Molten plutonium chlorides fast breeder reactor cooled by molten uranium chloride

Taube, M.; Ligou, J.

doi:10.1016/0302-2927(74)90045-2

Cited by 29 publications

(14 citation statements)

References 3 publications

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“…The load-following capability of this MSBR system was studied for various ramp rates of the power demand [2]. Later a fast breeder reactor of about 2 GW thermal output using molten chlorides both as fuel and coolant was proposed [3].…”

Section: The Small Modular Dual Fluid Reactormentioning

confidence: 99%

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

Liu

Luo

et al. 2020

Metals

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The Small Modular Dual Fluid Reactor (SMDFR) is a novel molten salt reactor based on the dual fluid reactor concept, which employs molten salt as fuel and liquid lead/lead-bismuth eutectic (LBE) as coolant. A unique design of this reactor is the distribution zone, which locates under the core and joins the core region with the inlet pipes of molten salt and coolant. Since the distribution zone has a major influence on the heat removal capacity in the core region, the thermal hydraulics characteristics of the distribution zone have to be investigated. This paper focuses on the thermal hydraulics analysis of the distribution zone, which is conducted by the numerical simulation using COMSOL Multiphysics with the CFD (Computational Fluid Dynamics) module and the Heat Transfer module. The energy loss and heat exchange in the distribution zone are also quantitatively analyzed. The velocity and temperature distributions of both molten salt and coolant at the outlet of the distribution zone, as inlet of the core region, are produced. It can be observed that the outlet velocity profiles are proportional in magnitude to the inlet velocity ones with a similar shape. In addition, the results show that the heat transfer in the center region is enhanced due to the velocity distribution, which could compensate the power peak and flatten the temperature distribution for a higher power density.

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Section: The Small Modular Dual Fluid Reactormentioning

confidence: 99%

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

Liu

Luo

et al. 2020

Metals

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“…During the early MSR programs at Oak Ridge National Laboratory (ORNL), the integrated neutronic and fuel cycle analysis tools [2] were created and the associated processing plant codes [3] were developed. Including [2,3], the early analyses of the MSR system focus on the equilibrium state of the reactor where fission products accumulates in the fuel salt as the fuel salt undergoes irradiation [4][5][6][7][8]. With the advancement of powerful simulation tools, recent analysis focus has shifted to the isotopic composition variation of the fuel salt from the startup to the equilibrium condition of the MSR system by modifying neutron transport and depletion codes to account for the continuous feeds and removals in the MSR systems [9][10][11][12][13][14][15][16][17][18][19][20][21].…”

Section: Tablesmentioning

confidence: 99%

A Systems Processing Model for Molten Salt Reactors

Yoo

2018

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The chemistry group within the U.S. Department of Energy Molten Salt Reactor Campaign is developing a model for the molten salt reactor system for assessing the suitability of various used fuel processing schemes. In the long run, the developed model is expected to be a tool for better understanding the interplay between the components of the molten salt reactor system including uranium resources, the molten salt reactor, the used fuel processor (e.g., reprocessing plant), and waste management. In this regard, the report proposes a theoretical framework for integrating the various components of the molten salt reactor system. Rather than being buried in implementation details for seemingly heterogeneous components of the reactor system asking for various modeling techniques, this report proposes to approximate and integrate all components with a unified mathematical framework, a discrete-time linear system. An abstracted molten salt reactor system is given as an example to illustrate the effectiveness of the proposed theoretical framework. A fully developed molten salt reactor system model (based on the proposed framework) is expected to be beneficial for various objectives including the transient and equilibrium analysis of fuel cycle scenarios and the identification of potential technology bottlenecks.

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“…The concept of the dual fluid reactor (DFR) is based on a two‐fluid molten salt/liquid metal coolant fast breeder reactor proposed by researchers at Institut fuer Festkoerper‐Kernphysik. Research on this type of reactor concept traces back to the 1960s, including design studies of the molten salt breeder reactors performed at Oak Ridge National Laboratory (ORNL), and the ideas from Taube and Ligou for a molten plutonium chloride fast breeder reactor cooled by molten uranium chloride, which are milestones in this field. The original idea and the design description of the DFR can be found in the work reported in Huke et al, in which the differences between the DFR and other liquid salt– or liquid metal–cooled reactors are also discussed.…”

Section: Introductionmentioning

confidence: 99%

“…It is also different from MacPherson's or Robertson's two‐fluid reactor designs, which separate the salt into fissile (fuel salt) and fertile (blanket salt) separated flows. The DFR and Taube and Ligou's concept both use a chloride‐based molten fuel salt to harden the neutron spectrum. Yet the DFR does not combine heat removal and breeding into one single circuit, but separates the two functions into two independent circuits.…”

Section: Introductionmentioning

confidence: 99%

Steady-state reactor physics of the dual fluid reactor concept

Wang

Macián‐Juan

2018

Int J Energy Res

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Summary The dual fluid reactor (DFR) is a molten salt fast reactor developed by the Institut fuer Festkoerper‐Kernphysik (Berlin) on the basis of the Gen‐IV molten salt reactor and liquid metal–cooled reactor (sodium‐cooled fast reactor and lead‐cooled fast reactor) concepts. In the concept, the fuel is selected with the molten chloride salt and the coolant is the liquid lead. The article establishes the model for the reactor physics analysis and summarizes the preliminary performed calculations and the achieved results so far by the author on the steady‐state reactor physics behavior with the default fuel salt of U‐Pu mixture under zero‐flow‐velocity conditions. They include criticality calculation, neutron spectrum, spatial flux distribution, reaction rates and power distribution, nuclide importance, and temperature coefficient. The conclusion of the article evaluates the reactor physics behavior of the DFR concept and gives comments on the concept itself as well as on the future researches. The article is modified from a part of the PhD thesis of the first author (X. Wang).

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Molten plutonium chlorides fast breeder reactor cooled by molten uranium chloride

Cited by 29 publications

References 3 publications

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

A Systems Processing Model for Molten Salt Reactors

Steady-state reactor physics of the dual fluid reactor concept

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