GB2585535A - Nuclear powered internal engine nuclear fuel cycle and housing design improvements - Google Patents

Nuclear powered internal engine nuclear fuel cycle and housing design improvements Download PDF

Info

Publication number
GB2585535A
GB2585535A GB2013210.6A GB202013210A GB2585535A GB 2585535 A GB2585535 A GB 2585535A GB 202013210 A GB202013210 A GB 202013210A GB 2585535 A GB2585535 A GB 2585535A
Authority
GB
United Kingdom
Prior art keywords
nanofuel
engine
transuranic elements
elements
moderator
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
GB2013210.6A
Other versions
GB202013210D0 (en
Inventor
Adams Mark
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
GLOBAL ENERGY RES ASSOCIATES LLC
Original Assignee
GLOBAL ENERGY RES ASSOCIATES LLC
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
Priority to US15/883,066 priority Critical patent/US20180170496A1/en
Application filed by GLOBAL ENERGY RES ASSOCIATES LLC filed Critical GLOBAL ENERGY RES ASSOCIATES LLC
Priority to PCT/US2019/015712 priority patent/WO2019164645A2/en
Publication of GB202013210D0 publication Critical patent/GB202013210D0/en
Publication of GB2585535A publication Critical patent/GB2585535A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42Reprocessing of irradiated fuel
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B63SHIPS OR OTHER WATERBORNE VESSELS; RELATED EQUIPMENT
    • B63HMARINE PROPULSION OR STEERING
    • B63H21/00Use of propulsion power plant or units on vessels
    • B63H21/18Use of propulsion power plant or units on vessels the vessels being powered by nuclear energy
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/02Reactor and engine structurally combined, e.g. portable
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F7/00Shielded cells or rooms
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B63SHIPS OR OTHER WATERBORNE VESSELS; RELATED EQUIPMENT
    • B63GOFFENSIVE OR DEFENSIVE ARRANGEMENTS ON VESSELS; MINE-LAYING; MINE-SWEEPING; SUBMARINES; AIRCRAFT CARRIERS
    • B63G8/00Underwater vessels, e.g. submarines; Equipment specially adapted therefor
    • B63G8/08Propulsion
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B64AIRCRAFT; AVIATION; COSMONAUTICS
    • B64GCOSMONAUTICS; VEHICLES OR EQUIPMENT THEREFOR
    • B64G1/00Cosmonautic vehicles
    • B64G1/22Parts of, or equipment specially adapted for fitting in or to, cosmonautic vehicles
    • B64G1/40Arrangements or adaptations of propulsion systems
    • B64G1/408Nuclear spacecraft propulsion
    • 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
    • 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
    • Y02E30/30Nuclear fission reactors
    • 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
    • Y02TCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO TRANSPORTATION
    • Y02T70/00Maritime or waterways transport
    • Y02T70/50Measures to reduce greenhouse gas emissions related to the propulsion system
    • 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
    • Y02TCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO TRANSPORTATION
    • Y02T90/00Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • Y02T90/40Application of hydrogen technology to transportation, e.g. using fuel cells
    • 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
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Abstract

A nanofuel engine including receiving nanofuel (including moderator, nanoscale molecular dimensions & molecular mixture) internally in an internal combustion engine that releases nuclear energy, is set forth. A nanofuel chemical composition of fissile fuel, passive agent, and moderator. A method of obtaining transuranic elements for nanofuel including: receiving spent nuclear fuel (SNF); separating elements from SNF, including a stream of elements with Z>92, fissile fuel, passive agent, fertile fuel, or fission products; and providing elements. A method of using transuranic elements to create nanofuel, including: receiving, converting, and mixing the transuranic elements with a moderator to obtain nanofuel. A method of operating a nanofuel engine loaded with nanofuel in spark or compression ignition mode. A method of cycling a nanofuel engine, including compressing nanofuel; igniting nanofuel; capturing energy released in nanofuel, which is also the working fluid; and using the working fluid to perform mechanical work or generate heat.

Claims (64)

What Is Claimed Is:
1. A method of obtaining transuranic elements for nanofuel comprising: a) receiving spent nuclear fuel; b) separating the transuranic elements from said spent nuclear fuel, wherein said separating comprises: separating said spent nuclear fuel into at least one stream, wherein said at least one stream comprises the transuranic elements comprising at least one of: any of all elements with an atomic number Z greater than 92 (Z > 92); a fissile fuel; a passive agent; a fertile fuel; or a fission product; and c) providing the transuranic elements.
2. The method according to claim 1, wherein said (a) of said receiving said spent nuclear fuel, comprises: receiving commercial light water reactor (LWR) spent nuclear fuel.
3. The method according to claim 1, wherein said (b) of said separating said spent nuclear fuel into at least one stream comprises at least one of: i) separating into a stream of substantially uranium isotope 238 (238U); ii) separating into a stream of substantially fission products; or iii) separating into a stream of the transuranic elements.
4. The method according to claim 3, wherein said (b) (i) of said separating into said stream of substantially uranium isotope 238 (238U), further comprises: productizing said stream of substantially uranium isotope 238 (238U) as a commodity.
5. The method according to claim 1, wherein said (c) of said providing the transuranic elements comprises at least one of: providing the transuranic elements in a solid form; providing the transuranic elements in a liquid form; or providing the transuranic elements in a gaseous form.
6. The method according to claim 5, wherein said providing the transuranic elements in said solid form comprises at least one of: providing the transuranic elements in a substantially tetrafluoride (F4) form; or providing the transuranic elements in a substantially dioxide (O2) form.
7. The method according to claim 1, wherein said (b) of said separating said spent nuclear fuel into at least one stream comprises at least one of: i) separating by at least one process of pyrochemical processing or pyroprocessing; ii) separating by at least one process of electrometallurgical treatment; iii) separating without isotope separation; or iv) separating by a proliferation resistant, environmentally friendly process.
8. The method according to claim 1, wherein said (c) of said providing the transuranic elements comprises: providing the transuranic elements for use in a nanofuel engine.
9. A method of using transuranic elements to create nanofuel, said method comprising: a) receiving the transuranic elements, wherein the transuranic elements comprise at least one of: any of all elements with atomic number Z greater than 92 (Z > 92); a fissile fuel; or a passive agent; and wherein the transuranic elements have had substantially most fission products removed therefrom; and b) mixing the transuranic elements with a moderator to obtain nanofuel.
10. The method according to claim 9, further comprising: c) loading the transuranic elements and said moderator in a nanofuel engine.
11. The method according to claim 9, wherein said (a) comprises: loading the transuranic elements in a nanofuel engine.
12. The method according to claim 9, wherein the transuranic elements comprise: at least one stream comprising at least one of: a stream of substantially uranium isotope 238 (238U); a stream of substantially fission products; or a stream of the transuranic elements.
13. The method according to claim 9, wherein said fissile fuel comprises: plutonium isotope 239 hexafluoride (22â JPuFr,)..
14. The method according to claim 9, wherein said passive agent comprises: plutonium isotope 240 hexafluoride (240PuFr,).
15. The method according to claim 9, wherein said moderator comprises: molecular hydrogen (Ff).
16. The method according to claim 9, wherein said (b) comprises: i) converting the transuranic elements into a gas form; and ii) mixing the transuranic elements in said gas form with said moderator to obtain said nanofuel.
17. The method according to claim 16, wherein said (b) (i) of converting the transuranic elements into a gaseous form comprises: loading the transuranic elements in a tetrafluoride form into a fluorination reactor; and converting the transuranic elements in said tetrafluoride form to the transuranic elements in a substantially hexafluoride form.
18. The method according to claim 16, wherein said (b) (ii) of mixing the transuranic elements with said moderator to obtain said nanofuel, comprises: wherein said moderator comprises: any of all elements having an atomic number Z less than 11 (Z < 11).
19. The method according to claim 9, wherein said (b) of mixing the transuranic elements with said moderator to obtain said nanofuel comprises: leaving said nanofuel ready for operation in a nanofuel engine.
20. A method of operating a nanofuel engine loaded with nanofuel, comprising at least one of: a) operating the nanofuel engine in a spark ignition mode by injecting neutrons into the nanofuel using a source external to the nanofuel; or b) operating the nanofuel engine in a compression ignition mode by creating neutrons in the nanofuel comprising: i) using a radioactive material that emits neutrons.
21. The method according to claim 20, wherein said (a) of said operating the nanofuel engine in said spark ignition mode by injecting neutrons into the nanofuel using said source external to the nanofuel, comprises at least one of: i) using a fusion neutron source; or ii) using a radioactive material that emits neutrons.
22. The method according to claim 21, wherein said (a) (i) of said using said fusion neutron source in said operating the nanofuel engine in said spark ignition mode by injecting neutrons into the nanofuel using said source external to the nanofuel comprises at least one of: using an accelerator-based neutron generator; or using a Z-pinch-based neutron generator.
23. The method according to claim 21, wherein said (a) (ii) of said using said radioactive material that emits neutrons in said operating the nanofuel engine in said spark ignition mode by injecting neutrons into the nanofuel using said source external to the nanofuel comprises: using californium isotope 252 (252Cf).
24. The method according to claim 20, wherein said (b) (i) of said operating the nanofuel engine in said compression ignition mode by creating neutrons in the nanofuel comprising said using said radioactive material that emits neutrons comprises at least one of: using neutrons emitted from a fission product; or using neutrons emitted from a transuranic element.
25. A method of using nanofuel in a nanofuel engine comprising: a) compressing the nanofuel in the nanofuel engine; and b) igniting the nanofuel using a neutron source, wherein said igniting comprises: triggering a release of nuclear energy from the nanofuel.
26. The method according to claim 25, wherein the nanofuel comprises: a moderator, a molecule with dimensions on a nanometer scale, and a molecular mixture.
27. The method according to claim 26, wherein the nanofuel comprises: a fissile fuel, wherein said fissile fuel comprises: a nuclide that undergoes neutron induced fission; a passive agent, wherein said passive agent comprises: a nuclide comprising a strong resonance neutron absorption cross-section in a low epithermal energy range; and a moderator, wherein said moderator comprises: a low atomic number element.
28. The method according to claim 26, wherein said triggering said release of nuclear energy from the nanofuel further comprises: using the energy released from the nanofuel to generate heat.
29. The method according to claim 26, further comprising: c) capturing said release of nuclear energy from the nanofuel in the nanofuel, wherein the nanofuel is also a working fluid in the nanofuel engine; and d) using the energy in said working fluid to perform work.
30. The method according to claim 26, further comprising: c) receiving the nanofuel in the nanofuel engine.
31. The method according to claim 26, further comprising: c) exhausting the nanofuel from the nanofuel engine.
32. The method according to claim 26, wherein the method comprises an Otto cycle, wherein said Otto cycle is characterized by a set of dimensionless parameters comprising: a compression ratio (r); and a ratio of an energy deposited in the nanofuel to an initial heat content of the nanofuel (0, wherein x = Q/(M cvT), wherein O is said energy deposited in the nanofuel, wherein Mis a mass of the nanofuel in the nanofuel engine, wherein cv is a constant-volume heat capacity of the nanofuel, and wherein T is a temperature of the nanofuel.
33. The method according to claim 32, wherein said compression ratio r comprises: a ratio of an engine core volume of the nanofuel engine in a bottom dead center (BDC) position to an engine core volume of the nanofuel engine in a top dead center (TDC) position.
34. The method according to claim 26, further comprising: c) controlling said release of nuclear energy from the nanofuel by at least one of: changing the nanofuel; adjusting an inlet nanofuel state; or varying a compression ratio r.
35. The method according to claim 26, wherein said compressing of the nanofuel of said (a), comprises: placing a mass of the nanofuel into an engine core, wherein said engine core changes with said compressing of the nanofuel.
36. The method according to claim 35, wherein said compressing of the nanofuel is accomplished by at least one of: at least one piston, in a reciprocating engine, wherein said reciprocating engine comprises at least one housing; or at least one rotor, in a rotary engine, wherein said rotary engine comprises a at lease one housing.
37. The method according to claim 26, wherein said igniting of said (b), comprises at least one of: igniting via an external neutron source; or igniting via an internal neutron source.
38. The method according to claim 26, wherein said release of nuclear energy, comprises at least one of: i) releasing energy until a nanofuel temperature gets too high and the nanofuel engine transitions into a subcritical state due to a nanofuel negative temperature coefficient of reactivity; or ii) releasing energy until an engine core gets too large and the nanofuel engine transitions into a subcritical state due to a criticality of said engine core.
39. The method according to claim 38, wherein said release of nuclear energy comprises said (i), and wherein said (i) comprises: wherein the nanofuel comprises: a fissile fuel, a passive agent, and a moderator; and wherein the nanofuel comprises a temperature coefficient of reactivity (ar) that is less than zero in units of inverse Kelvin (ar < 0 l/K), . . wherein wherein k comprises a neutron multiplication factor, and wherein T comprises a nanofuel temperature.
40. The method according to claim 38, wherein said release of nuclear energy comprises said (ii), and wherein said (ii), comprises: wherein said criticality of said engine core comprises: wherein Bm comprises a material buckling of said engine core, and wherein Bg comprises a geometric buckling of said engine core.
41. The method according to claim 40, wherein said criticality of said engine core further comprises: wherein the nanofuel engine comprises a cylindrical shape reciprocating engine geometry with said engine core comprising a cylinder radius R and a cylinder height H, and wherein said criticality comprises: wherein L comprises a neutron diffusion length, wherein /c¥comprises an infinite medium multiplication factor, wherein v0 and p comprise known constants, wherein Rc comprises an extrapolated critical radius of said engine core, and wherein Hc comprises an extrapolated critical height of said engine core.
42. The method according to claim 41, wherein said releasing energy until said engine core gets too large, comprises: wherein the nanofuel engine apparatus is supercritical when said cylinder radius R is greater than a critical radius Rc (R > Rc): and wherein said critical radius Rc of said engine core of said criticality for said cylindrical shape reciprocating engine geometry comprises: wherein r is a compression ratio, wherein d is an extrapolation distance, and wherein a subscript one represents an inlet property.
43. The method according to claim 38, wherein said (ii), comprises: wherein said releasing energy until said engine core gets too large with respect to said criticality, wherein said criticality relates to a reflector of the nanofuel engine, wherein said reflector reduces neutron leakage, and wherein said reflector comprises at least one of: making the nanofuel engine smaller than without said reflector; or slowing down and returning fast neutrons back into the nanofuel by a finite thickness of said reflector.
44. The method according to claim 29, wherein said using the energy in said working fluid to perform work of said (d), comprises at least one of: driving an alternator; driving a generator; driving a propeller; generating heat; turning a shaft; or turning at least one wheel.
45. The method according to claim 25, further comprising: c) cooling the nanofuel with a heat exchanger; and d) returning the nanofuel to the nanofuel engine.
46. The method according to claim 25, wherein the nanofuel engine comprises a rotary engine, and further comprising at least one of: allowing a full separation, or allowing a partial separation, of an intake and an exhaust port.
47. The method according to claim 46, wherein said partial separation of said intake and said exhaust port comprises: regulating an amount of the nanofuel left in the nanofuel engine, and permitting at least one of: using neutrons emitted from a fission product, or affecting energy released.
48. The method according to claim 25, wherein the nanofuel engine comprises a rotary engine, wherein said rotary engine comprises a rotor, wherein said rotor comprises a rotor cavity shape that comprises at least one of: an arbitrary shape; a cylindrical shape; an ellipsoidal shape; a rectangular shape; or a spherical shape; and wherein performance of said rotary engine is improved by decreasing said rotor cavity shape surface to volume ratio.
49. The method according to claim 48, wherein said rotor cavity shape comprises said ellipsoidal shape, wherein said rotary engine dimensions are dependent on said ellipsoidal shape when said rotor is in a top dead center (TDC) position, wherein a geometric condition arises wherein a rotor center-to-tip distance ( Rr ) depends on a minor radius (b) of said ellipsoidal shape and a reflector thickness (D) fitting between a rotor housing minor radius and an output shaft rotor journal when said rotor is in said TDC position, wherein c/Rr is an eccentricity ratio.
50. The method according to claim 49, wherein said rotary engine comprises a trochoid constant (K). wherein said K is equal to the inverse of said eccentricity ratio (K = Rr e). and wherein as said K increases said Rr decreases and said rotary engine dimensions decrease overall.
51 The method according to claim 50, wherein said trochoid constant K is greater than 5 and less than 11 (5 < K < 11).
52. The method according to claim 25, further comprising at least one of: a variable cycle speed; or a variable nanofuel engine power.
53. The method according to claim 1, wherein said (c) of said providing the transuranic elements comprises providing the transuranic elements in a plasma form.
54. The method according to claim 1, further comprising: d) receiving nanofuel into a nanofuel internal engine.
55. The method according to claim 54, wherein said nanofuel internal engine comprises: at least one engine housing; and at least one reflector.
56. The method according to claim 55, wherein at least one of: said at least one housing, or said at least one reflector, comprises: at least one channel.
57. The method according to claim 56, wherein said at least one channel comprises at least one of: a coolant; a reflector; or a moderator.
58. The method according to claim 54, wherein said nanofuel is received into an engine core of said nanofuel internal engine, and said engine core is bounded by a first layer material.
59. The method according to claim 58, wherein said first layer material has a second layer material to resist movement and to create structure.
60. The method according to claim 59, wherein said first layer material comprises Berrylium and wherein said second layer material comprises cement.
61. The method according to claim 54, comprising a coolant in a channel, a reflector, and a moderator.
62. The method according to claim 54, wherein said nanofuel internal engine and said nanofuel further comprise at least one of: water (ThO); heavy water (D20); light water (FFO): HF; C02; helium (He); molecular hydrogen (3⁄4); a reflector; beryllium (Be); lead (Pb); a coolant; a moderator; concrete; graphite; a channel; a vacuum; a first layer material; or a second layer material.
63. The method according to claim 54, wherein said nanofuel internal engine is geographically adjacent to any combination of, at least one of: a nuclear reactor; a spent nuclear fuel storage facility; or a fuel fabrication facility.
64. The method according to claim 54, wherein said nanofuel is fabricated from spent nuclear fuel from one or more sources comprising at least one of: stored nuclear waste; light water reactor spent nuclear fuel (LWRSNF); nuclear power plant spent nuclear fuel; spent nuclear waste from at least one of: reactor, commercial, industrial, university, military, or governmental source; industrial nuclear waste; or medical industry nuclear waste.
GB2013210.6A 2013-08-23 2019-01-29 Nuclear powered internal engine nuclear fuel cycle and housing design improvements Pending GB2585535A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
US15/883,066 US20180170496A1 (en) 2013-08-23 2018-01-29 Nuclear powered internal engine nuclear fuel cycle and housing design improvement
PCT/US2019/015712 WO2019164645A2 (en) 2018-01-29 2019-01-29 Nuclear powered internal engine nuclear fuel cycle and housing design improvements

Publications (2)

Publication Number Publication Date
GB202013210D0 GB202013210D0 (en) 2020-10-07
GB2585535A true GB2585535A (en) 2021-01-13

Family

ID=67687828

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2013210.6A Pending GB2585535A (en) 2013-08-23 2019-01-29 Nuclear powered internal engine nuclear fuel cycle and housing design improvements

Country Status (3)

Country Link
CA (1) CA3088263A1 (en)
GB (1) GB2585535A (en)
WO (1) WO2019164645A2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114030656B (en) * 2021-11-09 2022-08-05 西安交通大学 Novel variable-thrust nuclear heat propulsion system
CN114561603B (en) * 2022-03-02 2022-09-02 东北大学 NbHfZrU series uranium-containing high entropy alloy

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8192704B1 (en) * 2011-02-25 2012-06-05 The United States Of America As Represented By The Department Of Energy Spent nuclear fuel recycling with plasma reduction and etching
US20150052886A1 (en) * 2013-08-23 2015-02-26 Global Energy Research Associates, LLC Nanofuel engine apparatus and nanofuel
WO2015059445A1 (en) * 2013-10-03 2015-04-30 University Of Central Lancashire Chromatographic separation of nuclear waste
RU2626854C2 (en) * 2015-12-31 2017-08-02 Федеральное Государственное Унитарное Предприятие "Горно - Химический Комбинат" (Фгуп "Гхк") Method for producing mixed uranium and plutonium oxides

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8192704B1 (en) * 2011-02-25 2012-06-05 The United States Of America As Represented By The Department Of Energy Spent nuclear fuel recycling with plasma reduction and etching
US20150052886A1 (en) * 2013-08-23 2015-02-26 Global Energy Research Associates, LLC Nanofuel engine apparatus and nanofuel
WO2015059445A1 (en) * 2013-10-03 2015-04-30 University Of Central Lancashire Chromatographic separation of nuclear waste
RU2626854C2 (en) * 2015-12-31 2017-08-02 Федеральное Государственное Унитарное Предприятие "Горно - Химический Комбинат" (Фгуп "Гхк") Method for producing mixed uranium and plutonium oxides

Also Published As

Publication number Publication date
WO2019164645A2 (en) 2019-08-29
GB202013210D0 (en) 2020-10-07
CA3088263A1 (en) 2019-08-29
WO2019164645A3 (en) 2019-11-14

Similar Documents

Publication Publication Date Title
GB2585535A (en) Nuclear powered internal engine nuclear fuel cycle and housing design improvements
US9881706B2 (en) Nuclear powered rotary internal engine apparatus
CN110598304B (en) Physical and thermal coupling analysis method for space nuclear power propulsion system pebble bed reactor
Kowalczyk et al. Analysis of possible application of high-temperature nuclear reactors to contemporary large-output steam power plants on ships
US3009866A (en) Neutronic reactor
US9947423B2 (en) Nanofuel internal engine
US11450442B2 (en) Internal-external hybrid microreactor in a compact configuration
US20180170496A1 (en) Nuclear powered internal engine nuclear fuel cycle and housing design improvement
Ross et al. Nuclear closed-cycle gaseous heat engine concept
KYLSTRA et al. UF6 Plasma engine
Cooper Fast reactor rocket engines—Criticality
US3088890A (en) Method of fabricating a graphitemoderated reactor
Adams GERA
Robson A Conceptual Design for an Imploding-Liner Fusion Reactor
Perry Advanced Design Studies
Vaidyanathan Nuclear Reactor Engineering (Principle and Concepts)
Kile et al. Initial Development of a Generic Fluoride Salt-Cooled Reactor Model
Suwoto et al. Effects of fuel density on reactivity coefficients and kinetic parameters of pebble bed reactor
Jo et al. Preliminary Analysis of Temperature Coefficients for a 600MWth Block-type HTGR
Brasier et al. Application of Low Critical Mass Studies to Reactor Design
Boyarinov et al. An investigation of some models and approximations used in calculating fuel assemblies of a high-temperature gas-cooled reactor of the GT-MHR type
Wang et al. PRELIMINARY STUDY ON ZIRCONIUM HYDRIDE IN SHIELD DESIGN OF SMALL SODIUMCOOLED FAST REACTOR
Chen et al. Modeling and simulation of dispersion particle fuels in Monte Carlo neutron transport calculation
Alesso et al. Inherently safe nuclear-driven internal combustion engines
Ho et al. ICONE23-1651 IMPACT ON BURNUP PERFORMANCE OF COATED PARTICLE FUEL DESIGN IN PEBBLE BED REACTOR WITH ROX FUEL