摘要 :
Elementary equations related to the ''six-factor''formula for criticality are used to derive an expression for the cost of tritium,bred in a fission reactor,in terms of the cost of fissile material. Reasonable parameters give a va...
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Elementary equations related to the ''six-factor''formula for criticality are used to derive an expression for the cost of tritium,bred in a fission reactor,in terms of the cost of fissile material. Reasonable parameters give a value about two-thirds of that usually quoted (80times the price of fissile) for fusion-fission reactor self-bred tritium. However,the handling costs and hazards associated with large-scale LWR tritium production are not assessed. (ERA citation 02:050453)
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This paper examines the usefulness of testing hybrid fusion-fission blanket components in fission reactors, and reports the results of calculations indicating that blanket heating profiles, tritium breeding rates, fertile breeding...
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This paper examines the usefulness of testing hybrid fusion-fission blanket components in fission reactors, and reports the results of calculations indicating that blanket heating profiles, tritium breeding rates, fertile breeding rates, and fast-fission rates can be accurately duplicated in a fission reactor test. These results indicate that fission testing can play a major part in the hybrid blanket development program. (ERA citation 07:055829)
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A decentralized nuclear energy system is proposed comprising mass-produced pressurized water reactors in the size range 10 to 300 MW (thermal), to be used for the production of process heat, space heat, and electricity in applicat...
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A decentralized nuclear energy system is proposed comprising mass-produced pressurized water reactors in the size range 10 to 300 MW (thermal), to be used for the production of process heat, space heat, and electricity in applications where petroleum and natural gas are presently used. Special attention is given to maximizing the refueling interval with no interim batch shuffling in order to minimize fuel transport, reactor downtime, and opportunity for fissile diversion. These objectives demand a substantial fissile enrichment (7 to 15%). The preferred fissile fuel is U-233, which offers an order of magnitude savings in ore requirements (compared with U-235 fuel), and whose higher conversion ratio in thermal reactors serves to extend the period of useful reactivity and relieve demand on the fissile breeding plants (compared with Pu-239 fuel). Application of the neutral-beam-driven tokamak fusion-neutron source to a U-233 breeding pilot plant is examined. This scheme can be extended in part to a decentralized fusion energy system, wherein remotely located large fusion reactors supply excess tritium to a distributed system of relatively small nonbreeding D-T reactors. (ERA citation 04:053943)
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The conclusion of this work is that a bundle divertor, using an improved method of designing the magnetic field configuration, is feasible for the Demonstration Tokamak Hybrid Reactor (DTHR) investigated by Westinghouse. The most ...
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The conclusion of this work is that a bundle divertor, using an improved method of designing the magnetic field configuration, is feasible for the Demonstration Tokamak Hybrid Reactor (DTHR) investigated by Westinghouse. The most significant achievement of this design is the reduction in current density (1 kA/cm exp 2 ) in the divertor coils in comparison to the overall averaged current densities per tesla of field to be nulled for DITE (25 kA/cm exp 2 ) and for ISX-B exp 2 (11 kA/cm exp 2 ). Therefore, superconducting magnets can be built into the tight space available with a sound mechanical structure. (ERA citation 04:038007)
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Preliminary fusion reactor designs have been developed based on the tandem mirror confinement concept. These have included a 1000 MWe fusion power reactor and a nearer term fusion-fission hybrid reactor with reduced plasma confine...
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Preliminary fusion reactor designs have been developed based on the tandem mirror confinement concept. These have included a 1000 MWe fusion power reactor and a nearer term fusion-fission hybrid reactor with reduced plasma confinement and technology requirements. Brief descriptions are given. (ERA citation 04:007088)
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Fuel design considerations for a conceptual design of a commercial mirror hybrid reactor, optimized for breeding exp 239 Pu, are briefly discussed. exp 238 U sub 3 Si fuel and lithium hydride breeding material are proposed, along ...
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Fuel design considerations for a conceptual design of a commercial mirror hybrid reactor, optimized for breeding exp 239 Pu, are briefly discussed. exp 238 U sub 3 Si fuel and lithium hydride breeding material are proposed, along with helium gas cooling. Selection of materials for the blanket follows conventional fission reactor practice. A table of reactor parameters is presented. The Mirror Hybrid Reactor offers potential economical production of fissile material. (ERA citation 03:020713)
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摘要 :
The design environment for the blanket of a fusion hybrid is considered. It is noted that structural concerns play an important role in the trade-off between high performance and design simplicity for hybrid reactor systems and ar...
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The design environment for the blanket of a fusion hybrid is considered. It is noted that structural concerns play an important role in the trade-off between high performance and design simplicity for hybrid reactor systems and are quite challenging due to the high power densities and temperature gradients that may occur. The fusion--fission reactor concept and its mechanical features are reviewed. Structural concerns are discussed for tokamak, mirror and inertial fusion drivers. Various modes of fusion--fission operation are considered and the design requirements are discussed. The performance characteristics of hybrid blankets are considered. (ERA citation 04:052364)
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