Published July 1985 | Version v1
Journal article

Analysis of a hot-leg small break loss-of-coolant accident in a three-loop westinghouse pressurized water reactor plant

  • 1. Energy Inc., Idaho Falls, ID

Description

The RETRAN-02 computer code was used to perform a best-estimate analysis of a 7.52-cm-diam hotleg 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

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
70
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
104-110
ISSN
0029-5450
CODEN
NUTYB