CALANDRIA TYPE SODIUM GRAPHITE REACTOR

Patent · Tue Feb 11 04:00:00 EST 1964

OSTI ID:4027625

Peterson, R M; Mahlmeister, J E; Vaughn, N E; Sanders, W J; Williams, A C

A sodium graphite power reactor in which the unclad graphite moderator and fuel elements are contained within a core tank is described. The core tank is submersed in sodium within the reactor vessel. Extending longitudinally through the core thnk are process tubes with fuel elements positioned therein. A bellows sealing means allows axial expansion and construction of the tubes. Within the core tank, a leakage plenum is located below the graphite, and above the graphite is a gas space. A vent line regulates the gas pressure in the space, and another line removes sodium from the plenum. The sodium coolant flows from the lower reactor vessel through the annular space between the fuel elements and process tubes and out into the reactor vessel space above the core tank. From there, the heated coolant is drawn off through an outlet line and sent to the heat exchange. (AEC)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-019400
• Assignee: U.S. Atomic Energy Commission
• Patent Number(s): US 3121052
• OSTI ID: 4027625
• Country of Publication: United States
• Language: English

Related Subjects

COOLANT LOOPS
EXPANSION
FUEL ELEMENTS
GASES
GRAPHITE MODERATOR
HEAT EXCHANGERS
LEAKS
LIQUID FLOW
LIQUID METAL COOLANT
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
SEALS
SODIUM
TUBES
VESSELS