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Title: Fuel pin

Abstract

A fuel pin for a liquid metal nuclear reactor is provided. The fuel pin includes a generally cylindrical cladding member with metallic fuel material disposed therein. At least a portion of the fuel material extends radially outwardly to the inner diameter of the cladding member to promote efficient transfer of heat to the reactor coolant system. The fuel material defines at least one void space therein to facilitate swelling of the fuel material during fission.

Inventors:
; ; ;
Issue Date:
Research Org.:
Westinghouse Hanford Co., Richland, WA (USA)
OSTI Identifier:
6125940
Patent Number(s):
-US-A7124709
Application Number:
ON: DE89010953
Assignee:
Dept. of Energy TIC; EDB-89-069761
DOE Contract Number:  
AC06-76FF02170
Resource Type:
Patent
Resource Relation:
Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; FUEL PINS; DESIGN; HEAT TRANSFER; INVENTIONS; SWELLING; VOIDS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; 210500* - Power Reactors, Breeding

Citation Formats

Christiansen, D.W., Karnesky, R.A., Leggett, R.D., and Baker, R.B. Fuel pin. United States: N. p., 1987. Web.
Christiansen, D.W., Karnesky, R.A., Leggett, R.D., & Baker, R.B. Fuel pin. United States.
Christiansen, D.W., Karnesky, R.A., Leggett, R.D., and Baker, R.B. Tue . "Fuel pin". United States.
@article{osti_6125940,
title = {Fuel pin},
author = {Christiansen, D.W. and Karnesky, R.A. and Leggett, R.D. and Baker, R.B.},
abstractNote = {A fuel pin for a liquid metal nuclear reactor is provided. The fuel pin includes a generally cylindrical cladding member with metallic fuel material disposed therein. At least a portion of the fuel material extends radially outwardly to the inner diameter of the cladding member to promote efficient transfer of heat to the reactor coolant system. The fuel material defines at least one void space therein to facilitate swelling of the fuel material during fission.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {11}
}