SE544185C2 - A method for conversion of nuclear energy into thermal energy and a device for implementing the method - Google Patents
A method for conversion of nuclear energy into thermal energy and a device for implementing the methodInfo
- Publication number
- SE544185C2 SE544185C2 SE1851249A SE1851249A SE544185C2 SE 544185 C2 SE544185 C2 SE 544185C2 SE 1851249 A SE1851249 A SE 1851249A SE 1851249 A SE1851249 A SE 1851249A SE 544185 C2 SE544185 C2 SE 544185C2
- Authority
- SE
- Sweden
- Prior art keywords
- target
- energy
- unit
- flux
- nuclear
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
- G21G1/10—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by bombardment with electrically charged particles
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- H—ELECTRICITY
- H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
- H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
- H05H6/00—Targets for producing nuclear reactions
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- Y—GENERAL 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
- 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
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL 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
- 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
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Optics & Photonics (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Particle Accelerators (AREA)
Abstract
A method for converting nuclear energy into heat energy and a device for implementing the same, relating to the field of atomic energy. The invention is intended for energy generation using spent nuclear fuel, small actinides, and industrial radioactive and chemical waste. Energy generation is achieved by irradiating an actinide-based deeply subcritical target (4) using a beam of relativistic ions (Fig.1 and 2). The technical effect consists in increasing the efficiency of converting nuclear energy into heat energy, decreasing the cost of energy generation, expanding the list of energy technology applications, and enhancing the socioeconomic and environmental significance of converting nuclear energy into heat energy. The technical effect is achieved by introducing operations for accelerated ion beam scanning and for mixing the contents of a target, which are carried out by a scanning unit (3) and a mixing unit (5).
Description
A METHOD FOR CONVERSION OF NUCLEAR ENERGY INTO THERMALENERGY AND A DEVICE FOR |MPLEl\/IENTING THE The invention relates to the nuclear engineering domain and more specifically tothe method and devices for conversion of nuclear energy into thermal energy and isintended for production of thermal and electrical energy with recycling of spentnuclear fuel, small actinides, and industrial waste, including radioactive and chemicalwaste.
The Russian Federation Patent No. 2 238597 G21C1/30 dated 2003, “A methodfor conversion of nuclear energy into thermal energy”, suggests irradiating a deeplyunder-critical target made of heavy chemical elements (lead, bismuth, thorium, anddepleted uranium as well as their compositions) with a relativistic proton beam.Furthermore, the material of the target is used simultaneously both as fuel and as aheat carrier. The authors note the previously known fact that the higher the energy ofprimary particles is, the deeper nuclear fission is within the target. However, thistechnical solution has its disadvantages, including low efficiency of conversion ofnuclear energy into thermal energy, unacceptably high risks for producingradioactive materials, which may become available for nuclear terrorism, and theproblem of utilization of a neutron flux generated in the target material by primarilyaccelerated particles.
The Russian Federation Patent No. 2 413314 dated 2008, “A method and systemfor conversion of nuclear energy into thermal energy”, suggests a technical solutionconsisting in the acceleration of a beam of multicharge particles of uranium, thorium,bismuth, and lead isotopes up to energies causing origination of cascade nucleons ina deeply under-critical target, whereto such beam is directed. Furthermore, toimprove the intensity of secondary-particle flux and to ensure its subsequentrecycling, the target core is proposed to be partially or fully made of spent nuclearfuel. One of the disadvantages of this technical solution is low efficiency ofconversion of nuclear energy into thermal energy.
The method closest in its technical essence to the proposed method isconversion of nuclear energy into thermal energy described in the RussianFederation Patent No. 2 557616 lVlFlK G21C1/3O dated June 26, 2015.
The technical solution closest in its technical essence to the proposed devices isthe solution according to the first embodiment provided in the Russian FederationPatent No. 557616 MFIK G21C1/3O dated June 26, 2015, “A method for conversionof nuclear energy into thermal energy and a device for implementing the method(embodiments)”.
The disadvantage of the known method is low efficiency of the conversion ofnuclear energy into thermal energy as a result of non-uniform conversion of energywithin the target.
The disadvantage of the known device is a necessity to replace the target after ithas been used for a substantially long time: the replacement is required owing to thedecrease of the energy-generation efficiency on account of inevitable decrease ofthe fraction of fissionable material in the core.
The technical effect during the implementation of the proposed method isimproved efficiency of nuclear-energy conversion into thermal energy and adecrease of energy-generation cost.
The technical effect during the implementation of the proposed devices is adecrease of energy-generation cost and an increase of utilization factor of theinstalled capacity.
The technical result according to the method for conversion of nuclear energyinto thermal energy is achieved as follows:an ion beam is produced and accelerated;the material of deeply under-critical target is irradiated with the beam;the secondary-particle flux with two or more generations of nuclear fragments isobtained in the target;the intranuclear energy is released in the target having the size that ensures thetransfer of kinetic energy from the beam and from secondary-particle flux to thetarget; andthe loss of the material of the target is compensated;when irradiating the target, the ion beam is displaced along the surface of the targetin the spatial angle of the full absorption of the secondary-particle flux by the targetand the material of the target is simultaneously stirred.
The technical result is achieved as follows in the device for conversion of nuclearenergy into thermal energy: the first embodiment of the device comprisesan ion-flux accelerator and a flux transportation unit arranged in series and coaxially;a vertical deeply under-critical target of a liquid melt including heavy chemicalelements, wherein the target has a heat-, radiation-, and corrosion-resistant casewith an open upper end;a heat transformer unit; anda backup unit;wherein the device is additionally fitted with the electromagnetic flux orthogonalsweeping unit and a target-stirring unit, wherein the sweeping unit is coaxiallyarranged between the flux transportation unit and the target, and wherein the stirringunit is designed with a possibility of being in electromagnetic contact with itsmaterial.
The second embodiment of the device comprises an ion-flux accelerator and a flux transportation unit arranged in series and coaxially;a vertical deeply under-critical target, which includes heavy elements, wherein thetarget has a heat-, radiation-, and corrosion-resistant case with an open upper end; a heat transformer unit; and a backup unit connected thereto; wherein the target consists of bulk material, wherein the device is additionally fittedwith an electromagnetic flux orthogonal sweeping unit and a target-stirring unit, andwherein a hole is provided at the bottom of the target case; wherein the sweeping unit is coaxially arranged between the flux transportation unitand the target and the stirring unit is designed with a possibility of being inmechanical contact with the material of the target through both the holes in the caseof the target.
Furthermore, the bulk material of the target may be comprised of streamlined fuelelements. ln the proposed method for conversion of nuclear energy into thermal energy, thespatial angle of full absorption is defined as an angle, within which a primary flux ofaccelerated ions is displaced by a sweeping unit as to ensure that the secondary-particle flux created by the primary flux stays within the limits of the material of thetarget. Characteristics of the spatial angle, which limits the secondary-particle fluxoccurring in the material of the target, were determined experimentally when fixedlydirecting the primary flux towards the outer surface of the target. l\/lore specifically,the results were published in the following article: Barashenkov, V. 8.; Toneev V. D.,Interaction of high-energy particles and atomic nuclei with nuclei, Moscow,Atomizdat, 1972, Chapter 3 (B. C. BapaLueHKoB, BJJ. ToHeeB, < the target.
Mutual and simultaneous use of beam-sweeping operations and the stirring of thematerial of the target, as well as their implementation methods, are a mandatory anda sufficient condition for achieving the above-mentioned technical effect. Beamsweeping and continuous stirring of the material of the target is conducive toimproving the efficiency of the respective conversion of the target's nuclearcomposition under the beam and in the secondary-flux particle and to reducing theamplitude of fluctuatíon of concomitant energy generation with a proportionaldecrease of power density along with the loss compensation of the material of thetarget performed regularly (with the help of a backup unit). This ensures achieving asteady-state energy generation by the device and theoretically upholding thegeneration for an infinite amount of time.
The suggested method and devices are illustrated in Fig. 1-3 Fig. 1. is a general view of the first embodiment of the device that carries out theproposed method of conversion of nuclear energy into thermal energy.
Fig. 2 is a general view of the second embodiment of the device that carries outthe proposed method.
Fig. 3 is a sequence structure diagram for both device embodiments in a steady-state mode.
Reference numbers in the drawings - ion-beam accelerator - beam transportation unit - beam-sweeping unit - deeply under-critical full-absorption target- target-stirring unit - backup unit - heat transformer - closing device 9 -target makeup pipeline , 11, 12, 13 - heat-carrier pipelines14 _ open upper end of target - hole at the bottom of target GJNOÜUI-IÄLONA ln both embodiments of the device (Fig. 1 and Fig. 2), the outlet of the back-wavelinear accelerator 1 (BWLA, see Bogomolov, A. S., Bakirov T. S., Ion accelerators foruse in the industry, M. Dun, 2012, 87 pages [A. C. EoroMonoB, T. C. Eakvipoß,«|/|o|-|Hb|e yckopvnenvi nnfl vicnonbsoßanvm B vn-ipiycrpmvw, M. JIlyHa, 2012, 87 c.]) iscoaxially arranged with the inlet of the beam transportation unit 2. The outlet of thelatter is also connected with the inlet of the beam-sweeping unit 3. The vertically-oriented target 4 is coaxially arranged below the outlet of the beam-sweeping unit 3at a distance required for decreasing the negative impact of ionizing radiation comingfrom it onto the unit equipment.
The shape and dimensions of the target 4 are selected to ensure full absorptionof the swept primary beam and the secondary-particle flux in the material of thetarget for the default parameters of generation and recovery of heat formed therein.
The difference between the two embodiments is conditioned by their applicationand manifested in design and composition of the target 4, target-stirring unit 5,backup unit 6, and heat transformer 7.
The first embodiment (Fig. 1) comprises the target 4 with the material in the formof a liquid melt, which includes actinide elements and which is aimed at recyclingnuclear fuel waste, small actinides, other long-lived radionuclides, and otherindustrial radioactive and chemical waste, and generation of electric energy andthermal energy related to the target, in particular, for external consumers.
For homogenization of the liquid melt, which comprises heavy chemicalelements, the stirring unit 5 is employed, which has a possibility of being inelectromagnetic contact with the material of the target 4. Exemplary embodiments ofsuch a unit are devices presented, for example, in the Russian Federation PatentNo. 2 571971, Patent No. 2 567970, and Patent No. 2 453395.
The second embodiment of the device (Fig. 2) on the basis of using the target 4with a bulk material is mostly intended for application in the large-scale industrialheat- and power-generating industry, including the wide range of nuclear processsystems with balanced burn-out of spent nuclear fuel and small actinides, whoseincorporation into the target 4 is conducive to the increased energy generation of thedevice.
The bulk material of the target 4 is stirred by the respective unit, which isarranged in mechanical contact with the material of the target through the top 14 andbottom 15 holes in its case. The exemplary embodiment of such a unit may berepresented by a device described in the monography by Stolyarevsky, A. Ya.,Nuclear process systems based upon high-temperature reactors, Moscow:Energoatomizdat, 1988, p. 36 (AiLCfonsipeecki/uñ, Glplepiao-TexrionorwieckvieKomnnekcbi Ha ocHoBe Bbicokofemnepafypribix peaKTopoB», M.: âneproafoivivispiaf,1988 r., c.36). ln both embodiments of the device (Fig. 1 and Fig. 2), the backup unit 6 and theheat transformer unit 7 may contact mechanically with the material of the target 4.
Furthermore, the backup unit 6 is located above the target 4 to ensure the naturalfeeding of the material of the unit when the closing device 8 is in the open state inorder to compensate the loss of the material of the target 4. ln view of this, it shouldbe noted that the normal state of the closing device 8 is “closed”.
The aggregate state of the material in the backup unit corresponds to that of thematerial of the target for both embodiments of the device (a liquid melt in the firstembodiment and a bulk material in the second embodiment). The excessive heat is removed correspondingly from the target through the heat-carrier pipelines 10-13. lnthe first embodiment, heat is removed via a liquid-metal heat carrier, for which thematerial itself of the target may be used for the first circuit of the heat transformer 7.ln the second embodiment, heat is removed via a gaseous heat carrier, preferablyhelium.
The proposed method includes two embodiments of the device as follows. ln the first embodiment of the device (Fig. 1), a relativistic ion beam is directedout of the accelerator 1 through the transportation unit 2 and the beam-sweeping unit3 via the open upper face 14 to the target 4.
Cascade degradation is initiated by beam ions in atomic nuclei of the material ofthe target 4 generally with the concomitant release of intranuclear energy. Theresulting generated secondary-particle flux ensures main energy generation in thetarget 4 by nuclear fission of actinide elements. Before the very end of the flux,predominantly represented by neutrons, its large part is adsorbed by actinide nuclei,thus promoting the growth of the calorific value of the material of the target 4 to aknown extent. Another portion of this flux is neutralized by actinide nuclear fragmentswith their subsequent transmutation. Further, by means of the target-stirring unit 5, aportion of source and transmutation nuclei of fission products (within the actinidemixture) is displaced to the top of the target where it is destructed (generally withenergy release as well) by the primary beam and in the high-energy secondary-particle flux. Owing to the loss compensation of the material of the target 4, which isperformed regularly by the backup unit 6, an essentially indefinitely continuingbalanced proportion between the atomic-nuclei disintegration products and actinidesis thus reached and maintained in the target.
The excessive heat being generated in the target is removed by means ofcirculation loops comprising the heat carrier pipelines 10-13 of the heat transformer7 and then either fully converted to electric energy with the subsequent transfer of itsrespective portion to consumers or partially utilized for various process needs as ahigh- and a low-potential thermal energy. ln the second embodiment (Fig. 2), the method for conversion of nuclear energyinto thermal energy is similar to that described in the first embodiment.
The devices operate according to the sequence diagram (Fig. 3).
During the standard operation of the first embodiment of the device, theextraction of the material of the target 4 in the form of liquid and (or) solid radioactivewaste is completely excluded. The radioactive materials generated during operationof the second embodiment of the device as mechanically spent bulk material of thetarget 4 are either directed to re-fabrication with the subsequent loading into a similartarget or transformed into a liquid melt for the subsequent use as the target contentof the first embodiment of the device.
Upon expiration of the service life of both devices or in case of earlydecommissioning, the radioactive materials of the units 4-7 and the infrastructure 8- 13 may serve as fuel for similar devices, including the next generation ones.
Therefore, the use according to the invention allows developing and deployingthe nuclear-power engineering in line with the IAEA requirements: practicallyunlimited reserves of fuel raw material, the natural safety of nuclear-power units,compliance with the non-proliferation treaty, and stable background radiation onEarth.
Claims (4)
1. A method for Conversion of nuclear energy into thermal energy, comprising an ion beam that is produced and accelerated, the material of deeply under-critical target that is irradiated with the beam, the secondary-particle flux with two or more generations of nuclear fragments that isobtained in the target, the intranuclear energy that is released in the target having the size that ensures thetransfer of kinetic energy from the beam and from secondary-particle flux to thetarget, and the loss of the material of the target that is compensated, characterized in that when irradiating the target, the ion beam is displaced along thesurface of the target in the spatial angle of the full absorption of the secondary-particle flux by the target and the material of the target is simultaneously stirred.
2. A device for carrying out the method as claimed in claim 1, comprising an ion-flux accelerator and a flux transportation unit arranged in series and coaxially;a vertical deeply under-critical liquid-melt target, which includes heavy chemicalelements, wherein the target has a heat-, radiation-, and corrosion-resistant casewith an open upper end; a heat transformer unit; and a backup unit; characterized in that the device is additionally fitted with an electromagnetic fluxorthogonal sweeping unit and a target-stirring unit, wherein the sweeping unit iscoaxially arranged between the flux transportation unit and the target and whereinthe stirring unit is designed with the possibility of being in electromagnetic contactwith the material of the target.
3. A device for carrying out the method as claimed in claim 1, comprising an ion-flux accelerator and a flux transportation unit arranged in series and coaxially; a vertical deeply under-critical target, which includes heavy chemical elements,wherein the target has a heat-, radiation-, and corrosion-resistant case with an openupper end; a heat transformer unit; and a backup unit connected thereto; characterized in that the target consists of bulk material, wherein the device is additionally fitted with an electromagnetic flux orthogonal sweeping unitand a target-stirring unit, a hole is provided at the bottom of the target case, the sweeping unit is coaxially arranged between the flux transportation unit and thetarget, and the stirring unit is designed with the possibility of being in mechanical contact withthe material of the target through both the holes in the case of the target.
4. A device as claimed in claim 3 characterized in that all of the bulk material ofthe target is comprised of streamlined fuel elements.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2016109041A RU2624824C1 (en) | 2016-03-14 | 2016-03-14 | Method of nuclear energy conversion into thermal and device for its implementation (variants) |
PCT/RU2017/000127 WO2017160184A1 (en) | 2016-03-14 | 2017-03-10 | Method for converting nuclear energy into heat energy and device for implementing same (variants) |
Publications (2)
Publication Number | Publication Date |
---|---|
SE1851249A1 SE1851249A1 (en) | 2018-10-12 |
SE544185C2 true SE544185C2 (en) | 2022-02-22 |
Family
ID=59312918
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SE1851249A SE544185C2 (en) | 2016-03-14 | 2017-03-10 | A method for conversion of nuclear energy into thermal energy and a device for implementing the method |
Country Status (4)
Country | Link |
---|---|
DE (1) | DE112017001303T5 (en) |
RU (1) | RU2624824C1 (en) |
SE (1) | SE544185C2 (en) |
WO (1) | WO2017160184A1 (en) |
Citations (6)
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JP2004191190A (en) * | 2002-12-11 | 2004-07-08 | Laser Gijutsu Sogo Kenkyusho | High-temperature generating method and system by nuclear transformation processing |
WO2009117803A1 (en) * | 2008-03-25 | 2009-10-01 | Abb Inc. | Modulated electromagnetic stirring of metals at advanced stage of solidification |
WO2011120555A1 (en) * | 2010-03-29 | 2011-10-06 | Jacobs E&C Limited | Accelerator-driven nuclear system with control of effective neutron multiplication coefficent |
KR20130079521A (en) * | 2010-08-31 | 2013-07-10 | 더 텍사스 에이 앤드 엠 유니버시티 시스템 | Accelerator driven sub-critical core |
US20140305261A1 (en) * | 2013-04-16 | 2014-10-16 | Michael Lundh | Method And A Control System For Controlling A Melting And Refining Process |
SE1551606A1 (en) * | 2014-12-10 | 2016-06-11 | Ltd Liability Company Injector | Method for conversion of nuclear energy into heat and devicetherefor |
Family Cites Families (4)
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US5037601A (en) * | 1990-08-23 | 1991-08-06 | Dauvergne Hector A | Glass-pool, gas-cycle nuclear power plant |
RU2238597C1 (en) * | 2003-03-03 | 2004-10-20 | Острецов Игорь Николаевич | Method for nuclear-to-heat energy conversion |
RU2413314C2 (en) * | 2008-07-09 | 2011-02-27 | Алексей Сергеевич Богомолов | Method and complex of conversion of nuclear energy to heat energy |
RU2567970C1 (en) | 2014-08-05 | 2015-11-10 | Федеральное государственное бюджетное учреждение науки Институт механики сплошных сред Уральского отделения Российской академии наук | Device for mixing melted aluminium alloy (versions) |
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2016
- 2016-03-14 RU RU2016109041A patent/RU2624824C1/en active
-
2017
- 2017-03-10 SE SE1851249A patent/SE544185C2/en unknown
- 2017-03-10 DE DE112017001303.8T patent/DE112017001303T5/en not_active Withdrawn
- 2017-03-10 WO PCT/RU2017/000127 patent/WO2017160184A1/en active Application Filing
Patent Citations (6)
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JP2004191190A (en) * | 2002-12-11 | 2004-07-08 | Laser Gijutsu Sogo Kenkyusho | High-temperature generating method and system by nuclear transformation processing |
WO2009117803A1 (en) * | 2008-03-25 | 2009-10-01 | Abb Inc. | Modulated electromagnetic stirring of metals at advanced stage of solidification |
WO2011120555A1 (en) * | 2010-03-29 | 2011-10-06 | Jacobs E&C Limited | Accelerator-driven nuclear system with control of effective neutron multiplication coefficent |
KR20130079521A (en) * | 2010-08-31 | 2013-07-10 | 더 텍사스 에이 앤드 엠 유니버시티 시스템 | Accelerator driven sub-critical core |
US20140305261A1 (en) * | 2013-04-16 | 2014-10-16 | Michael Lundh | Method And A Control System For Controlling A Melting And Refining Process |
SE1551606A1 (en) * | 2014-12-10 | 2016-06-11 | Ltd Liability Company Injector | Method for conversion of nuclear energy into heat and devicetherefor |
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Title |
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Also Published As
Publication number | Publication date |
---|---|
RU2624824C1 (en) | 2017-07-07 |
WO2017160184A1 (en) | 2017-09-21 |
DE112017001303T5 (en) | 2018-11-22 |
SE1851249A1 (en) | 2018-10-12 |
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