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Improved channel analysis for reactivity insertion transients

R. Vera, Fava Javier

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Abstract

The Reactor Core Fast Transient (RCFT) model has been formulated, to peform analysis of reactivity insertion transients in Light Water Reactors (LWR), such as control rod ejection, loss forced reactor coolant, and reactor coolant pump rotor seizure or shaft break. The RCFT model uses an axially and radially sectionalized single fuel/coolant channel to model a reactor core. The RCFT model has the following characteristics: (1) use of cylindrical geometry, (2) analytical solution (not numerical approximation) for steady-state fuel temperature, (3) explicit model of fuel pellet-clad gap, without mixed nodes properties approximations, (4) annular pellet model, for use in high burnup fuel analysis, (5) direct procedure (no iteration) for pressure drop forced transient calculation, (6) compliance with NRC Regulatory Guide 1.77, for PWR control rod-ejection transient analysis. The RCFT model incorporates additional features over currently licensed models, and has the potential to perform improved fuel transient behavior analyzes for the core reload licensing submittals of Light Water Reactors.

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What this paper is about

The Reactor Core Fast Transient (RCFT) model has been formulated, to peform analysis of reactivity insertion transients in Light Water Reactors (LWR), such as control rod ejection, loss forced reactor coolant, and reactor coolant pump rotor seizure or shaft break. The RCFT model uses an axially and radially sectionalized single fuel/coolant channel to model a reactor core. The RCFT model has the following characteristics: (1) use of cylindrical geometry, (2) analytical solution (not numerical approximation) for steady-state fuel temperature, (3) explicit model of fuel pellet-clad gap, without mixed nodes properties approximations, (4) annular pellet model, for use in high burnup fuel analysis, (5) direct procedure (no iteration) for pressure drop forced transient calculation, (6) compliance with NRC Regulatory Guide 1.77, for PWR control rod-ejection transient analysis. The RCFT model incorporates additional features over currently licensed models, and has the potential to perform improved fuel transient behavior analyzes for the core reload licensing submittals of Light Water Reactors.

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Available abstract

The Reactor Core Fast Transient (RCFT) model has been formulated, to peform analysis of reactivity insertion transients in Light Water Reactors (LWR), such as control rod ejection, loss forced reactor coolant, and reactor coolant pump rotor seizure or shaft break. The RCFT model uses an axially and radially sectionalized single fuel/coolant channel to model a reactor core. The RCFT model has the following characteristics: (1) use of cylindrical geometry, (2) analytical solution (not numerical approximation) for steady-state fuel temperature, (3) explicit model of fuel pellet-clad gap, without mixed nodes properties approximations, (4) annular pellet model, for use in high burnup fuel analysis, (5) direct procedure (no iteration) for pressure drop forced transient calculation, (6) compliance with NRC Regulatory Guide 1.77, for PWR control rod-ejection transient analysis. The RCFT model incorporates additional features over currently licensed models, and has the potential to perform improved fuel transient behavior analyzes for the core reload licensing submittals of Light Water Reactors.

Key concepts: Burnup, Control rod, Nuclear engineering, Coolant, Transient (computer programming), Pressure drop, Light-water reactor, Scram

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