Nuclear reactor safety device
Abstract
A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 6977469
- Application Number:
- ON: DE84011043
- Assignee:
- Dept. of Energy
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; CONTROL ROD DRIVES; CONTROL ELEMENTS; SCRAM; TRANSIENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWNS; 220400* - Nuclear Reactor Technology- Control Systems; 210500 - Power Reactors, Breeding
Citation Formats
Hutter, E. Nuclear reactor safety device. United States: N. p., 1983.
Web.
Hutter, E. Nuclear reactor safety device. United States.
Hutter, E. Mon .
"Nuclear reactor safety device". United States.
@article{osti_6977469,
title = {Nuclear reactor safety device},
author = {Hutter, E},
abstractNote = {A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {8}
}