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Showing 1 to 20 of 36 for “"Loss of Coolant Accident"”.
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Evaluation of multilayer silicon carbide composite cladding under loss of coolant accident conditions
… and a 1000°C higher melting temperature, all of which are important during a loss of coolant accident (LOCA). To improve the performance of SiC cladding, a multilayered architecture consisting of layers of monolithic SiC (mSiC) and SiC/SiC ceramic matrix composite (CMC) has been proposed. In …
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Effects of Nodalization on Containment Analysis in a Loss of Coolant Accident Using GOTHIC
Existing containment models for a loss of coolant accident at many nuclear power plants were created in the 1970s using older computer technology and thermal hydraulic models which were available at that time. While conservative, these models may not present the detail necessary to identify …
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EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR
… Commission (U.S. NRC) to assess the effect of debris loading on pressurized water reactor (PWR) emergency core cooling systems (ECCS) sump strainers during a Loss-of-Coolant Accident (LOCA). Potential contributors to the debris loading include latent dirt, fiberglass insulation, paints, …
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Spatio-temporal probabilistic methodology to estimate location-specific loss-of-coolant accident frequencies for risk-informed analysis of nuclear power plants
… Regulatory Commission (NRC) has promoted the use of Probabilistic Risk Assessment (PRA) in nuclear regulatory activities. Since loss-of-coolant accidents (LOCAs) are critical initiating events for many PRA applications, the NRC has taken steps towards the quantification of LOCA frequencies for use …
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A Study on the Mechanical Characteristics of a Fiberglass Bed Formed During a Loss-of-Coolant-Accident at a PWR Nuclear Facility
Following a Loss-of-Coolant-Accident (LOCA) in one of the primary coolant lines in the containment building of a PWR Facility, it is possible that fiberglass pipe insulation could be dislodged and washed down to the sump pool. This fiberglass could collect into a bed' and cause blockage on the sump …
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A theoretical analysis of the temperature response in a bimetallic, composite geometry, nuclear reactor pressure vessel undergoing a loss-of-coolant accident
This work addresses the problem of thermal shock in a light water cooled nuclear reactor undergoing emergency cooling following a hypothetical loss of coolant accident. Portions of this work provide novel approaches to heat conduction problems. Moreover, the scope of this analysis is broader than …
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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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Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor
… reactor by analyzing the main steam line break loss of coolant accident performed in the Purdue university multi-dimensional test assembly (PUMA). RELAP5 code simulations, both for the PUMA main steam line break (MSLB) case and for the simplified boiling water reactor (SBWR) MSLB case have been …
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Heat and Mass Transfer in Reactor Core During a Loca-Single Channel Analysis (Mixed Convection, Numerical, Flow, Thermal-Hydraulics)
Ability to predict the scenario following a loss-of-coolant accident (LOCA) is of central importance in the safety analysis of water reactors. During LOCA, the reactor core is uncovered and the residual water inventory is boiled off by fission products decay heating. For the Three Mile Island …
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A thermal-hydraulic analysis of the cooling system for the 500 KW Virginia Polytechnic Institute and State University reactor
In order to increase the usefulness of the nuclear research reactor, it is necessary to enhance the neutron fluxes available in the experimental facilities. One method of attaining this objective is to increase the power level of the reactor. The VPI&SU 100 KW research reactor has been studied to …
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Helium-Air mixing in simulated reactor cavities of Very High Temperature Reactors
… and commercial purposes. They have a high level of inherent passive safety making them a viable alternative to traditional water-cooled reactors. These helium gas-cooled reactors use graphite containing U-235 TRISO fuel particles in their core, as a moderator to slow down neutrons for fission …
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The consequence of station blackout in a nuclear power plant
The main purpose of the nuclear power plant is to generate electricity and to supply it to the grid and its auxiliaries systems. Since nuclear safety overrides the production of electricity and therefore nuclear power plants are designed to protect the public and the environment from the radiation …
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Design of an experimental loop for post-LOCA heat transfer regimes in a Gas-cooled Fast Reactor
The goal of this thesis is to design an experimental thermal-hydraulic loop capable of generating accurate, reliable data in various convection heat transfer regimes for use in the formulation of a comprehensive convection heat transfer correlation. The initial focus of the design is to ensure that …
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Feasibility of risk-informed regulation for Generation-IV reactors
With the advent of new and innovative Generation-IV reactor designs, new regulations must be developed to assure the safety of these plants. In the past a purely deterministic way of developing design basis accidents was prevalent, however this is felt to not be satisfactory, since this leaves …
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Transient analysis of hydride fueled pressurized water reactor cores
… performed to determine the optimum combination of lattice pitch, rod diameter, and channel shape-further referred to as geometry-for maximizing power given specific transient conditions for pressurized water reactors (PWR) loaded with either U02 or UZrH1.6 fuel. Several geometries have been …
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CFD Analyses of Flow Structures in Air-Ingress and Rod Bundle Problems
… One study is the air-ingress phenomenon during a loss of coolant accident (LOCA) scenario, and the other is a 5-by-5 bundle assembly problem under a design of PWRs. The objectives are to investigate the Kelvin-Helmholtz instability of the gravity-driven stratified flows inside a coaxial pipe and …
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An alternate high pressure injection system for pressurized-water reactors
… Injection System (ICIS) performance during a loss-of-coolant accident (LOCA) due to a major rupture in the primary system of a pressurized water reactor (PWR), tests were conducted using the thermal-hydraulic computer code RELAP4/MOD5.</p> <p>The results for the overall plant system show that …
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Long-Term Cooling of an SBLOCA: Boron Precipitation in the Core, Boron Dilution in the Steam Generators
… core cooling (LTCC) during the small break loss-of-coolant accident (SBLOCA): boron precipitation and boron dilution. The initial consequences of the SBLOCA are mitigated by the emergency safety systems, but the core continues to boil. As boron is less volatile than steam, the steam is …
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Flooding and non-equilibrium in counter-current flows with reference to pressurised water reactors
During the refill stage of a Loss of Coolant Accident (LOCA) in Pressurised Water Reactor (PWR) the effectiveness with which the emergency coolant penetrates to the lower plenum, and hence to the core, is of paramount importance. This thesis presents the results of experimental and theoretical work …
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