Removal of Molten Sodium from Reactor Coolant Systems
Journal Article
·
· Industrial and Engineering Chemistry
A method for the removal of molten sodium from oxygen-free inaccessible locations in reactor coolant systems by flotation with HB-40 (a liquid hydrogenated terphenyl) is described. Butyl alcohol, under nitrogen pressure, is used to remove small amounts of sodium adhering to the stainless steel surface. (C.J.G.)
- Research Organization:
- Atomics International Div., North American Aviation Inc. Canoga Park, Calif.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-14-011277
- OSTI ID:
- 4200752
- Journal Information:
- Industrial and Engineering Chemistry, Journal Name: Industrial and Engineering Chemistry Journal Issue: 3 Vol. 52; ISSN 0019-7866
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Evaluation of molten lead mixing in sodium coolant by diffusion for application to PAHR. [LMFBR]
AN IN-PILE STUDY OF ORGANICS AS NUCLEAR REACTOR COOLANTS
METHOD FOR REMOVING SODIUM OXIDE FROM LIQUID SODIUM
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5951430
AN IN-PILE STUDY OF ORGANICS AS NUCLEAR REACTOR COOLANTS
Journal Article
·
Wed Dec 31 23:00:00 EST 1958
· Chem. Eng. Progr.
·
OSTI ID:4208159
METHOD FOR REMOVING SODIUM OXIDE FROM LIQUID SODIUM
Patent
·
Sat Nov 30 23:00:00 EST 1957
·
OSTI ID:4329503