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Title: HEAVY WATER MODERATED POWER REACTORS. Progress Report, November 1962

Technical Report ·
OSTI ID:4710177

The Heavy Water Components Test Reactor (HWCTR) was operated intermittently at a maximum power of about 35 Mw for irradiation of test fuel assemblies of various types. Near the end of November, a cladding failure occurred in an assembly of two Zircaloy-clad tubes of unalloyed uranium. The reactor was scrammed without incident, and the activity in the primary coolant system decreased from 0.026 microcurie/ml 18 hours after the scram to 0.0037 microcurie/ml 5 days after the scram. Hardness measurements at elevated temperature indicate that the addition of about 200 ppm of silicon to U--350 ppm Fe--900 ppm Al might increase the resistance of the latter to swelling during irradiation. Resonance integrals and self-shielding factors were measured for a variety of foil materials that are frequentiy used in experimental lattice studies. Experimental data were obtained on heat transfer burnout for forced fiow of subcooled water in annuli at pressures of 500 to 1000 psi. (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-17-011979
OSTI ID:
4710177
Report Number(s):
DP-805
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English