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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.:
US Dept. of Energy (USDOE), Washington, DC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1176607
Patent Number(s):
H000689
Application Number:
07/124709
Assignee:
The United States of America as represented by the United States Department of Energy (Washington, DC)
Resource Type:
Patent
Resource Relation:
Patent File Date: 1987 Nov 24
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; statutory invention registration

Citation Formats

Christiansen, David W., Karnesky, Richard A., Leggett, Robert D., and Baker, Ronald B. Fuel pin. United States: N. p., 1989. Web.
Christiansen, David W., Karnesky, Richard A., Leggett, Robert D., & Baker, Ronald B. Fuel pin. United States.
Christiansen, David W., Karnesky, Richard A., Leggett, Robert D., and Baker, Ronald B. Tue . "Fuel pin". United States. https://www.osti.gov/servlets/purl/1176607.
@article{osti_1176607,
title = {Fuel pin},
author = {Christiansen, David W. and Karnesky, Richard A. and Leggett, Robert D. and Baker, Ronald 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 = {1989},
month = {10}
}