STEADY STATE HEAT TRANSFER ANALYSIS OF MOLTEN CORE-REACTOR VESSEL SYSTEM
This paper extends the steady state analysis of molten core and reactor vessel systems by L.S. Tong. Three other cases of interest were considered and found to be significant for the Maritime CNSG. Due to the design differences between the CNSG and land-based nuclear plants, there is a greater possibility that a postulated molten core could be contained within the reactor vessel with water only outside of the vessel.
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Corporate Authors:
North Holland Publishing Company
68-70 N.Z. Voorburgwal, Box 103
Amsterdam C, Netherlands -
Authors:
- Hagan, R C
- Reynolds, A
- Publication Date: 1977-10
Media Info
- Features: References;
- Pagination: p. 53-59
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Serial:
- Nuclear Engineering and Design
- Volume: 44
- Issue Number: 1
- Publisher: North Holland Publishing Company
Subject/Index Terms
- TRT Terms: Core samples; Heat transfer; Nuclear phenomena; Nuclear power; Nuclear power generation; Nuclear reactor cores; Nuclear reactors; Pressure vessels; Propulsion; Ships; Steel
- Old TRIS Terms: Consolidated nuclear steam generators; Cores; Maritime consolidated nuclear steam generator; Nuclear
- Subject Areas: Marine Transportation; Vehicles and Equipment;
Filing Info
- Accession Number: 00173120
- Record Type: Publication
- Source Agency: Engineering Index
- Files: TRIS
- Created Date: Apr 26 1978 12:00AM