ECCSA-1: A DIGITAL COMPUTER PROGRAM FOR THERMAL AND HYDRAULIC ANALYSIS OF CORE CHANNELS IN THE EVENT OF A NUCLEAR-REACTOR LOSS-OF-COOLANT ACCIDENT

ECCSA-I is a digital computer program specifically designed to predict the thermal and hydraulic performance of reactor core channels during a loss-of-coolant accident and subsequent emergency core cooling injection. The program represents reactor fuel rods and associated flow channels by means of an equivalent single channel. Thermal and hydraulic behavior in the channel is predicted on a local basis at various axial positions during the blowdown, core heat-up, and emergency core cooling injection phases of an accident. Blowdown pressure and flow information are used as input data for ECCSA-I. The development and content of the program is described, including major assumptions, mathematical models, and computer equation. A source deck and sample problem for the CDC-6400 computer will be available through the ANL Code Center. Typical results are presented for analyses of BWR, PWR, and LOFT loss-of-coolant accidents. ( auth )

• Corporate Authors:

  Battelle Memorial Institute

  505 King Avenue
  Columbus, OH  United States  43201
• Authors:
  • Iyer, Jay S
• Publication Date: 1968-3-1

Media Info

• Pagination: 79 p.

Subject/Index Terms

• TRT Terms: Crashes; Nuclear reactor coolants; Nuclear reactor cores; Nuclear reactors
• Old TRIS Terms: Nuclear reactor accidents
• Subject Areas: Marine Transportation; Safety and Human Factors;

Filing Info

• Accession Number: 00001623
• Record Type: Publication
• Source Agency: National Technical Information Service
• Contract Numbers: W7405eng92
• Files: TRIS
• Created Date: Oct 30 1973 12:00AM