TCT hybrid preconceptual blanket design studies
Description
The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region … continued below
Physical Description
Pages: 138
Creation Information
Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al. January 1, 1978.
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Pacific Northwest Laboratory
Publisher Info: Battelle Pacific Northwest Labs., Richland, Wash. (USA)Place of Publication: Richland, Washington
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Description
The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region of molten salt containing PuF/sub 3/. PNL analyzed this concept to determine its structural, thermal and hydraulic performance characteristics. An adequate first wall cooling method was determined, utilizing low pressure water in a double wall design. A conceptual layout of the converter region tubes was performed, providing adequate helium cooling and the desired movement of U-Mo slugs. A thermal hydraulic analysis of the power-producing blanket regions indicated that either more helium coolant tubes are needed or the salt must be circulated to obtain adequate heat removal capability.
Physical Description
Pages: 138
Notes
Dep. NTIS, PC A07/MF A01.
Subjects
Keywords
- Actinide Compounds
- Actinide Isotopes
- Actinide Nuclei
- Alkali Metal Compounds
- Alloys
- Alpha Decay Radioisotopes
- Beta Decay Radioisotopes
- Beta-Minus Decay Radioisotopes
- Boron Carbides
- Boron Compounds
- Breeding Blankets
- Carbides
- Carbon Compounds
- Chromium Alloys
- Chromium Steels
- Chromium-Nickel Steels
- Closed Plasma Devices
- Coolants
- Cooling Systems
- Corrosion Resistant Alloys
- Cracks
- Cryogenic Fluids
- Design
- Deuterium
- Divertors
- Elements
- Even-Even Nuclei
- First Wall
- Fluid Mechanics
- Fluids
- Fluorides
- Fluorine Compounds
- Halides
- Halogen Compounds
- Heat Resisting Alloys
- Heavy Nuclei
- Helium
- Hybrid Reactors
- Hydraulics
- Hydrogen Isotopes
- Iron Alloys
- Iron Base Alloys
- Isotopes
- Light Nuclei
- Lithium Compounds
- Lithium Fluorides
- Lithium Halides
- Materials Testing
- Mechanical Properties
- Mechanics
- Metals
- Molten Salts
- Molybdenum
- Molybdenum Alloys
- Nickel Alloys
- Nonmetals
- Nuclei
- Odd-Even Nuclei
- Odd-Odd Nuclei
- Performance Testing
- Physical Properties
- Physical Radiation Effects
- Plutonium Compounds
- Plutonium Fluorides
- Power Plants
- Radiation Effects
- Radioisotopes
- Rare Gases
- Reactor Components
- Refractory Metals
- Salts
- Stable Isotopes
- Stainless Steel-316
- Stainless Steels
- Steels
- Swelling
- Tensile Properties
- Testing
- Thermodynamic Properties
- Thermonuclear Devices
- Thermonuclear Reactor Cooling Systems
- Thermonuclear Reactor Walls
- Thermonuclear Reactors
- Tokamak Devices
- Tokamak Type Reactors
- Transition Elements
- Transuranium Compounds
- Tritium
- Two-Component Torus
- Uranium 238
- Uranium Compounds
- Uranium Fluorides
- Uranium Isotopes
- Years Living Radioisotopes 700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
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- Report No.: PNL-2304
- Grant Number: EY-76-C-06-1830
- Digital Object Identifier: https://doi.org/10.2172/5055484
- Office of Scientific & Technical Information Report Number: 5055484
- Archival Resource Key: ark:/67531/metadc1055369
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- January 1, 1978
Added to The UNT Digital Library
- Jan. 22, 2018, 7:23 a.m.
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- May 12, 2021, 2:21 p.m.
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Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al. TCT hybrid preconceptual blanket design studies, report, January 1, 1978; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1055369/: accessed March 24, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.