16 research outputs found
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NOEL-A no-leak fusion blanket concept
Thermal analysis and tests of a non-leak fusion blanket concept (NOEL-No External Leak) are presented. The NOEL blanket module operates with a material A that is present in both its solid and liquid phases. The solid phase zone of material A is maintained as a thick lining on the inside of blanket module shells (which are made of stainless steel, aluminum or any other structural metal and serve as the first wall) by cooling tubes embedded in the solid zone. These metal tubes carry a liquid or gas coolant B at a temperature below the melting point of A. Most of the 14 MeV neutron energy is deposited as heat in the module interior, and the temperature increase from the shell to the interior due to heat flow is sufficient to keep the interior liquid. Pressure on the liquid A interior is maintained at a higher level than the pressure on B, so that B can not leak out if failures occur in the coolant tubes embedded in the frozen layer
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HYFIRE: a tokamak-high-temperature electrolysis system
Brookhaven National Laboratory (BNL) is carrying out a comprehensive conceptual design study called HYFIRE of a commercial fusion Tokamak reactor, high-temperature electrolysis system. The study is placing particular emphasis on the adaptability of the STARFIRE power reactor to a synfuel application. The HYFIRE blanket must perform three functions: (a) provide high-temperature (approx. 1400/sup 0/C) process steam at moderate pressures (in the range of 10 to 30 atm) to the high-temperature electrolysis (HTE) units; (b) provide high-temperature (approx. 700/sup 0/ to 800/sup 0/C) heat to a thermal power cycle for generation of electricity to the HTE units; and (c) breed enough tritium to sustain the D-T fuel cycle. In addition to thermal energy for the decomposition of steam into its constituents, H/sub 2/ and O/sub 2/, electrical input is required. Fourteen hundred degree steam coupled with 40% power efficiency results in a process efficiency (conversion of fusion energy to hydrogen chemical energy) of 50%
Fusion-Fission Hybrid Reactors
to the design of hybrid reactors and to inform the new generation of hybrid reactor researchers of the hybrid reactor data base developed in the seventies and early eighties
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Hyper fuse: a novel inertial confinement system utilizing hypervelocity projectiles for fusion energy production and fission waste transmutation
Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from an LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with a target in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs or /sup 90/Sr. The 14 MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n, 2n), (n, ..cap alpha..), etc.) that convert the long lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product
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HYPERFUSE: a novel inertial confinement system utilizing hypervelocity projectiles for fusion energy production and fission waste transmutation
Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from an LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with each other or a target block in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs or /sup 90/Sr. The 14-MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n, 2n), (n, ..cap alpha..), etc.) that convert the long lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product
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HYPERFUSE: a hypervelocity inertial confinement system for fusion energy production and fission waste transmutation
Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from an LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with each other or a target block in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs, /sup 90/Sr, /sup 129/I, /sup 99/Tc, etc. The 14-MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n,2n), (n,..cap alpha..), (n,..gamma..), etc.) that convert the long-lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product. The transmutation parametric studies conclude that the design of the hypervelocity projectiles should emphasize the achievement of high densities in the transmutation regions (greater than the DT fusion fuel density), as well as the DT ignition and burn criterion (rho R=1.0 to 3.0) requirements
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Results of parametric neutronic studies for high-temperature blankets with breeding
Previous conceptual studies have been extended to examine a wide range of possible blanket configurations. The overall goals of this study have been to achieve neutronically viable blanket combinations that obtain an average breeding ratio (BR) of at least 1.1 and a sufficiently high fraction of fusion energy, Q/sub FRAC//sup HI/ (20% HTE High Temperature Heat) in the HTE process steam. The present studies have converged on the most attractive blanket option. After a preliminary and a secondary round of parametric calculations, ZrO/sub 2/ was selected as the best ceramic material; and a shell design with a flux trap type of back breeding zone with a Zr or Graphite plug, was chosen as optimal for the HTE module
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Aluminum blanket/shield design for a high field ignition test reactor
A conceptual design is presented of a minimum activity Al blanket/shield for a High Field Ignition Test Reactor (HFITR). This blanket/shield minimizes the medium and long-term activation from high energy neutrons resulting from D-T reactions and should permit direct hands-on maintenance of blanket components from within the plasma chamber. The principal function of the proposed blanket/shield assembly is to attenuate neutrons
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Maintenance of low activity blankets
Engineering design considerations of a first wall blanket/shield assembly to facilitate maintenance and reliability of a high field ignition test reactor (HFITR) are addressed. The design of the blanket/shield assembly comprised primarily of high priority ALCOA aluminum or SAP and boron carbide minimizes the medium and long-term activation from high energy neutrons and should permit direct hands-on maintenance of blanket components from within the plasma chamber
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HYFIRE: fusion-high temperature electrolysis system
The Brookhaven National Laboratory (BNL) is carrying out a comprehensive conceptual design study called HYFIRE of a commercial fusion Tokamak reactor, high-temperature electrolysis system. The study is placing particular emphasis on the adaptability of the STARFIRE power reactor to a synfuel application. The HYFIRE blanket must perform three functions: (a) provide high-temperature (approx. 1400/sup 0/C) process steam at moderate pressures (in the range of 10 to 30 atm) to the high-temperature electrolysis (HTE) units; (b) provide high-temperature (approx. 700 to 800/sup 0/C) heat to a thermal power cycle for generation of electricity to the HTE units; and (c) breed enough tritium to sustain the D-T fuel cycle. In addition to thermal energy for the decomposition of steam into its constitutents, H/sub 2/ and O/sub 2/, electrical input is required. Power cycle efficiencies of approx. 40% require He cooling for steam superheat. Fourteen hundred degree steam coupled with 40% power cycle efficiency results in a process efficiency (conversion of fusion energy to hydrogen chemical energy) of 50%