IL45831A - Process of enchancing fusion energy - Google Patents

Process of enchancing fusion energy

Info

Publication number
IL45831A
IL45831A IL45831A IL4583174A IL45831A IL 45831 A IL45831 A IL 45831A IL 45831 A IL45831 A IL 45831A IL 4583174 A IL4583174 A IL 4583174A IL 45831 A IL45831 A IL 45831A
Authority
IL
Israel
Prior art keywords
fusion
area
nuclei
chamber
burn
Prior art date
Application number
IL45831A
Other versions
IL45831A0 (en
Original Assignee
Texas Gas Transmission Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Texas Gas Transmission Corp filed Critical Texas Gas Transmission Corp
Publication of IL45831A0 publication Critical patent/IL45831A0/en
Publication of IL45831A publication Critical patent/IL45831A/en

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/03Thermonuclear fusion reactors with inertial plasma confinement
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

Description

45831/2 ΠΛ'ΤΟ n*AT3K maan1? - nn Process of enhancing fusion energy TEXAS GAS TRAN3 ISSI0N CORPORATIOH This invention relates to the Enhancement of Fusion Reaction and more particularly to increase s of energy of fusion by the presence of a nuclei which upon absorption of a neutron, will disintegrate, releasing energy.
Much work is presently being done on the achievement of ignition and burn of fusion fuel such as, for example, deuterium-tritium in pellet form.
While there are a number of different approaches to this problem, one of them includes the utilization of a source of energy from a laser and particular pellet configurations which will make it possible to achieve U.S. ignition and burn in a reaction chamber./ Patents which illustrate generally the apparatus which can be used in this type of system are: Whittlesey 3,378,446 - April 16, 1968 Daiber 3,489,645 - Jan. 13, 1970 Hedstrom 3,762,992 - Oct.. 2, 1973 It has been proposed to utilize boron in a process and an apparatus provided for the disso¬ ciation of H2 A general conception of a fusion reactor consists of two principJ^ arts. A central reaction chamber in which nuclear fusion fuel (hydrogen isotopes or other nuclear isotopes that undergo fusion) is caused to fuse. An example is deuterium and tritium fuse to produce helium and neutrons. The neutrons produced have a high energy and escape the fusion reaction chamber, and can be utilized for neutron reactions in a blanket chamber, the second part, which is formed by an annulus between the fusion chamber and the outer wall.
The present invention relates to the use of neutrons which, after a fusion burn, may penetrate the reaction chamber wall in the range of 14 MEV neutrons originally derived from the deuterium-tritium reactions. These neutrons are very difficult to confine, and accordingly, if the energy thereof can be successfully utilized in a radiolysis process, there are distinct advantages to be gained.
The reactions that appear to be most favorable for the subject invention can be described in the following formulation: 10 7 B (n,o Li Q (Energy) = 2.5 MEV Li6 (n, t) He4 Q = 4.8 MEV 10 In the first reaction, B , which is present in natural boron, reacts with a neutron and releases the energy shown above in the form of alpha radiation . . .6 and Li-7 recoil. The second reaction, Li , present in natural lithium, reacts with a neutron to release the energy, 4.8 MEV in the form of tritium and He-4 recoil. The Li , used in the latter reaction, can be utilized, either separated, or enriched, or as present in natural lithium.
It is therefore an object of the present invention to provide an apparatus and a process for utilizing the neutrons resulting from a fusion reaction to increase the energy by exposing them to selected nuclei.
It is a further object to provide a system which will greatly increase the yield of energy by exposure of neutrons to nuclei which dissociate exothermically upon capture of neutrons.
Other objects and features of the invention will be apparent in the following description and claims in which the principles of operation and use of the invention are set forth in the best mode presently contemplated for the practice of the invention.
A drawing accompanies the disclosure and may be described as a schematic view of an apparatus for accomplishing the process.
It should be appreciated that the invention relates to the reduction of induced radioactivity in a fusion burn by the absorption of neutrons in a medium such as boron or lithium which react exothermically to produce heat, but which produce no radioactive debris. Thus, the resulting radioactivity is reduced, the confining apparatus is less subject to deterioration and the entire process is easier to deal with.
In FIGURE 1, there is illustrated a laser driven fusion reactor where a laser source 10 directs pulse to a pellet 12 at the center of a reaction chamber 14 surrounded by a wall 16. A pellet source 18 is shown for introduction of the fusion fuel in any suitable manner. Surrounding the wall is a secondary chamber 20 formed by an outer wall 22 of a metal such as titanium or other highly heat resistant material. It is in this chamber that the fuel materials for generating additional energy will be placed.
Using this general arrangement, there are a number of ways in which boron and lithium containing materials may be introduced. There are two ingredients required for this process invention. The first is pure boron or lithium bearing compounds or metallic alloys. The second is a heat transport medium for extracting the thermal energy derived through the nuclear reaction. A third material which may be desirable is a neutron moderator to reduce the energy of the neutron flux and thus improve the neutron reaction efficiency of the composite.
The selection of absorber depends upon four considerations: (1) the amount of energy released per neutron absorbed; (2) the residual radioactivity after exposure ; (3) the neutron cross-section which is indicative of the neutron "stopping power"; and (4) the absorption of radiation in the surrounding medium.
When a neutron is absorbed in any particular isotope, the product isotopes emit energy in various forms (alpha-radiation, beta-radiation, gamma-radiation, neutrons, etc.). Eventually, the radiation energy is absorbed in the medium and is converted to thermal energy. The first consideration evaluates the efficiency of this energy transformation. The second consideration evaluates the rate of the energy transfer dictated by the characteristic decay period of the products.
If the period is long, the radiation may prove a problem from the standpoint of radiological safety.
The third consideration is the neutron cross-section for the reaction. This determines the mass or thickness of material required and, therefore, the dilution of the energy release. The fourth consideration has to do with the amount of absorbing medium required to absorb the product isotope radiation. For example, high energy gamma-radiation would require a large mass to absorb the radiant energy. Consequently, the energy density would be low.
The isotope preferred for this application should have a high energy return per neutron absorbed, no penetrating radiation of a long decay period produced and a high nuclear cross-section. Boron and lithium meet these objectives well.
Other materials employed in the fusion reactor annulus formed between the reaction chamber 20 and the outer wall 22 are a neutron moderator material which slows the neutrons down for efficient reaction with boron or lithium and a coolant that does not parasitically capture neutrons, yet has a high temperature capability and is compatible with construction materials. The boron or lithium may also be dispersed in a solid metal, graphite or ceramic matrix to provide uniform heat extraction. The matrix materials must also have a low cross-section to neutrons to avoid competition with the principle neutron reaction. Materials suggested for the various applications are tabulated in Table I .
TABLE I MATERIAL SELECTIONS Dispersion Absorbers Coolants Medium Moderator Boron Water Lithium Gases Graphite Fluoride Beryllium Boron Carbide CO, Lithium Hydride He Beryllium oxide Water Aqueous solution Metal Hydrides Liquid Metals Dispersion Liquid Lithium of Solids Lead Solids Bismuth Aluminum Sodium Graphite NaK Beryllium oxide Fused Salts Alumina These additive materials which dissociate exothermically can be introduced in many ways. Solid structures can be built to hold solid boron or lithium containing rods or plates. Provisions for periodic removal must be made to replace radiation damaged and depleted fuel elements. This can be accomplished by providing a removable wall section in wall 22. Part of the structure may include a neutron moderator to increase the effective exposure. Any of a number of known coolants can be circulated through the structure to transport thermal energy to external applications (such as a steam generator for a turbine electric plant, a chemical operation, or others) . The structure can be simplified by introducing the fuel in a fluid form (aqueous solution, fused salt, liquid metal, gas dispersion, fluidized bed of solids, and spherical pebbles) . These forms permit continuous or intermittent replacement of fuel without interrupting the reactor operation and simplifies fuel handling. A further simplification is to combine the moderator and coolant into a fluid. Examples of this are water coolant, liquid lithium, and graphite-gas dispersions. A further simplification would be to combine all three functions into one fluid, namely, a heat exchange fluid which carries, for example, boron and also a moderator, which is circulated through the annulus. The thermal energy extraction and fuel replacement operations are part of the circuit external of the reactor. The following published sources are pertinent in connection with this technology: (1) C. R. Tipton, Jr., "Reactor Handbook", Interscience Publishers Inc., (1960). (2) S. Glasstone, "Principles of Nuclear Reactor Engineering", D. Van Nostrand Co., Inc., (1955).
With reference to the drawing, the annulus chamber 20 has openings 24, 26 and 30 which serve as inlets or outlets with suitable closures.
For example, a steam or mist of H20 in which boron is dissolved may be introduced through openings 24 and 26 prior to a burn with an outlet 30 to permit proper flow. If desired, a fluid carrying a particulate of boron or lithium may be introduced under pressure through any of the openings. A fluidized quantity of a particulate could be introduced at 30 to maintain a desired amount of boron, for example, in the chamber 20 surrounding the reaction chamber.
With the use of a fusion reactor as a source of neutrons to expose boron or lithium, there are a number of advantages. The unit can be operated steadily with a non-destructive burn and the additive can be supplied continuously, if desired, to obtain the highest efficiency of energy output. There will result a high neutron yield per unit of energy and the introduction of a material such as boron will not interfere with the operation of the reactor. As has been pointed out, there is no fission product radioactivity involved in the system and the handling of the material additions is relatively simple.

Claims (13)

CLAIMS :
1. A process of enhancing fusion burn energy which comp (a) establishing a fusion burn chamber, (b) depositing a quantity of fusion fuel within said chamber, (c) illuminating the fuel with a pulsed laser beam to create a fusion burn, (d) introducing boron nuclei which dissociate exothermically upon capture of neutrons into an area adjacent said chamber to be present during said fusion burn, and (e) removing heat resulting from said burn and the dissociation of said boron nuclei.
2. A process as defined in Claim 1 in which said nuclei are introduced into said area as a boron compound in solution in a liquid.
3. A process as defined in claim 2 in which said liquid is introduced into said area as a finely divided mist.
4. A process as defined in claim 1 in which said nuclei introduced into said area as a finely divided particulate carried by a fluid medium.
5. A process as defined in claim 1 in which said are nuclei jtfi introduced into said area as a finely divided particulate carried by a gaseous medium.
6. A process as defined in claim 1 in which said nuclei ¾ξΘ introduced into said area as a finely divided particulate carried and suspended in said chamber during a fusion burn by a moving gaseous medium.
7. A process of enhancing fusion burn energy which comprises introducing into a fusion burn area a compound of a material including nuclei of an element which dissociates exothermically upon capture of neutrons.
8. A process as defined in claim 7 in which said compound is introduced into said area as a particulate carried by a fluid medium.
9. A process as defined in claim 7 in which said element is selected from a group consisting of boron 10 and lithium 6. «
10. 1 A process as defined in claim 1 in which said 2 heat is removed by passing a coolant containing a 3 moderator around said area.
11. 1 A process of enhancing fusion burn energy 2 which comprises: 3 (a) establishing a fusion burn chamber, 4 (b) depositing a quantity of fusion fuel within 5 said chamber, 6 (c) illuminating the fuel with a pulsed laser 7 beam to create a fusion burn, 8 (d) introducing φ. nuclei which dissociate^ 9 exothermically upon capture of neutrons into an area 0 adjacent said chamber to be present during said fusion burn 1 by including said nuclei in a fluid, and passing said 2 fluid around said chamber.
12. 1 A process as defined in claim 11 in which a 2 moderator material is included in said fluid.
13. 1 A process as defined in claim 11 in which 2 said moderator comprises a material selected from 3 H20, liquid lithium, and graphite gas dispersions, 4 beryllium, beryllium oxide, and metal hydrides.
IL45831A 1973-11-09 1974-10-11 Process of enchancing fusion energy IL45831A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US41437173A 1973-11-09 1973-11-09

Publications (2)

Publication Number Publication Date
IL45831A0 IL45831A0 (en) 1974-12-31
IL45831A true IL45831A (en) 1977-04-29

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Application Number Title Priority Date Filing Date
IL45831A IL45831A (en) 1973-11-09 1974-10-11 Process of enchancing fusion energy

Country Status (16)

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JP (1) JPS5078794A (en)
BE (1) BE821666A (en)
BR (1) BR7408811A (en)
CA (1) CA1024270A (en)
CH (1) CH587537A5 (en)
DE (1) DE2451605A1 (en)
DK (1) DK142338B (en)
ES (1) ES431774A1 (en)
FR (1) FR2251077B1 (en)
GB (1) GB1493358A (en)
IL (1) IL45831A (en)
IT (1) IT1025549B (en)
NL (1) NL7413914A (en)
NO (1) NO744025L (en)
SE (1) SE399606B (en)
ZA (1) ZA746492B (en)

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* Cited by examiner, † Cited by third party
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WO2005099321A1 (en) * 2004-04-08 2005-10-20 Silin Vjacheslaw Volodymyrovic Method and device (variants) for producing high heat energy
WO2009079068A2 (en) * 2007-10-04 2009-06-25 Lawrence Livermore National Security, Llc Triso fuel for high burn-up nuclear engine

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3624239A (en) * 1970-02-11 1971-11-30 Atomic Energy Commission Pulsed laser-ignited thermonuclear reactor
US3762992A (en) * 1972-03-01 1973-10-02 Atomic Energy Commission Laser driven fusion reactor

Also Published As

Publication number Publication date
CA1024270A (en) 1978-01-10
ZA746492B (en) 1976-06-30
ES431774A1 (en) 1977-05-16
GB1493358A (en) 1977-11-30
FR2251077A1 (en) 1975-06-06
IL45831A0 (en) 1974-12-31
DK142338B (en) 1980-10-13
CH587537A5 (en) 1977-05-13
SE7414050L (en) 1975-05-12
AU7431074A (en) 1976-04-15
NO744025L (en) 1975-06-02
BE821666A (en) 1975-04-30
DK142338C (en) 1981-03-09
DE2451605A1 (en) 1975-05-28
SE399606B (en) 1978-02-20
DK583574A (en) 1975-06-30
JPS5078794A (en) 1975-06-26
IT1025549B (en) 1978-08-30
NL7413914A (en) 1975-05-13
FR2251077B1 (en) 1978-06-16
BR7408811A (en) 1975-11-18

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