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

Leslie D. Montgomery | Zendy

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

Author(s) -

Leslie D. Montgomery

Publication year - 1964

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4005294

Subject(s) - snap , coolant , flow (mathematics) , channel (broadcasting) , mechanics , peripheral , materials science , chemistry , physics , thermodynamics , engineering , electrical engineering , computer science , computer graphics (images) , operating system

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

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