Patent US4367193A successfully refreshed from Google Patents.
US4367193A
Expired / Lapsed
US
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Modular fusion apparatus using disposable core
Assignee: FDX Patents Holding Co NV
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Filing: 1979-10-22
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Granted: 1983-01-04
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Expires: 1999-10-22
Abstract
Abstract A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and/or recycled for subsequent use within the same blanket region. The high density plasma produces a large radiation and particle flux on the first wall of the plasma core region thereby necessitating replacement of the core from the blanket region from time to time. A series of disposable and replaceable central core regions are disclosed for a large-scale economical electrical power generating plant.
Inventors
- 👤 Robert W. Bussard
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-09 04:45
CPC Classifications
G; G21; G21B; G21B1/00; G21B1/25; H; H05; H05H; H05H1/00; H05H1/02; H05H1/10; H05H1/12; Y; Y02; Y02E; Y02E30/00; Y02E30/10
Claims Analysis
Total Claims: 21
Claim 1
Independent Claim
324 words
A toroidal reactor for generating thermal energy from fusion reactions in ionized plasma of fusible fuel comprising: (a) fusion core unit comprising a plasma containment means having a major radius on the order of 50 cm for containing said fusible fuel, said plasma containment means forming a plasma containment region, (b) said plasma containment means including a plurality of toroidal field coils adjacent to and surrounding said plasma containment region for generating a toroidal magnetic field, (c) means for transporting a cooling fluid to said toroidal field coils, (d) said toroidal field coils having fluid conducting portions for transporting said cooling fluid within regions of said toroidal field coils, (e) power supply means connected to said toroidal field coils for generating a high toroidal magnetic field within the ionized plasma within said plasma containment region, said toroidal magnetic field being on the order of greater than 100 KG, (f) said plurality of toroidal field coils comprising high-strength; non-superconducting conductors for sustaining said high field and thermal energies, (g) ohmic heating means for inducing an ohmic heating plasma current in said plasma fuel within said plasma containment means, said ohmic heating current raising the temperature of said plasma, said ohmic heating means including transformer means and said ohmic heating current generating a poloidal magnetic field within said plasma, (h) blanket means positioned completely outside of and substantially surrounding said toroidal field coils, (i) means extending into said plasma containment means for delivering said fusible fuel therein, (j) said fusion core unit being readily separable from said blanket means for permitting facile access to said fusion core unit to allow for replacement of said fusion core unit as required, (k) blanket cooling fluid transport means connected to said blanket means for transporting a cooling fluid to said blanket means, and (l) means connected to at least one of said blanket cooling fluid transport means and said toroidal field cooling transport means for extracting thermal energy therefrom.
Claim 2
Dependent Claim
324 words
A toroidal reactor for generating thermal energy from fusion reactions in ionized plasma of fusible fuel comprising: (a) fusion core unit comprising a plasma containment means having a major radius on the order of 50 cm for containing said fusible fuel, said plasma containment means forming a plasma containment region, (b) said plasma containment means including a plurality of toroidal field coils adjacent to and surrounding said plasma containment region for generating a toroidal magnetic field, (c) means for transporting a cooling fluid to said toroidal field coils, (d) said toroidal field coils having fluid conducting portions for transporting said cooling fluid within regions of said toroidal field coils, (e) power supply means connected to said toroidal field coils for generating a high toroidal magnetic field within the ionized plasma within said plasma containment region, said toroidal magnetic field being on the order of greater than 100 KG, (f) said plurality of toroidal field coils comprising high-strength; non-superconducting conductors for sustaining said high field and thermal energies, (g) ohmic heating means for inducing an ohmic heating plasma current in said plasma fuel within said plasma containment means, said ohmic heating current raising the temperature of said plasma, said ohmic heating means including transformer means and said ohmic heating current generating a poloidal magnetic field within said plasma, (h) blanket means positioned completely outside of and substantially surrounding said toroidal field coils, (i) means extending into said plasma containment means for delivering said fusible fuel therein, (j) said fusion core unit being readily separable from said blanket means for permitting facile access to said fusion core unit to allow for replacement of said fusion core unit as required, (k) blanket cooling fluid transport means connected to said blanket means for transporting a cooling fluid to said blanket means, and (l) means connected to at least one of said blanket cooling fluid transport means and said toroidal field cooling transport means for extracting thermal energy therefrom.
Claim 3
Dependent Claim
69 words
The toroidal reactor of claim 1, wherein said plasma containment means further includes a toroidal housing having a major radius on the order of 50 cm and a minor radius on the order of 20 cm and wherein, said toroidal field coils being adjacent to and surround said toroidal housing and means for transporting said cooling fluid around the surfaces of said toroidal housing adjacent said toroidal field coils.
Claim 4
Dependent Claim
25 words
The toroidal reactor of claim 2, wherein said blanket means further includes tritium breeding means for generating tritium from neutrons emitted in said fusion reactions.
Claim 5
Dependent Claim
40 words
A toroidal reactor as recited in claim 1 wherein said plasma containment means comprises: (a) a toroidal region for containing said plasma, and (b) means, including said plurality toroidal field coils, for magnetically confining said plasma within said toroidal region.
Claim 6
Dependent Claim
32 words
A toroidal reactor as recited in claim 4 wherein said means for magnetically confining said plasma further comprises means, in addition to said ohmic heating means, for generating said poloidal magnetic field.
Claim 7
Dependent Claim
23 words
A toroidal reactor as recited in claim 1 or 5 wherein said toroidal magnetic field strength is on the order of 100-150 kilogauss.
Claim 8
Dependent Claim
19 words
A toroidal reactor as recited in claim 1 wherein said fusible fuel is a mixture of deuterium and tritium.
Claim 9
Dependent Claim
32 words
A toroidal reactor as recited in claim 7 wherein said means for extracting thermal energy is connected to both said plasma containment means and said blanket means and comprises fluid transport means.
Claim 10
Dependent Claim
41 words
A toroidal reactor as recited in claim 8 wherein said thermal energy extraction means comprises one fluid transport means for extracting thermal energy from said plasma containment means and another fluid transport means for extracting thermal energy from said blanket means.
Claim 11
Dependent Claim
30 words
A toroidal reactor as recited in claim 8 wherein said thermal energy extraction means comprises a single fluid transport means for both said plasma containment means and said blanket means.
Claim 12
Dependent Claim
19 words
A toroidal reactor as recited in claim 6 wherein said fusible fuel is a mixture of deuterium and tritium.
Claim 13
Dependent Claim
32 words
A toroidal reactor as recited in claim 1 wherein said means for extracting thermal energy is connected to both said plasma containment means and said blanket means and comprises fluid transport means.
Claim 14
Dependent Claim
41 words
A toroidal reactor as recited in claim 12 wherein said thermal energy extraction means comprises one fluid transport means for extracting thermal energy from said plasma containment means and another fluid transport means for extracting thermal energy from said blanket means.
Claim 15
Dependent Claim
29 words
A toroidal reactor as recited in claim 12 wherein said thermal energy extraction means comprises a single fluid transport means for both said plasma containment and said blanket means.
Claim 16
Dependent Claim
41 words
A toroidal reactor as recited in claim 1 wherein said fusible fuel is a mixture of deuterium and tritium, said plasma containment means comprising a toroidal region and said toroidal region having a major radius on the order of 50 cm.
Claim 17
Dependent Claim
22 words
A toroidal reactor as recited in claim 15 wherein said toroidal region has a minor radius on the order of 20 cm.
Claim 18
Dependent Claim
24 words
A toroidal reactor as recited in claim 1 wherein said plasma containment means includes a toroidal region having as aspect ratio of approximately 2.5.
Claim 19
Dependent Claim
15 words
A toroidal reactor as recited in claim 17 wherein said toroidal field coils include copper-coils.
Claim 20
Dependent Claim
17 words
A toroidal reactor as recited in claim 1 further comprising means for reprocessing said radiation-damaged containment means.
Claim 21
Dependent Claim
18 words
A toroidal reactor device as recited in claim 1 further comprising auxiliary heating means for heating said plasma.
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USPTO Annuity & Maintenance Windows
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| 7.5 Years (Year 8) | 1990-01-03 | 1990-07-05 | 1991-01-04 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1994-01-03 | 1994-07-05 | 1995-01-04 | $7700.00 | Window Closed / Lapsed |