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Title: 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 » and supported on said vessel wall between said heat exchanger means and said inlet plenum means. (AEC)« less

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4704362
Patent Number(s):
3080308
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-17-019665
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}
}