Method and apparatus for automated crack behavior prediction determination
AssigneeGeneral Electric Company
InventorsRonald Martin Horn, F. Peter Ford, Peter L. Andersen, Jenny Y. Mui
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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.
Claims5
A method of predicting component crack behavior in a nuclear reactor, the method comprising:
- (a) receiving input water chemistry characteristics over a global computer network;
- (b) accessing a crack growth behavior model that predicts component crack behavior according to the input water chemistry characteristics;
- and
- (c) outputting over the global computer network a crack growth prediction profile according to an analysis of the crack growth behavior model by outputting a real time crack growth prediction according to the input water chemistry characteristics.
A computer system for predicting component crack behavior in a nuclear reactor, the computer system comprising:
- at least one user computer running a computer program that receives input water chemistry characteristics;
- and
- a system server running a server program, the at least one user computer and the system server being interconnected by a computer network, the system server storing a crack growth behavior model that predicts component crack behavior according to the input water chemistry characteristics, and the system server outputting over the computer network a crack growth prediction profile according to an analysis of the crack growth behavior model by outputting a real time crack growth prediction according to the input water chemistry characteristics.
A computer program embodied on a computer readable medium for predicting component crack behavior in a boiling water nuclear reactor, the computer program comprising:
- means for receiving input water chemistry characteristics over a global computer network;
- means for accessing a crack growth behavior model that predicts component crack behavior according to the input water chemistry characteristics;
- and
- means for outputting over the global computer network a crack growth prediction profile or crack growth based result according to an analysis of the crack growth behavior model by outputting a real time crack growth prediction according to the input water chemistry characteristics.
A method of predicting component crack behavior in a nuclear reactor, the method comprising:
- (a) receiving input water chemistry characteristics over a global computer network;
- (b) accessing a crack growth behavior model that predicts component crack behavior according to the input water chemistry characteristics, wherein the input water chemistry characteristics are the only data input via the global computer network for predicting component crack behavior;
- and
- (c) outputting over the global computer network a crack growth prediction profile according to an analysis of the crack growth behavior model by outputting a real time crack growth prediction according to the input water chemistry characteristics.
Dependencies are inferred from the claim text.