STEAM-COOLED REACTOR FEASIBILITY STUDY STEAM WATER REACTOR (SWR). Volume I (Sections 1-6). Volume II (Sections 7 and 8). Final Report
The concept feasibility study is reported for a 200Mwe, 530-Mwh reactor. Steam at 2200 psi enters the reactor. Forty percent of the steam is heated in the peripheral region to 1050 deg F and flows to the turbine. Sixty percent is heated to 950 deg and vaporizes the water from the condensers. A low-pressure Al tank containing D/sub 2/O moderator is mounted horizontally in graphite. Horizontal Zircaloy pressure tubes for the stainless steel-clad UO/sub 2/ fuel rods and steam coolant go through the Al tank. Thermal insulation between pressure tubes and moderator must be provided. Energy costs and other characteristics of the reactor are given. It is concluded that the development work required to achieve this type of reactor is worthwhile, and a recommended development program is outlined. (T.R.H.)
- Research Organization:
- East Central Nuclear Group; Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
- NSA Number:
- NSA-13-005166
- OSTI ID:
- 4297987
- Report Number(s):
- NDA-2562-1(Vols.I and II)
- Country of Publication:
- United States
- Language:
- English
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BURNUP
CANNING
CONFIGURATION
COOLANT LOOPS
ECONOMICS
EVAPORATION
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GRAPHITE
HEAT TRANSFER
HEATING
HEAVY WATER MODERATOR
HIGH TEMPERATURE
MAINTENANCE
PERSONNEL
PIPES
PLANNING
POWER
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR CORE
REACTORS
RODS
STAINLESS STEELS
STEAM
SUPERHEATING
THERMAL INSULATION
TUBES
TURBINES
URANIUM DIOXIDE
WATER COOLANT
ZIRCALOY
ZONES