Ionic melts in nuclear power

Katyshev, S. F.; Teslyuk, L. M.

doi:10.2495/978-1-78466-175-5/021

Cited by 3 publications

(7 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This forms a very promising boundary condition to achieve sufficient breeding and thus the salt composition could be a promising candidate for a future reactor. However, for the NaCl-UCl3-UCl4 salt system with the eutectic at 42.5%-17.0%-40.5% (E-eutectic, Pperitectic) [13,16] showing the two compositions for the later analysis.…”

Section: The Salt Systemmentioning

confidence: 95%

“…A first search for detailed information for the NaCl-UCl system led to the publications [15,16] providing preliminary information like the phase diagram and density field for 1050 K and the 3 component system NaCl-UCl 3 -UCl 4 , see Figure 1.…”

Section: The Salt Systemmentioning

confidence: 99%

“…This reference identifies NaCl-UCl 3 -UCl 4 having a eutectic composition at 42.5%-17.0%-40.5%, to be attractive for a further detailed investigation on different levels. The mentioned eutectic point of the NaCl-UCl 3 -UCl 4 salt has a melting point of 338 • C [16] and acceptable melting temperatures even for non-eutectic compositions, which will almost be unavoidably formed during reactor operation. From the point of view of operating on spent nuclear fuel and the devolved requirement to achieve sufficient breeding the main attraction of this system would be the high loading of fertile material already at the eutectic point.…”

Section: The Salt Systemmentioning

confidence: 99%

“…The experimental error in the density measurements is given with max ±1.5%. for the NaCl-UCl 3 -UCl 4 salt system with the eutectic at 42.5%-17.0%-40.5% (E-eutectic, P-peritectic) [13,16] showing the two compositions for the later analysis.…”

Section: The Salt Systemmentioning

confidence: 99%

See 3 more Smart Citations

The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor

et al. 2020

View full text Add to dashboard Cite

The energy trilemma and UN SDG 7 form the key drivers for the future of all kinds of energy research. In nuclear technology, molten salt reactors are an interesting option, since they can offer a game-changing approach to deliver an attractive, highly sustainable option for a zero-carbon society by providing sufficient breeding for a self-sustained long-term operation based on spent nuclear fuel from existing reactors while being able to be controlled ideally by inherent processes. To achieve these goals, several basic challenges have already been identified and worked on; demonstration of sufficient breeding and development of a demand driven salt clean up system. This study follows up on the opportunity for reactor control based on inherent feedback mechanisms. It is demonstrated that the investigated sodium chloride-uranium chloride-based systems can feasibly deliver a thermal feedback effect, which is strong enough, to compensate for the critically change due to breeding and fission product accumulation for two different compositions. The achieved results provide a very positive outlook on the system inherent ability for reactor self-control and even for the feasibility of a load following operation based on inherent feedback effects instead of massive and costly manual/automated control system operation.

show abstract

Section: The Salt Systemmentioning

confidence: 95%

Section: The Salt Systemmentioning

confidence: 99%

Section: The Salt Systemmentioning

confidence: 99%

Section: The Salt Systemmentioning

confidence: 99%

See 2 more Smart Citations

The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor

et al. 2020

View full text Add to dashboard Cite

show abstract

“…The salt data for the applied fuel composition were based on two advanced Russian publications by Katyshev and Teslyuk [24] and by Desyatnik and Katyshev [25]. The base configuration is NaCl-UCl3-UCl4 with the eutectic composition 45%(molar) NaCl -38.5%(molar) UCl4 -16.5%(molar) UCl3, worthy of further detailed investigation due to its relatively high loading of fertile heavy metal material at the eutectic point, which makes it a very promising composition for achieving the required breeding efficiency essential for future self-sustained breeding [19].…”

Section: Simulation Codes and Methods And Salt Datamentioning

confidence: 99%

Defining the Challenges - Identifying the Key Poisoning Elements to be Separated in a Future Integrated Molten Salt Fast Reactor Clean-up System for iMAGINE

Merk¹,

Detkina²,

Litskevich³

et al. 2022

Preprint

View full text Add to dashboard Cite

Nuclear fission technologies have the potential to play a significant role in the energy mix of a net-zero and sustainable society. However, to achieve the sustainability goal two significant challenges remain: efficient and sustainable fuel usage and the minimisation of long term nuclear waste. Civil nuclear molten salt systems and technologies offer the opportunity to address both, delivering future reactors at scale for efficient and effective power production and nuclear waste burnup. Potentially, both objectives could be fulfilled in one reactor system, which could significantly improve sustainability indices. In addition, demand driven development of a significantly reduced fuel cycle with enhanced proliferation resistance offers further potential for improvement. To achieve these goals, a transformative approach for salt clean-up during molten salt reactor operation is proposed in this work, by concentrating on the detection and removal of key neutron poisoning elements which prevent the reactor from long-term operation. This work also demonstrates the importance of the effective integration of physics, reactor design and chemistry when systems modelling in achieving these system development goals.

show abstract

Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors

Jeong

Shirvan

Buric

2022

Nuclear Science and Engineering

View full text Add to dashboard Cite

This work establishes a generic multiphysics tool for liquid-fueled molten salt reactors (LFMSRs) to select key installation locations and specify the expected operating temperature range for the development of advanced instrumentation and control systems, particularly distributed temperature sensors using fiber optics. A commercial computation fluid dynamics package (STAR-CCM+) is used to formulate a neutronics and thermal-hydraulic coupled solver, showing good agreement with a recent benchmark problem developed for evaluating the coupling methodology of neutronics and thermal hydraulics. The multiphysics model is then applied to the reference molten chloride salt fast reactor (MCFR) design under development by TerraPower based on publicly available information. The available twodimensional axisymmetric model for the reactor core is used for coupling calculations, and system component details are leveraged using the lumped method to complete the energy balance. The dynamic responses of the MCFR model are investigated during operational transients, such as unprotected loss-offlow and uniform perturbation scenarios. Maximum temperature and local temperature distributions are characterized during unprotected loss of flow and unprotected loss of heat sink events. The thermal responses of the fuel salt and core components are analyzed from induced perturbation of the system parameters, such as the flow rate and the heat sink capacity. The results motivate the use of continuous monitoring of the temperature variation in real time along the reflector region with the use of fiber optics to validate the multiphysics code to support a reactor's licensing basis, as well as to support the structural longevity and improve safety in LFMSRs.

show abstract

Ionic melts in nuclear power

Cited by 3 publications

References 0 publications

The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor

The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor

Defining the Challenges - Identifying the Key Poisoning Elements to be Separated in a Future Integrated Molten Salt Fast Reactor Clean-up System for iMAGINE

Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors

Contact Info

Product

Resources

About