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Title: BOILER-SUPERHEATED REACTOR

Abstract

A nuclear power reactor of the type in which a liquid moderator-coolant is transformed by nuclear heating into a vapor that may be used to drive a turbo- generator is described. The core of this reactor comprises a plurality of freely suspended tubular fuel elements, called fuel element trains, within which nonboiling pressurized liquid moderator-coolant is preheated and sprayed through orifices in the walls of the trains against the outer walls thereof to be converted into vapor. Passage of the vapor ovcr other unwetted portions of the outside of the fuel elements causes the steam to be superheated. The moderatorcoolant within the fuel elements remains in the liqUid state, and that between the fuel elements remains substantiaily in the vapor state. A unique liquid neutron-absorber control system is used. Advantages expected from the reactor design include reduced fuel element failure, increased stability of operation, direct response to power demand, and circulation of a minimum amount of liquid moderatorcoolant. (A.G.W.)

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4128821
Patent Number(s):
US 2982712
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-18-006505
NSA Number:
NSA-18-006505
Resource Type:
Patent
Resource Relation:
Patent File Date: 1958 Aug 01; Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ABSORPTION; BOILING; CONFIGURATION; CONTROL ELEMENTS; COOLANT LOOPS; COOLANTS; EFFICIENCY; ELECTRICITY; EVAPORATION; FAILURES; FLUID FLOW; FUEL ELEMENTS; GAS COOLANT; GAS FLOW; GENERATORS; HEAT TRANSFER; HEATING; HIGH TEMPERATURE; LIQUIDS; MODERATORS; NEUTRON FLUX; NEUTRONS; PATENT; PLANNING; POWER PLANTS; PRESSURE; PRODUCTION; REACTIVITY; REACTOR CORE; REACTOR SAFETY; STABILITY; STEAM; SUPERHEATING; SURFACES; TRANSIENTS; TUBES; TURBINES; VAPORS; WATER COOLANT; ZONES

Citation Formats

Heckman, T.P.. BOILER-SUPERHEATED REACTOR. United States: N. p., 1961. Web.
Heckman, T.P.. BOILER-SUPERHEATED REACTOR. United States.
Heckman, T.P.. Mon . "BOILER-SUPERHEATED REACTOR". United States. doi:.
@article{osti_4128821,
title = {BOILER-SUPERHEATED REACTOR},
author = {Heckman, T.P.},
abstractNote = {A nuclear power reactor of the type in which a liquid moderator-coolant is transformed by nuclear heating into a vapor that may be used to drive a turbo- generator is described. The core of this reactor comprises a plurality of freely suspended tubular fuel elements, called fuel element trains, within which nonboiling pressurized liquid moderator-coolant is preheated and sprayed through orifices in the walls of the trains against the outer walls thereof to be converted into vapor. Passage of the vapor ovcr other unwetted portions of the outside of the fuel elements causes the steam to be superheated. The moderatorcoolant within the fuel elements remains in the liqUid state, and that between the fuel elements remains substantiaily in the vapor state. A unique liquid neutron-absorber control system is used. Advantages expected from the reactor design include reduced fuel element failure, increased stability of operation, direct response to power demand, and circulation of a minimum amount of liquid moderatorcoolant. (A.G.W.)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 01 00:00:00 EDT 1961},
month = {Mon May 01 00:00:00 EDT 1961}
}