Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling

Engel, J.R.; Bauman, H.F.; Dearing, J.F.; Grimes, W.R.; McCoy, H.E.; Rhoades, W.A.

doi:10.2172/5352526

Cited by 66 publications

(43 citation statements)

References 8 publications

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“…Recover the oxides by decantation and filtration. Hydrofluorinate the oxides into the purified melt of LiF-BeF 2 -ThF 4 , and reduce the melt with H 2 and reconstitute fuel with the desired UF 4 /UF 3 ratio [35].…”

Section: Selective Oxide Precipitation Processmentioning

confidence: 99%

Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes

Hirose¹

2021

Nuclear Power Plants - The Processes From the Cradle to the Grave

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A mixture of NaF-KF-UF 4 eutectic and NaF-KF-TRUF 3 eutectic containing heavy elements as much as 2.8 g/cc makes a fast-spectrum molten salt reactor based upon the U-Pu cycle available without a blanket. It does not object breeding but a stable operation without fissile makeup under practical contingencies. It is highly integrated with online dry chemical processes based on "selective oxide precipitation" to create a U-Pu cycle to provide as low as 0.01% leakage of TRU and nominated as the FFMSR. This certifies that the radiotoxicity of HLW for 1500 effective full power days (EFPD) operation can be equivalent to 405 tons of depleted uranium after 500 years cooling without Partition and Transmutation (P&T). A certain amount of U-TRU mixture recovered from LWR spent fuel is loaded after the initial criticality until U-Pu equilibrium but the fixed amount of 238 U only thereafter. The TRU inventory in an FFMSR stays at an equilibrium perpetually. Accumulation of spent fuel of an LWR for 55 years should afford to start up the identical thermal capacity of FFMSR and to keep operation hypothetically until running out of 238 U. Full deployment of the FFMSR should make the entire fuel cycle infrastructures needless except the HLW disposal site.Keywords: fast-spectrum fluoride molten salt reactor, high-level radioactive waste, structure of fuel salt, density of fuel salt, redox potential control, freezing behavior of fuel salt, selective oxide precipitation process, front-end processing dedicated to the MOX spent fuel, nuclear fuel cycle and associated wastes

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Section: Selective Oxide Precipitation Processmentioning

confidence: 99%

Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes

Hirose¹

2021

Nuclear Power Plants - The Processes From the Cradle to the Grave

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“…Some corrosion product can be oxidizer of other metals, for example, the corrosion product NiF 2 is the oxidizer of Cr through a reaction

Cr + {NiF}_{2 (d)} \to {CrF}_{2 (d)} + Ni

and therefore, it leads to Cr corrosion . The precipitation of corrosion products may lead to fouling at the HX and affect the heat‐transfer performance of the HX.…”

Section: Impurities Contamination Mechanisms and Available Removal mentioning

confidence: 99%

“…CrF 2ðdÞ þ Ni (2) and therefore, it leads to Cr corrosion. [54] The precipitation of corrosion products may lead to fouling at the HX and affect the heat-transfer performance of the HX. On the other hand, continuous corrosion will lead to structural material degradation.…”

Section: Source and Transportmentioning

confidence: 99%

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Zhang

2019

Energy Tech

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The fluoride salt‐cooled high‐temperature reactor (FHR) is one of the Gen. IV reactor concepts. Considering the complexity of salt chemistry, radiation risk, impurity‐induced material corrosion, and impurity‐induced solid precipitation, the salt chemistry should be well controlled. Therefore, molten salt cleanup systems are needed in operation. Based on the experience of molten salt reactors (MSRs) and available data, the present study identifies the types of impurities, their potential sources, and their impact in FHR primary coolants. Cleanup methods for each type of impurity and future research activities are also discussed.

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“…(5) MCODE (Xu et al, 2002), which uses MCNP neutron transport with ORIGEN2 (Ludwig and Renier, 1989) depletion in applications (Ahmad et al, 2015) to the denatured molten salt reactor (DMSR), (Engel et al, 1980), and (6) MCNP6 neutron transport with CINDER90 (MCNP6) depletion in applications to whole core (Park et al, 2015) and multi-zone (Jeong et al, 2016) MSR modeling and simulations.…”

Section: /57mentioning

confidence: 99%

Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE

Betzler

Powers

Worrall

2017

Annals of Nuclear Energy

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Current interest in advanced nuclear energy and molten salt reactor (MSR) concepts has enhanced interest in building the tools necessary to analyze these systems. A Python script known as ChemTriton has been developed to simulate equilibrium MSR fuel cycle performance by modeling the changing isotopic composition of an irradiated fuel salt using SCALE for neutron transport and depletion calculations. Improved capabilities in ChemTriton include a generic geometry capable of modeling multi-zone and multi-fluid systems, enhanced time-dependent feed and separations, and a critical concentration search. Although more generally applicable, the capabilities developed to date are illustrated in this paper in three applied problems: (1) simulating the startup of a thorium-based MSR fuel cycle (a likely scenario requires the first of these MSRs to be started without available 233 U); (2) determining the effect of the removal of different fission products on MSR operations; and (3) obtaining the equilibrium concentration of a mixed-oxide light-water reactor fuel in a two-stage fuel cycle with a sodium fast reactor. The third problem is chosen to demonstrate versatility in an application to analyze the fuel cycle of a non-MSR system. In the first application, the initial fuel salt compositions fueled with different sources of fissile material are made feasible after (1) removing the associated nonfissile actinides after much of the

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Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling

Abstract: NOTICE This document contains information of a preliminary nature. It is subject to revision or correction and therefore does not represent a final report.

Cited by 66 publications

References 8 publications

Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes

Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE

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