Published September 1980
| Version v1
Journal article
Comparison of experimental and analytic simulation of reactor structural response to a hypothetical core disruptive accident
Creators
- 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 12588318
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; DEFORMATION; DESIGN BASIS ACCIDENTS; REACTOR CORE DISRUPTION; RESPONSE FUNCTIONS; SCALE DIMENSION; SIMULATION
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUNCTIONS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS