Abstract: An insulated solution injector may include an outer tube and an inner tube arranged within the outer tube. The outer tube and the inner tube may define an annular space therebetween, and the inner tube may define a solution space within. The annular space may be configured so as to insulate the solution within the solution space. As a result, the solution may be kept to a temperature below its decomposition temperature prior to injection. Accordingly, the decomposition of the solution and the resulting deposition of its constituents within the solution space may be reduced or prevented, thereby decreasing or precluding the occurrence of a blockage.

Abstract: A method for applying a coating to a defect area of a reactor component includes forming a patch on the reactor component at the defect area using a plasma-spray coating process. The plasma-spray coating process includes grounding the reactor component and a power supply of a plasma gun to a common ground such that a potential difference exists between the reactor component and a cathode of the plasma gun, and concurrently directing an ion-etching stream and a coating stream towards the region of the reactor component using the plasma gun while maintaining a desired distance between the plasma gun and the region of the reactor component. The directing the ion-etching stream includes heating the region of the reactor component using a plasma stream exiting a spray nozzle of the plasma gun. The coating stream includes droplets of a coating material.

Abstract: A method for applying a coating to a defect area of a reactor component includes forming a patch on the reactor component at the defect area using a plasma-spray coating process. The plasma-spray coating process includes grounding the reactor component and a power supply of a plasma gun to a common ground such that a potential difference exists between the reactor component and a cathode of the plasma gun, and concurrently directing an ion-etching stream and a coating stream towards the region of the reactor component using the plasma gun while maintaining a desired distance between the plasma gun and the region of the reactor component. The directing the ion-etching stream includes heating the region of the reactor component using a plasma stream exiting a spray nozzle of the plasma gun. The coating stream includes droplets of a coating material.

Abstract: An insulated solution injector may include an outer tube and an inner tube arranged within the outer tube. The outer tube and the inner tube may define an annular space therebetween, and the inner tube may define a solution space within. The annular space may be configured so as to insulate the solution within the solution space. As a result, the solution may be kept to a temperature below its decomposition temperature prior to injection. Accordingly, the decomposition of the solution and the resulting deposition of its constituents within the solution space may be reduced or prevented, thereby decreasing or precluding the occurrence of a blockage.

Abstract: A method of predicting component crack behavior in a nuclear reactor provides access to a crack growth behavior model over a global network. A user inputs water chemistry and material characteristics of a particular nuclear reactor and can perform crack growth rate predictions by accessing the behavior model over the computer network. A crack growth prediction profile or crack growth based result is output over the network according to an analysis by the behavior model.

Abstract: The method includes receiving parameters input by a user and calculating crack behavior estimations based on the received parameters by using a plurality of accessible crack behavior models. The crack behavior estimations calculated from each of the models are displayed to the user in order to illustrate how the different models compare in calculating a desired crack behavior profile. The displayed crack behavior estimations utilize a compilation of both historical crack growth rate data, as well as predicted crack growth rate data, and may be displayed as an estimated crack growth rate versus time, or as estimated crack growth over time. These parameters are displayed graphically for each crack behavior model in order to enable the user to make a comparison for each crack growth model.

Abstract: Plant parameters and performance of an industrial plant such as a boiling water nuclear reactor plant can be assessed over a global network. Plant parameter and performance data are compiled from a plurality of operating plants, and this data is stored in a categorized historical database. Users are provided access to the historical database over the global network to perform self-assessments and generate comparison graphics showing percentile ranking, trending, etc. Data generated at a particular plant can be downloaded to a server site for more detailed engineering analyses using conventional methods. Reports and commentary on the analyses can be returned to the user via the global network.

Abstract: A method of monitoring process parameters and process effectiveness over a global network enables multiple processing sites to utilize globally compiled field data to determine process parameters and the like. Application parameters are received from multiple processing sites over the global network, and post-application data is received from the multiple processing sites at preset time intervals. The application parameters and the post-application data are analyzed to determine analytical models for future application parameters, which are accessible by system users via the global network.

Abstract: The method includes receiving parameters input by a user and calculating crack behavior estimations based on the received parameters by using a plurality of accessible crack behavior models. The crack behavior estimations calculated from each of the models are displayed to the user in order to illustrate how the different models compare in calculating a desired crack behavior profile. The displayed crack behavior estimations utilize a compilation of both historical crack growth rate data, as well as predicted crack growth rate data, and may be displayed as an estimated crack growth rate versus time, or as estimated crack growth over time. These parameters are displayed graphically for each crack behavior model in order to enable the user to make a comparison for each crack growth model.

Abstract: A method of predicting component crack behavior in a nuclear reactor provides access to a crack growth behavior model over a global network. A user inputs water chemistry and material characteristics of a particular nuclear reactor and can perform crack growth rate predictions by accessing the behavior model over the computer network. A crack growth prediction profile or crack growth based result is output over the network according to an analysis by the behavior model.

Abstract: Plant parameters and performance of an industrial plant such as a boiling water nuclear reactor plant can be assessed over a global network. Plant parameter and performance data are compiled from a plurality of operating plants, and this data is stored in a categorized historical database. Users are provided access to the historical database over the global network to perform self-assessments and generate comparison graphics showing percentile ranking, trending, etc. Data generated at a particular plant can be downloaded to a server site for more detailed engineering analyses using conventional methods. Reports and commentary on the analyses can be returned to the user via the global network.