SIMPLIFIED SODIUM GRAPHITE REACTOR SYSTEM
Abstract
This patent relates to a nuclear power reactor comprising a reactor vessel, shielding means positioned at the top of said vessel, means sealing said reactor vessel to said shielding means, said vessel containing a quantity of sodium, a core tank, unclad graphite moderator disposed in said tank, means including a plurality of process tubes traversing said tank for isolating said graphite from said sodium, fuel elements positioned in said process tubes, said core tank being supported in spaced relation to the walls and bottom of said reactor vessel and below the level of said sodium, neutron shielding means positioned adjacent said core tank between said core tank and the walls of said vessel, said neutron shielding means defining an annuiar volume adjacent the inside wall of said reactor vessel, inlet plenum means below said core tank for providing a passage between said annular volume and said process tubes, heat exchanger means removably supported from the first-named shielding means and positioned in said annular volume, and means for circulating said sodium over said neutron shielding means down through said heat exchanger, across said inlet plenum and upward through said process tubes, said last-named means including electromagnetic pumps located outside said vesselmore »
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4704362
- Patent Number(s):
- 3080308
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- NSA Number:
- NSA-17-019665
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; CONFIGURATION; ELECTROMAGNETIC PUMPS; FUEL ELEMENTS; GRAPHITE MODERATOR; HEAT EXCHANGERS; LIQUID FLOW; LIQUID METAL COOLANT; NEUTRONS; PATENT; POWER PLANTS; PRESSURE VESSELS; REACTORS; SHIELDING; SODIUM
Citation Formats
Dickinson, R W. SIMPLIFIED SODIUM GRAPHITE REACTOR SYSTEM. United States: N. p., 1963.
Web.
Dickinson, R W. SIMPLIFIED SODIUM GRAPHITE REACTOR SYSTEM. United States.
Dickinson, R W. Fri .
"SIMPLIFIED SODIUM GRAPHITE REACTOR SYSTEM". United States.
@article{osti_4704362,
title = {SIMPLIFIED SODIUM GRAPHITE REACTOR SYSTEM},
author = {Dickinson, R W},
abstractNote = {This patent relates to a nuclear power reactor comprising a reactor vessel, shielding means positioned at the top of said vessel, means sealing said reactor vessel to said shielding means, said vessel containing a quantity of sodium, a core tank, unclad graphite moderator disposed in said tank, means including a plurality of process tubes traversing said tank for isolating said graphite from said sodium, fuel elements positioned in said process tubes, said core tank being supported in spaced relation to the walls and bottom of said reactor vessel and below the level of said sodium, neutron shielding means positioned adjacent said core tank between said core tank and the walls of said vessel, said neutron shielding means defining an annuiar volume adjacent the inside wall of said reactor vessel, inlet plenum means below said core tank for providing a passage between said annular volume and said process tubes, heat exchanger means removably supported from the first-named shielding means and positioned in said annular volume, and means for circulating said sodium over said neutron shielding means down through said heat exchanger, across said inlet plenum and upward through said process tubes, said last-named means including electromagnetic pumps located outside said vessel and supported on said vessel wall between said heat exchanger means and said inlet plenum means. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {3}
}