dynamics methodology, on human reliability aspect and used it to predict the …
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Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications
In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the outer surface of the reactor vessel. Increasing the CHF level by altering the cooling fluid would increase the safety margin of current …