Towards the thorium fuel cycle with molten salt fast reactors

Heuer, D.; Merle, E.; Allibert, M.; Brovchenko, Mariya; Ghetta, V.; Rubiolo, P.

doi:10.1016/j.anucene.2013.08.002

Cited by 174 publications

(76 citation statements)

References 8 publications

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“…This choice does not reflect the diversity of 4th generation reactors and their associated fuel cycle explored worldwide [5] or in the Generation IV International Forum (GIF) [6] but rather illustrates the benefits of FNR in the French nuclear strategy. Although our paper is based on the French strategy and does not aim at reflecting all the potential future reactors systems, it is important to recall that EPRs can be potentially used also for other innovative fuel cycles [7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Assessment of the Anticipated Environmental Footprint of Future Nuclear Energy Systems. Evidence of the Beneficial Effect of Extensive Recycling

2017

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Abstract:In this early 21st century, our societies have to face a tremendous and increasing energy need while mitigating the global climate change and preserving the environment. Addressing this challenge requires an energy transition from the current fossil energy-based system to a carbon-free energy production system, based on a relevant energy mix combining renewables and nuclear energy. However, such an energy transition will only occur if it is accepted by the population. Powerful and reliable tools, such as life cycle assessments (LCA), aiming at assessing the respective merits of the different energy mix for most of the environmental impact indicators are therefore mandatory for supporting a risk-informed decision-process at the societal level. Before studying the deployment of a given energy mix, a prerequisite is to perform LCAs on each of the components of the mix. This paper addresses two potential nuclear energy components: a nuclear fuel cycle based on the Generation III European Pressurized Reactors (EPR) and a nuclear fuel cycle based on the Generation IV Sodium Fast Reactors (SFR). The basis of this study relies on the previous work done on the current French nuclear fuel cycle using the bespoke NELCAS tool specifically developed for studying nuclear fuel cycle environmental impacts. Our study highlights that the EPR already brings a limited improvement to the current fuel cycle thanks to a higher efficiency of the energy transformation and a higher burn-up of the nuclear fuel (−20% on most of the chosen indicators) whereas the introduction of the GEN IV fast reactors will bring a significant breakthrough by suppressing the current front-end of the fuel cycle thanks to the use of depleted uranium instead of natural enriched uranium (this leads to a decrease of the impact from 17% on water consumption and withdrawal and up to 96% on SO x emissions). The specific case of the radioactive waste is also studied, showing that only the partitioning and transmutation of the americium in the blanket fuel of the SFR can reduce the footprint of the geological disposal (saving up to a factor of 7 on the total repository volume). Having now at disposition five models (open fuel cycle, current French twice through fuel cycle, EPR twice through fuel cycle, multi-recycling SFR fuel cycle and at a longer term, multi-recycling SFR fuel cycle including americium transmutation), it is possible to model the environmental impact of any fuel cycle combining these technologies. In the next step, these models will be combined with those of other carbon-free energies (wind, solar, biomass . . . ) in order to estimate the environmental impact of future energy mixes and also to analyze the impact on the way these scenarios are deployed (transition pathways).

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Section: Introductionmentioning

confidence: 99%

Assessment of the Anticipated Environmental Footprint of Future Nuclear Energy Systems. Evidence of the Beneficial Effect of Extensive Recycling

2017

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“…These figures are less than 26.5 Mt, the estimate for the total amount of uranium recoverable until the end of this century at still tolerable price of 140 USD/kg U. There should be little doubt that in the years 2065-2125 this much uranium could be found [14] and we assume the availability of this higher figure for plutonium production. Retiring of LWR reactors, built in the replacement period from 2025-65 before the working life of the last one expired by 2105, would not be economical unless they could be replaced with some cheaper carbon free energy source.…”

Section: Starting Requirements For Introduction Of Fbr and Mstr Respementioning

confidence: 99%

“…[14], annual breeding yield for thorium core reactor is 95 kg of U233 for 1,500 MW, or 63.3 kg of U233 per GW annually. With initial inventory of 3,260 kg of U233 per GW, one would need to operate thorium core reactor for 51.5 years to breed initial inventory to launch the next generation of MSTR reactors.…”

Section: Starting Requirements For Introduction Of Fbr and Mstr Respementioning

confidence: 99%

“…To stay with specific numerical example of CPP replacement in a transition time of 40 years ending 2065, 15,390 t of plutonium would be produced in the years 2016-2105, or 22,020 t of plutonium would be produced in the years 2016-2125 for extended life of LWR plants. If we use a figure of 7.46 t of plutonium per GW [14] to start thorium reactor with plutonium, the amount of plutonium obtained from LWR with working life of 40 years would start 2,063 GW of MSTR. With LWR reactors working life of 60 years 2,952 GW of MSTR could be started.…”

Section: Starting Requirements For Introduction Of Fbr and Mstr Respementioning

confidence: 99%

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Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change

Knapp¹,

Matijević²,

Pevec³

et al. 2016

JEPE

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Abstract:A climate relevant and immediately available proven light water nuclear strategy with a potential to contribute essentially and timely to reduction of carbon dioxide emission to the year 2065 was assumed. The perspective of fission energy after that year is considered. Two technologies with long term perspective which need no or small amounts of uranium, i.e. fast breeders and molten salt thorium reactors were singled out. The main technical and safety characteristics were considered. In both of these technologies it is essential to have starter nuclides as neither U238 nor Th232 are fissile. It was investigated whether plutonium from spent fuel of light water reactors generated to the year 2065 would be present in quantities sufficient to continue operation on the same or similar level in both technologies. However, taking into account operational safety, proliferation risks, and waste production preference must be given to thorium technology.

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“…In 2002, the GIF selected six nuclear reactor technologies being clean, safe and cost-effective, so as to meet increasing energy demands on a sustainable basis, while being resistant to diversion of materials for weapons proliferation and secure from terrorist attacks. Molten salt reactor [1][2][3] is among the six G4 reactor designs.…”

Section: Introductionmentioning

confidence: 99%

Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor

Sun

Cheng

2016

NUCL SCI TECH

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The Molten Salt Reactor (MSR) is one of the six advanced reactor nuclear energy systems for further research and development selected by Generation IV International Forum (GIF), which is distinguished by its core in which the fuel is dissolved in molten fluoride salt. Because fuel flow in the primary loop, the depletion of MSR is different from that of solid-fuel reactors. In this paper, an MCNP5 and ORIGEN2 Coupled Burnup (MOCBurn) code for MSR is developed under the MATLAB platform. Some new methods and novel arrangements are used to make it suitable for fuel flow in the MSR. To consider the fuel convection and diffusion in the primary loop of MSR, fuel mixing calculation is carried out after each burnup time step. Modeling function for geometry with repeat structures is implicated for reactor analysis with complex structures. Calculation for a high-burnup reactor pin cell benchmark is performed using the MOCBurn code. Results of depletion study show that the MOCBurn code is suitable for the traditional solid-fuel reactors. A preliminary study of the fuel mixture effect in MSR is also carried out.

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Towards the thorium fuel cycle with molten salt fast reactors

Cited by 174 publications

References 8 publications

Assessment of the Anticipated Environmental Footprint of Future Nuclear Energy Systems. Evidence of the Beneficial Effect of Extensive Recycling

Assessment of the Anticipated Environmental Footprint of Future Nuclear Energy Systems. Evidence of the Beneficial Effect of Extensive Recycling

Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change

Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor

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