Electrical energy requirements for ATW and fusion neutrons
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This note compares the electrical energy requirements of accelerator (ATW) and fusion plants designed to transmute nuclides of fission wastes. Both systems use the same blanket concept but for each source neutron the fusion system must utilize one blanket neutron for tritium breeding. The ATW and fusion plants are found to have the same electrical energy requirement per available blanket neutron when the blanket coverage is comparable and fusion Q {approx} 1, but the fusion plant has only a fraction of the energy requirement when Q {much{underscore}gt} 1. If the blanket thermal energy is converted to electricity, the fusion plant and ATW have comparable net electrical energy outputs per available neutron when Q {>=} 2.Keywords:
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Fusion power
Nuclear transmutation
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Neutron Transport
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Nuclear transmutation
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Long-lived fission product
Transuranium element
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The power profile in the blanket material of a nuclear fusion reactor can be simulated by using microwaves at 200 MHz. Using these microwaves, ceramic breeder materials can be thermally tested to determine their acceptability as blanket materials without entering a nuclear fusion environment. A resonating cavity design is employed which can achieve uniform cross sectional heating in the plane transverse to the neutron flux. As the sample size increases in height and width, higher order modes, above the dominant mode, are propagated and destroy the approximation to the heating produced in a fusion reactor. The limits at which these modes develop are determined in the paper.
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Breeder (animal)
Microwave heating
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We present a computer code DETRA which solves analytically the Bateman equations governing the decay, build-up and transmutation of radionuclides. The complexity of the chains and the number of nuclides are not limited. The nuclide production terms considered include transmutation of the nuclides inside the chain, external production, and fission. Time dependent calculations are possible since all the production terms can be re-defined for each irradiation step. The number of irradiation steps and output times is unlimited. D ETRA is thus able to solve any decay and transmutation problem as long as the nuclear data i.e. decay data and production rates, or cross sections, are known.
Nuclear transmutation
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Radioactive decay
Nuclear data
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Decay heat
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Xe-128 in I-127 transmutation targets irradiated by Xi'an pulse reactor was analyzed by using Quadrupole Mass Spectrometer (QMS) to calculate transmutation rate and release rate. Transmutation is an alternative method to transform long-lived toxic radio nuclides to short-lived radio nuclides or stable nuclides. 127I targets were irradiated in Xi'an Pulse Reactor for the first time to simulate the transmutation behavior of 129I. After irradiation, 128Xe in the target was determinate with online isotope dilution method by Quadrupole Mass Spectrometer (QMS), so that the transmutation rate and release rate could be calculated. Release behaviors of 128Xe were investigated through melting and step-heated modes. The stepwise heating experiment was done by puncturing method. The result shows the release rate in melting mode is 99.9% (RSD = 1%) and increases with the temperature in stepwise heating mode. The technique proposed in this work is suitable for accurate determination of transmutation rate of 129I.
Nuclear transmutation
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Quadrupole mass analyzer
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Nuclear transmutation
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Section (typography)
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The lead-cooled fast reactor can be used for the post-processing of part of the minor actinides (MA) nuclides contained in the spent fuel. This study designs three modes of adding MA nuclides to analyze and study the effect of the MA nuclides transmutation on the core critical performance, core life cycle and fuel temperature coefficient thus to study the effect of the MA nuclides addition on the reactor safety performance. The results show that the addition of MA nuclides reduces the initial critical performance of the core; that the addition by either coating or mixing with fuel can significantly extend the life cycle of the lead-cooled fast reactor, while the addition of transmutation rod has different effect on the core life cycle depending on the rod location; and that the addition of MA nuclides causes the change of fuel temperature coefficient, which, however, remains negative. All of the three addition modes are feasible. In particular, attention should be paid to the effect of the transmutation rod location on the core life cycle. It is not advisable to distribute the transmutation rods in a concentrated area.
Nuclear transmutation
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Transuranium element
Nuclear fuel cycle
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Fusion power
Structural material
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A configuration of a fusion-driven transmutation reactor with a low aspect ratio tokamak-type neutron source was determined in a self-consistent manner by using coupled analysis of tokamak systems and neutron transport. We investigated the impact of blanket configuration on the characteristics of a fusion-driven transmutation reactor. It was shown that by merging the TRU burning blanket and tritium breeding blanket, which uses PbLi as the tritium breeding material and as coolant, effective transmutation is possible. The TRU transmutation capability can be improved with a reduced blanket thickness, and fast fluence at the first wall can be reduced. Article History: Received: July 10th 2017; Received: Dec 17th 2017; Accepted: February 2nd 2018; Available onlineHow to Cite This Article: Hong, B.G. (2018) Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor. International Journal of Renewable Energy Development, 7(1), 65-70.https://doi.org/10.14710/ijred.7.1.65-70
Nuclear transmutation
Fusion power
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