Molten-Salt Reactors—History, Status, and Potential

Rosenthal, M.W.; Kasten, P.R.; Briggs, R. B.

doi:10.13182/nt70-a28619

Cited by 196 publications

(64 citation statements)

References 16 publications

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“…Two experiments with molten salt reactors were successfully conducted in Oak Ridge: the ARE (Aircraft Reactor Experiment) was running for approximately one hundred hours around 1955 at a thermal power of 2.5 MWth. Ten years later the MSRE (Molten Salt Reactor Experiment) started [Rosenthal, 1970] an 8MWth reactor fuelled at the beginning with 235 U and at the end with 233 U, ran for five years without any problem As the power was low, there was no need to perform one-line salt reprocessing. This preparatory work led the ORNL team to present a power reactor project, the Molten Salt Breeder Reactor [ Bettis 1970] fuelled with thorium and 233 U as fissile material.…”

Section: Why Molten Salts In Nuclear Energy Production?mentioning

confidence: 99%

Molten salts and nuclear energy production

Brun

2007

Journal of Nuclear Materials

137

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Molten salts (fluorides or chlorides) have been taken in consideration very soon in nuclear energy production researches. This was initially due to their advantageous physical properties: good heat transfer capacity, radiation insensitivity, high boiling point, .. and they can be used in various situations: heat transfer, core coolants with solid fuels, liquid fuel in molten salt reactor, solvents for spent nuclear solid fuel in the case of pyro-reprocessing, fusion. Molten salt reactors which are one of the six innovative concepts chosen by the Generation IV international forum may be particularly interesting in the case of waste incinerators or of the thorium cycle. As the neutron balance is very tight, the possibility to quickly extract poisoning fission products is very attractive. The most important questions addressed to demonstrate the scientific feasibility of Molten Salt Reactor will be reviewed.

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Section: Why Molten Salts In Nuclear Energy Production?mentioning

confidence: 99%

Molten salts and nuclear energy production

Brun

2007

Journal of Nuclear Materials

137

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“…Separation of product from the melt as part of an industrial process could employ vacuum distillation at high temperature to remove the salt whilst still molten. 48,49 …”

Section: Discussionmentioning

confidence: 99%

Electrochemical Reduction of UO₂to U in LiCl-KCl Molten Salt Eutectic Using the Fluidized Cathode Process

Abdulaziz

Brown

Inman

et al. 2017

J. Electrochem. Soc.

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The electrochemical reduction of UO 2 to U metal has been investigated in both Fluidized Cathode (FC) and Metallic Cavity Electrode (MCE) cell arrangements. Differences in the local concentration of O 2− where the reduction takes place influnces the reduction potential. The fleeting contact of UO 2 particle contact with the current collector in case of the FC results in much less O 2− buildup compared to MCE. Consequently, UO 2 reduction occurs over a range of potentials in the FC and may involve separate two 2-electron steps compared to one apparent 4-electron step in the MCE. It is proposed that there are three discrete periods during the FC reduction process. The first is an induction period during which reduced uranium particles gradually adhere to the tungsten current collector. The second is reduction associated with a rapid growth in electrode area and consequent increase in current. The third is a slower reduction of the remaining oxide in the melt. Complete reduction of metallic U is achieved at −2.2 V (vs. Ag/Ag + ) with an estimated faradaic current efficiency of >92%. There are significant drivers for pursuing the next generation of nuclear reactors. Generation IV reactors offer both advancements in reactor design and also feature fully integrated fuel reprocessing capabilities. There are six types of Generation IV nuclear reactors and power plants under development. These are: the very-high-temperature reactor (VHTR), the sodium-cooled fast reactor (SFR), the supercriticalwater-cooled reactor (SCWR), the gas-cooled fast reactor (GFR), the lead-cooled fast reactor (LFR), and the molten salt reactor (MSR). The key features of each are summarized in Table I. The fuel type used in the majority of these reactors is metal. Given that most current reactors employ metal oxide (MOX or UOX) fuel and the majority of legacy waste is also metal oxide, the conversion of metal oxides to metals is an important component in a future nuclear power flow sheet.High temperature molten salt reprocessing technology (pyroprocessing) 2 for spent nuclear fuel offers a range of advantages when compared to aqueous reprocessing techniques. This is due to: an improved proliferation resistance (local processing reduces the likelihood of material diversion, no separation of plutonium); using facilities with a smaller footprint; a shorter cooling period for irradiated fuel, and also improved criticality safety margins. Different process systems and salts have been studied in pyroprocessing, most of which are summarized by the Nuclear Energy Agency (NEA). Conceptual flow sheets for the pyrochemical treatment of used nuclear fuel are described by Argonne National Lab (ANL). 4 The spent nuclear fuel, in the form of oxide pellets, is decladded and chopped, then passed on for an electrolytic reduction step. The uranium is in the form of UO 2 ; hence, the reduction of UO 2 to U metal is being investigated here. The reduced species then undergo electrorefining, [5][6][7][8][9] where U product and other transuranic species are separated an...

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“…Criteria for selection include chemical compatibility, thermal conductivity, and melting point. Molten salt test reactor studies in the 1970s demonstrated minimal corrosion issues 9.4 between the coolant and in-vessel components; however, it is unclear whether these results can be extrapolated to AdvSMR designs (Rosenthal et al 1970). Metal corrosion can be controlled in LiF-BeF 2 coolants by purging the molten salt bath with H 2 /HF.…”

Section: Molten Salt Reactorsmentioning

confidence: 99%

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

Anheier¹,

Suter²,

Qiao³

et al. 2013

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Energy Research and Development Roadmap and industry stakeholders by evaluating optically based instrumentation and control (I&C) concepts for advanced small modular reactor (AdvSMR) applications. These advanced designs will require innovative thinking in terms of engineering approaches, materials integration, and I&C concepts to realize their eventual viability and deployment. The primary goals of this report include:1. Establish preliminary I&C needs, performance requirements, and possible gaps for AdvSMR designs based on best-available published design data.2. Document commercial off-the-shelf (COTS) optical sensors, components, and materials in terms of their technical readiness to support essential AdvSMR in-vessel I&C systems.3. Identify technology gaps by comparing the in-vessel monitoring requirements and environmental constraints to COTS optical sensor and materials performance specifications.4. Outline a future research, development, and demonstration (RD&D) program plan that addresses these gaps and develops optical-based I&C systems that enhance the viability of future AdvSMR designs.The DOE-NE roadmap outlines RD&D activities intended to overcome technical barriers that currently limit advances in nuclear energy. As part of this strategy, DOE-NE is sponsoring research on advanced reactor supportive technologies to reduce the identified barriers. Key challenges that must be overcome include the high capital costs to develop nuclear power plants, maintaining safety performance as the reactor fleet expands, minimizing nuclear waste, and maintaining strong proliferation resistance. AdvSMR designs are a major component of this strategy, because these designs offer a number of unique advantages. The modular and small size of AdvSMR designs naturally lead to reduced capital investments and, potentially, construction savings through factory fabrication. However, new economic and technical challenges accompany the many attractive features offered by AdvSMR designs. Specifically, the modest power output of AdvSMRs does not provide the economy of scale afforded by large reactors. In addition, many of the AdvSMR designs operate at much higher temperatures than lightwater reactors and require instrumentation to withstand harsh, in-vessel environments arising from unconventional, chemically aggressive coolants and unique reactor system configurations.Addressing these I&C challenges will be critically important to the AdvSMR development program to ensure the viability and future success of advanced reactor designs. Solutions will likely be found through evolution of conventional reactor technology, and the development of entirely new concepts. Early pressure/boiling water reactors used conventional I&C technologies (e.g., thermocouples, ionchambers, strain-gauge pressure sensors) to satisfy design requirements. Because these technologies worked well in the relatively low-temperature reactor designs, the demand for alternate I&C technologies was limited. At the time, optical-based reactor monitoring concepts were g...

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Molten-Salt Reactors—History, Status, and Potential

Cited by 196 publications

References 16 publications

Molten salts and nuclear energy production

Molten salts and nuclear energy production

Electrochemical Reduction of UO₂to U in LiCl-KCl Molten Salt Eutectic Using the Fluidized Cathode Process

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

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Molten-Salt Reactors—History, Status, and Potential

Cited by 196 publications

References 16 publications

Molten salts and nuclear energy production

Molten salts and nuclear energy production

Electrochemical Reduction of UO2to U in LiCl-KCl Molten Salt Eutectic Using the Fluidized Cathode Process

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

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Product

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Electrochemical Reduction of UO₂to U in LiCl-KCl Molten Salt Eutectic Using the Fluidized Cathode Process