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Title: ANALYSIS OF SNAP REACTOR COOLANT CROSS-FLOW IN THE SNAP-2 REACTOR EXCLUDING THE PERIPHERAL $sub 4$UNFED$sub 4$ CHANNEL

Technical Report ·
DOI:https://doi.org/10.2172/4005294· OSTI ID:4005294

The deviation from the expected coolant flow distribution within the SNAP 2 reactor is due to the filling and draining of the unfed'' peripheral flow channels. An analysis of the cross-flow in a simulated SNAP 2 model omitting the unfed'' peripheral channels was made. The results of this investigation are presented herein. (auth)

Research Organization:
Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
DOE Contract Number:
AT(11-1)-GEN-8
NSA Number:
NSA-18-021673
OSTI ID:
4005294
Report Number(s):
NAA-SR-Memo-9576
Resource Relation:
Other Information: Thermo-Physics Technical Note No. 30. Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English