HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960
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)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, Del.
- DOE Contract Number:
- AT(07-2)-1
- NSA Number:
- NSA-14-025050
- OSTI ID:
- 4149609
- Report Number(s):
- DP-505
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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