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Title: HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960

Abstract

BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a maximum exposure of 950 Mwd/ton at a maximum uranium temperature of 40O deg C experienced less than 1.5% volume increase and 0.14% outer-cladding strain. Inspection of the swaged oxide tube that had failed during irradiation in a Savannah River reactor revealed that a 9-in.-long crack of as-yet-unknown origin had developed in the outer stainless-steel cladding of the tube. Transient calculations showed that boiling D/sub 2/O reactors that are fueled with uranium metal probably would not operate stably as presently designed, but that those fueled with uranium oxide operating at high fuel temperature probably would be stable. A computer code for the calculation of the lattice bucklings of D/sub 2/O-moderated reactors is described. A description is presented of the tandem-extrusion process that was developed for the fabrication of bonded joints of Zircaloy and stainless steel. (For preceding period see DP- 495.) (auth)

Authors:
;
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, Del.
OSTI Identifier:
4149609
Report Number(s):
DP-505
NSA Number:
NSA-14-025050
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; BOILING; BONDING; BUCKLING; COMPUTERS; DEFORMATION; EQUATIONS; EXTRUSION; FABRICATION; FUEL CANS; FUEL ELEMENTS; HEAVY WATER MODERATOR; HIGH TEMPERATURE; IN PILE LOOPS; INSPECTION; IRRADIATION; JOINTS; POWER PLANTS; PROGRAMMING; REACTORS; STABILITY; STAINLESS STEELS; TRANSIENTS; URANIUM; URANIUM OXIDES; ZIRCALOY

Citation Formats

Hood, R.R., and Isakoff, L. comps. HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960. United States: N. p., 1960. Web. doi:10.2172/4149609.
Hood, R.R., & Isakoff, L. comps. HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960. United States. doi:10.2172/4149609.
Hood, R.R., and Isakoff, L. comps. Fri . "HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960". United States. doi:10.2172/4149609. https://www.osti.gov/servlets/purl/4149609.
@article{osti_4149609,
title = {HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960},
author = {Hood, R.R. and Isakoff, L. comps.},
abstractNote = {BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a maximum exposure of 950 Mwd/ton at a maximum uranium temperature of 40O deg C experienced less than 1.5% volume increase and 0.14% outer-cladding strain. Inspection of the swaged oxide tube that had failed during irradiation in a Savannah River reactor revealed that a 9-in.-long crack of as-yet-unknown origin had developed in the outer stainless-steel cladding of the tube. Transient calculations showed that boiling D/sub 2/O reactors that are fueled with uranium metal probably would not operate stably as presently designed, but that those fueled with uranium oxide operating at high fuel temperature probably would be stable. A computer code for the calculation of the lattice bucklings of D/sub 2/O-moderated reactors is described. A description is presented of the tandem-extrusion process that was developed for the fabrication of bonded joints of Zircaloy and stainless steel. (For preceding period see DP- 495.) (auth)},
doi = {10.2172/4149609},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {7}
}

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