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Title: FUSED REACTOR FUELS

Abstract

This invention relates to a nuciear reactor fuel composition comprising (1) from about 0.01 to about 50 wt.% based on the total weight of said composition of at least one element selected from the class consisting of uranium, thorium, and plutonium, wherein said eiement is present in the form of at least one component selected from the class consisting of oxides, halides, and salts of oxygenated anions, with components comprising (2) at least one member selected from the class consisting of (a) sulfur, wherein the sulfur is in the form of at least one entity selected irom the class consisting of oxides of sulfur, metal sulfates, metal sulfites, metal halosulfonates, and acids of sulfur, (b) halogen, wherein said halogen is in the form of at least one compound selected from the class of metal halides, metal halosulfonates, and metal halophosphates, (c) phosphorus, wherein said phosphorus is in the form of at least one constituent selected from the class consisting of oxides of phosphorus, metal phosphates, metal phosphites, and metal halophosphates, (d) at least one oxide of a member selected from the class consisting of a metal and a metalloid wherein said oxide is free from an oxide of said elementmore » in (1); wherein the amount of at least one member selected from the class consisting of halogen and sulfur is at least about one at.% based on the amount of the sum of said sulfur, halogen, and phosphorus atom in said composition; and wherein the amount of said 2(a), 2(b) and 2(c) components in said composition which are free from said elements of uranium, thorium, arid plutonium, is at least about 60 wt.% based on the combined weight of the components of said composition which are free from said elements of uranium, thorium, and plutonium. (AEC)« less

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4730167
Patent Number(s):
US 3063923
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-17-010007
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ENRICHMENT; FUSED SALT FUEL; HALIDES; MINERAL ACIDS; PHOSPHOROUS ACID; PLUTONIUM; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; PLUTONIUM PHOSPHATES; PLUTONIUM SULFATES; SALTS; SULFITES; SULFONIC ACIDS; THORIUM; THORIUM COMPOUNDS; THORIUM OXIDES; THORIUM PHOSPHATES; THORIUM SULFATES; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES; URANIUM PHOSPHATES; URANIUM SULFATES

Citation Formats

Mayer, S.W.. FUSED REACTOR FUELS. United States: N. p., 1962. Web.
Mayer, S.W.. FUSED REACTOR FUELS. United States.
Mayer, S.W.. 1962. "FUSED REACTOR FUELS". United States. doi:.
@article{osti_4730167,
title = {FUSED REACTOR FUELS},
author = {Mayer, S.W.},
abstractNote = {This invention relates to a nuciear reactor fuel composition comprising (1) from about 0.01 to about 50 wt.% based on the total weight of said composition of at least one element selected from the class consisting of uranium, thorium, and plutonium, wherein said eiement is present in the form of at least one component selected from the class consisting of oxides, halides, and salts of oxygenated anions, with components comprising (2) at least one member selected from the class consisting of (a) sulfur, wherein the sulfur is in the form of at least one entity selected irom the class consisting of oxides of sulfur, metal sulfates, metal sulfites, metal halosulfonates, and acids of sulfur, (b) halogen, wherein said halogen is in the form of at least one compound selected from the class of metal halides, metal halosulfonates, and metal halophosphates, (c) phosphorus, wherein said phosphorus is in the form of at least one constituent selected from the class consisting of oxides of phosphorus, metal phosphates, metal phosphites, and metal halophosphates, (d) at least one oxide of a member selected from the class consisting of a metal and a metalloid wherein said oxide is free from an oxide of said element in (1); wherein the amount of at least one member selected from the class consisting of halogen and sulfur is at least about one at.% based on the amount of the sum of said sulfur, halogen, and phosphorus atom in said composition; and wherein the amount of said 2(a), 2(b) and 2(c) components in said composition which are free from said elements of uranium, thorium, arid plutonium, is at least about 60 wt.% based on the combined weight of the components of said composition which are free from said elements of uranium, thorium, and plutonium. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1962,
month =
}
  • A process is given for recovering plutonium from a neutron-irradiated uranium mass (oxide or alloy) by dissolving the mass in an about equimolar alkali metalaluminum double chloride, adding aluminum metal to the mixture obtained at a temperature of between 260 and 860 deg C, and separating a uranium-containing metal phase and a plutonium-chloride- and fission-product chloridecontaining salt phase. Dissolution can be expedited by passing carbon tetrachloride vapors through the double salt. Separation without reduction of plutonium from neutron- bombarded uranium and that of cerium from uranium are also discussed.
  • A crushed hydrocarbon-bearing material containing hydrocarbon and foreign mineral constituents is dispersed in fused alkali metal caustic to remove the sulfur content and release the foreign mineral matter from the hydrocarbon material for recovery and/or upgrading of the hydrocarbon content. The process permits recovery of 80-95% of the available kerogen or other hydrocarbon in a mineral matrix such as oil shale rock and conditions a solid fossil fuel such as coal, as well as the kerogen or other hydrocarbon released from the mineral matrix, for removal of substantially all remaining ash and other foreign mineral matter by subsequent washing ofmore » the hydrocarbon product in an aqueous solution of acid.« less
  • The present invention relates to the field of fused-salt nuclear reactors and its object is the extraction of the gases produced in the course of operation of these reactors. The process according to the invention consists in placing into position a piece of material permeable for gases and impermeable for the used fused salts, for instance, a piece of graphite, in such a way that part of the surface of this piece is in contact with the circuit of the radioactive salts and another part connected to a gas suction device. The piece could also be scavenged in its massmore » by a flow of inert gas. Application is contemplated in reactors using a mixture of lithium fluoride, beryllium fluoride, and uranium and/or thorium fluoride. 10 claims, 2 drawing figures.« less