LCTL TEST OF HNPF MODERATOR CANS
Technical Report
·
OSTI ID:4098526
In a test of Hallam Nuclear Power Facility stainlesssteel moderator cans, a cluster of seven of these was heated isothermally to 1010 deg F in sodium. Subsequently the cans were thermally shocked to produce a maximum temperature difference of 154 deg F between the centers and edges of the can flats. Test results indicated that sensitization and depassivation of can surfaces is likely to take place during reactor operation. (J.R.D.)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- NSA Number:
- NSA-15-008347
- OSTI ID:
- 4098526
- Report Number(s):
- NAA-SR-Memo-5442
- Country of Publication:
- United States
- Language:
- English
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