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Title: Irradiation of three T-111 clad uranium nitride fuel pins for 8070 hours at 990/sup 0/C (1815/sup 0/F)

Abstract

The design and successful operation of three tantalum alloy (Ta-8W-2Hf) clad uranium mononitride (UN) fuel pins irradiated for 8070 h at 990/sup 0/C (1815/sup 0/F) is described. Two pin diameters having measured burnups of 0.47 and 0.90 uranium atom percent were tested. No clad failures or swelling was detected; however, postirradiation clad samples tested failed with 1 percent strain. The fuel density decrease was 2 percent, and the fission gas release was less than 0.05 percent. Isotropic fuel swelling, which averaged about 0.5 percent, was less than fuel pin assembly clearances. Thus the clad was not strained. Thermocouples with a modified hot zone operated at average temperatures to 1100/sup 0/C (2012/sup 0/F) without failure. Factors that influence the ability to maintain uniform clad temperature as well as the results of the heat transfer calculations are discussed.

Authors:
; ; ;
Publication Date:
Research Org.:
National Aeronautics and Space Administration, Cleveland, OH (USA). Lewis Research Center
OSTI Identifier:
6861885
Alternate Identifier(s):
OSTI ID: 6861885; Legacy ID: TI84900933
Report Number(s):
N-73-31614; NASA-TM-X-2878
ON: TI84900933
Resource Type:
Technical Report
Resource Relation:
Other Information: Paper copy only, copy does not permit microfiche production
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL PINS; PERFORMANCE TESTING; FISSION PRODUCT RELEASE; FUEL CANS; IRRADIATION; PBR REACTOR; POST-IRRADIATION EXAMINATION; TANTALUM ALLOY-T111; URANIUM NITRIDES; VERY HIGH TEMPERATURE; ACTINIDE COMPOUNDS; ALLOYS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; NITRIDES; NITROGEN COMPOUNDS; PNICTIDES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TANTALUM ALLOYS; TANTALUM BASE ALLOYS; TESTING; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220300* -- Nuclear Reactor Technology-- Fuel Elements

Citation Formats

Slaby, J.G., Siegel, B.L., Gedeon, L., and Galbo, R.J. Irradiation of three T-111 clad uranium nitride fuel pins for 8070 hours at 990/sup 0/C (1815/sup 0/F). United States: N. p., 1973. Web. doi:10.2172/6861885.
Slaby, J.G., Siegel, B.L., Gedeon, L., & Galbo, R.J. Irradiation of three T-111 clad uranium nitride fuel pins for 8070 hours at 990/sup 0/C (1815/sup 0/F). United States. doi:10.2172/6861885.
Slaby, J.G., Siegel, B.L., Gedeon, L., and Galbo, R.J. Mon . "Irradiation of three T-111 clad uranium nitride fuel pins for 8070 hours at 990/sup 0/C (1815/sup 0/F)". United States. doi:10.2172/6861885. https://www.osti.gov/servlets/purl/6861885.
@article{osti_6861885,
title = {Irradiation of three T-111 clad uranium nitride fuel pins for 8070 hours at 990/sup 0/C (1815/sup 0/F)},
author = {Slaby, J.G. and Siegel, B.L. and Gedeon, L. and Galbo, R.J.},
abstractNote = {The design and successful operation of three tantalum alloy (Ta-8W-2Hf) clad uranium mononitride (UN) fuel pins irradiated for 8070 h at 990/sup 0/C (1815/sup 0/F) is described. Two pin diameters having measured burnups of 0.47 and 0.90 uranium atom percent were tested. No clad failures or swelling was detected; however, postirradiation clad samples tested failed with 1 percent strain. The fuel density decrease was 2 percent, and the fission gas release was less than 0.05 percent. Isotropic fuel swelling, which averaged about 0.5 percent, was less than fuel pin assembly clearances. Thus the clad was not strained. Thermocouples with a modified hot zone operated at average temperatures to 1100/sup 0/C (2012/sup 0/F) without failure. Factors that influence the ability to maintain uniform clad temperature as well as the results of the heat transfer calculations are discussed.},
doi = {10.2172/6861885},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Oct 01 00:00:00 EDT 1973},
month = {Mon Oct 01 00:00:00 EDT 1973}
}

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