Published September 1980 | Version v1
Journal article

Comparison of experimental and analytic simulation of reactor structural response to a hypothetical core disruptive accident

  • 1. Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.
  • 2. General Electric Co., Sunnyvale, CA (USA). Fast Breeder Reactor Dept.

Description

A series of scale model tests assessing the ability of the Clinch River Breeder Reactor to withstand the loads resulting from a hypothetical core disruptive accident have been performed. Supporting analytic simulation of these tests using the REXCO-HEP code were also performed. Comparison of the analytic and experimental results are described in this paper. As a general conclusion, the analytically predicted loads on the coolant boundary and resulting structural deformations were greater than the corresponding experimental loads and deformations. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
60
Journal Issue
2
Series
Nucl. Eng. Des.
Journal Page Range
257-266
ISSN
0029-5493