Analysis of a Hot-Leg Small Break Loss-of-Coolant Accident in a Three-Loop Westinghouse Pressurized Water Reactor Plant
Craig E. Peterson, V.K. Chexal, Talmage B. Clements
Abstract
Craig E. Peterson, V.K. Chexal, Talmage B. Clements
Abstract
The RETRAN-02 computer code was used to perform a best-estimate analysis of a 7.52-cm-diam hot-leg break in a three-loop Westinghouse pressurized water reactor. This break size produced a net primary coolant mass depletion through the early portion of the transient. The primary system started to refill only after the accumulator valves opened. As the primary system refilled, there were extreme temperature differentials around the system with cold, denser fluid collecting at the lower elevations and two-phase fluid at higher elevations.
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The RETRAN-02 computer code was used to perform a best-estimate analysis of a 7.52-cm-diam hot-leg break in a three-loop Westinghouse pressurized water reactor. This break size produced a net primary coolant mass depletion through the early portion of the transient. The primary system started to refill only after the accumulator valves opened. As the primary system refilled, there were extreme temperature differentials around the system with cold, denser fluid collecting at the lower elevations and two-phase fluid at higher elevations.
Key concepts: Coolant, Nuclear engineering, Pressurized water reactor, Accumulator (cryptography), Environmental science, Loss-of-coolant accident, Materials science, Nuclear physics