Difference between revisions of "Automated burnup sequence"

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(Created page with "Generating group constants for a fuel cycle simulator calculation requires covering all operating conditions within the reactor core throughout the simulated cycle, such as fu...")
 
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Generating group constants for a fuel cycle simulator calculation requires covering all operating conditions within the reactor core throughout the simulated cycle, such as fuel temperature, coolant void fraction (BWR) and the concentration of soluble absorber (PWR). The group constant data is parametrized according to discrete state-points, from which the core simulator interpolates the values corresponding to burnup and thermal hydraulic state. Since
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Homogenized group constants form the input data for core-level fuel cycle and transient simulator calculations. The data is parametrized according to discrete state-points, which are defined by the local thermal hydraulic conditions together with reactivity control. The process of group constant generation must cover the full range of operating states within the reactor core, which often requires repeating the assembly-level calculation thousands of times. Since the local operating conditions inside a fuel assembly also affect how the materials are depleted, the state-points by which the data is parametrized are not completely independent either. The calculations are instead divided into:
the local operating conditions inside a fuel assembly also affect how the assembly is depleted, the state-points by which the group constant data is parametrized are not completely independent. The calculations are instead divided into:
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Revision as of 19:54, 19 February 2016

Homogenized group constants form the input data for core-level fuel cycle and transient simulator calculations. The data is parametrized according to discrete state-points, which are defined by the local thermal hydraulic conditions together with reactivity control. The process of group constant generation must cover the full range of operating states within the reactor core, which often requires repeating the assembly-level calculation thousands of times. Since the local operating conditions inside a fuel assembly also affect how the materials are depleted, the state-points by which the data is parametrized are not completely independent either. The calculations are instead divided into: