Actinide transmutation properties of thermal and fast fission reactors including multiple recycling

Wiese, H.W.

doi:10.1016/s0925-8388(98)00141-8

Cited by 24 publications

(6 citation statements)

References 1 publication

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“…During the studies at FZK some additional effects of the high Pu content have been discovered: "It turns out that for the CAPRA reactor with (U,Pu)-MOX fuel the upper limit of Pu/(U + Pu) « 0.45 works against quantitative recycling of burner Pu because of its quality decreasing with continued recycling" [42]. Consequently, this leads to the following conclusion: "CAPRA burner turns out to be a high-grade consumer of 'good and bad quality' Pu, leaving behind Pu which is deteriorated and proliferation resistant.…”

Section: Consommation Accrue De Plutonium Dans Les Réacteurs à Neutromentioning

confidence: 99%

“…Consequently, this leads to the following conclusion: "CAPRA burner turns out to be a high-grade consumer of 'good and bad quality' Pu, leaving behind Pu which is deteriorated and proliferation resistant. In equilibrium, 58% of Pu from reprocessing of spent CAPRA fuel has to be ultimate excluded from recycling" [42]. Thus, the CAPRA 4/94 core is not sustainable.…”

Section: Consommation Accrue De Plutonium Dans Les Réacteurs à Neutromentioning

confidence: 99%

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On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

Merk

Litskevich

2015

Energies

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An efficient burning of the plutonium produced during light water reactor (LWR) operation has the potential to significantly improve the sustainability indices of LWR operations. The work offers a comparison of the efficiency of Pu burning in different reactor configurations-a molten salt fast reactor, a LWR with mixed oxide (MOX) fuel, and a sodium cooled fast reactor. The calculations are performed using the HELIOS 2 code. All results are evaluated against the plutonium burning efficiency determined in the Consommation Accrue de Plutonium dans les Réacteurs à Neutrons RApides (CAPRA) project. The results are discussed with special view on the increased sustainability of LWR use in the case of successful avoidance of an accumulation of Pu which otherwise would have to be forwarded to a final disposal. A strategic discussion is given about the unavoidable plutonium production, the possibility to burn the plutonium to avoid a burden for the future generations which would have to be controlled.

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Section: Consommation Accrue De Plutonium Dans Les Réacteurs à Neutromentioning

confidence: 99%

Section: Consommation Accrue De Plutonium Dans Les Réacteurs à Neutromentioning

confidence: 99%

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

Merk

Litskevich

2015

Energies

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“…Moreover, the transmutation rate depends obviously also from the neutron flux intensity. Let us call to mind some useful parameters in transmutation studies [7]. The neutron spectrum is defined as χ ( r, E, t) = ϕ( r, E, t) ϕ( r, t) ,…”

Section: Theorymentioning

confidence: 99%

A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors

Bomboni

Cerullo

Lomonaco

et al. 2008

Science and Technology of Nuclear Installations

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This paper presents a critical review of the recent improvements in minimizing nuclear waste in terms of quantities, long-term activities, and radiotoxicities by innovative GCRs, with particular emphasis to the results obtained at the University of Pisa. Regarding these last items, in the frame of some EU projects (GCFR, PUMA, and RAPHAEL), we analyzed symbiotic fuel cycles coupling current LWRs with HTRs, finally closing the cycle by GCFRs. Particularly, we analyzed fertile-free and Pu-Th-based fuel in HTR: we improved plutonium exploitation also by optimizing Pu/Th ratios in the fuel loaded in an HTR. Then, we chose GCFRs to burn residual MA. We have started the calculations on simplified models, but we ended them using more “realistic” models of the reactors. In addition, we have added the GCFR multiple recycling option usingkeffcalculations for all the reactors. As a conclusion, we can state that, coupling HTR with GCFR, the geological disposal issues concerning high-level radiotoxicity of MA can be considerably reduced.

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“…The result confirms the expectations that breeding is traditionally more efficient with reduced initial Pu loading per unit volume [16] as well as coinciding with the opposite observation that the breeding performance and the Pu fissile quality tend to degrade with very high Pu content in cores. This effect has been observed in the modelling and simulation investigations of the CAPRA project, which investigated plutonium burning [24]. Based on this final test, it seems from a reactor physics point of view a really attractive approach to accept a lower power density, based on the comparable low fuel cost for the proposed NaCl-UCl system (compared to MOX fuelled fast reactors) and the significantly better breeding performance.…”

Section: Results and Discussion For The Two Component Systemmentioning

confidence: 72%

Evaluation of the Breeding Performance of a NaCl-UCl-Based Reactor System

et al. 2019

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The energy trilemma forms the key driver for the future of energy research. In nuclear technologies, molten salt reactors are an upcoming option which offers new approaches. However, the key would be closed fuel cycle operation which requires sufficient breeding for a self-sustained long term operation ideally based on spent fuel. To achieve these attractive goals two challenges have been identified: achieving of sufficient breeding and development of a demand driven salt clean up system. The aim is to follow up on previous work to create an initial approach to achieving sufficient breeding. Firstly, identification of a salt system with a high solubility for fertile material and sufficiently low melting point. Secondly, evaluation of the sensitivity of the breeding performance on the sort of fissile material, the fissile material loading, and the core dimension all based on a realistic salt system which provides the solubility for sufficient fertile material to achieve the required breeding in a homogeneous reactor without breeding blanket. Both points are essential to create an innovative solution to harvest the fruits of a closed fuel cycle without the penalty of the prohibitively huge investments. It is demonstrated that the identified and investigated NaCl-UCl based systems are feasible to deliver the requested in-core breeding within the given solubility limits of fertile material in the salt system using either uranium as start-up fissile component or plutonium. This result is enriched by the analysis of the achievable full power days per inserted mass of plutonium. These new insights support reactor optimization and lead to a first conclusion that systems with lower power density could be very attractive in the case of low fuel cost, like it would be given when operating on spent nuclear fuel.

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Actinide transmutation properties of thermal and fast fission reactors including multiple recycling

Cited by 24 publications

References 1 publication

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors

Evaluation of the Breeding Performance of a NaCl-UCl-Based Reactor System

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