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Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor
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What this work says
Outgoing claims: the papers this work cites, builds on, or argues with.
inferredcites →https://doi.org/10.1002/er.3371openalex-snapshot
Whole core analysis of molten salt breeder reactor with online fuel reprocessing
inferredcites →https://doi.org/10.1016/j.anucene.2012.10.017openalex-snapshot
Depletion analysis on long-term operation of the conceptual Molten Salt Actinide Recycler & Transmuter (MOSART) by using a special sequence based on SCALE6/TRITON
inferredcites →https://doi.org/10.1016/j.anucene.2013.08.002openalex-snapshot
Towards the thorium fuel cycle with molten salt fast reactors
inferredcites →https://doi.org/10.1016/j.anucene.2013.09.009openalex-snapshot
Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit
inferredcites →https://doi.org/10.1016/j.anucene.2014.08.014openalex-snapshot
Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributes
inferredcites →https://doi.org/10.1016/j.anucene.2014.08.024openalex-snapshot
The Serpent Monte Carlo code: Status, development and applications in 2013
inferredcites →https://doi.org/10.1016/j.anucene.2016.11.040openalex-snapshot
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
inferredcites →https://doi.org/10.1016/j.anucene.2017.10.040openalex-snapshot
Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations
inferredcites →https://doi.org/10.1016/j.anucene.2018.04.043openalex-snapshot
Fuel cycle and neutronic performance of a spectral shift molten salt reactor design
inferredcites →https://doi.org/10.1016/j.jnucmat.2013.06.026openalex-snapshot
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor
inferredcites →https://doi.org/10.1016/j.nucengdes.2009.12.033openalex-snapshot
Molten salt reactors: A new beginning for an old idea
inferredcites →https://doi.org/10.1016/j.pnucene.2004.11.001openalex-snapshot
Potential of thorium molten salt reactorsdetailed calculations and concept evolution with a view to large scale energy production
inferredcites →https://doi.org/10.1016/j.pnucene.2013.06.006openalex-snapshot
Investigation of the MSFR core physics and fuel cycle characteristics
inferredcites →https://doi.org/10.1016/j.pnucene.2014.02.014openalex-snapshot
The molten salt reactor (MSR) in generation IV: Overview and perspectives
inferredcites →https://doi.org/10.1051/rgn/20106095openalex-snapshot
Simulation Tools and New Developments of the Molten Salt Fast Reactor
inferredcites →https://doi.org/10.1080/00223131.2015.1062812openalex-snapshot
Equilibrium core design methods for molten salt breeder reactor based on two-cell model
inferredcites →https://doi.org/10.1088/1742-6596/1133/1/012026openalex-snapshot
Nuclear fuel optimization for molten salt fast reactor
inferredcites →https://doi.org/10.1088/issn.1742-6596openalex-snapshot
Journal of Physics: Conference Series
inferredcites →https://doi.org/10.13182/nt10-124openalex-snapshot
Monte Carlo Criticality Methods and Analysis Capabilities in SCALE
inferredcites →https://doi.org/10.13182/nt10-163openalex-snapshot
SCALE 6: Comprehensive Nuclear Safety Analysis Code System
inferredcites →https://doi.org/10.13182/nt11-3openalex-snapshot
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE
inferredcites →https://doi.org/10.13182/nt70-1openalex-snapshot
Experience with the Molten-Salt Reactor Experiment
inferredcites →https://doi.org/10.13182/nt8-2-118openalex-snapshot
Experience with the Molten-Salt Reactor Experiment
inferredcites →https://doi.org/10.2172/1432668openalex-snapshot
Integral Full Core Multi-Physics PWR Benchmark with Measured Data
inferredcites →https://doi.org/10.2172/4030941openalex-snapshot
CONCEPTUAL DESIGN STUDY OF A SINGLE-FLUID MOLTEN-SALT BREEDER REACTOR.
inferredcites →https://doi.org/10.2172/4741221openalex-snapshot
ROD: A NUCLEAR AND FUEL-CYCLE ANALYSIS CODE FOR CIRCULATING-FUEL REACTORS.
inferredcites →https://doi.org/10.2172/5285077openalex-snapshot
User's manual for the ORIGEN2 computer code
inferredcites →https://doi.org/10.2172/7157044openalex-snapshot
DIF3D: a code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems. [LMFBR]
inferredcites →https://doi.org/10.5281/zenodo.1196454openalex-snapshot
arfc/saltproc: Code for online reprocessing simulation of molten salt reactor with external depletion solver SERPENT
What points at this work
Incoming claims: where this work appears in other papers’ reference lists and arguments.
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Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors
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Transmutation of 135 Cs in a single‐fluid double‐zone thorium molten salt reactor
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Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop
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Effect of reprocessing on neutrons of a molten chloride salt fast reactor
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Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium
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Molten salt reactor physics: characterization, neutronic performance, multiphysics coupling, and reduced-order modeling
inferred← citeshttps://doi.org/10.1016/j.anucene.2019.107115openalex-snapshot
Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
inferred← citeshttps://doi.org/10.1016/j.anucene.2020.107656openalex-snapshot
Strategies for thorium fuel cycle transition in the SD-TMSR
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Neutronics design for molten salt accelerator-driven system as TRU burner
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Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
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Machine learning application to single channel design of molten salt reactor
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Whole core analysis of the single-fluid double-zone heavy water-moderated molten salt reactor (SD-HWMSR)
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SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems
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The influence of graphite moderator density on the neutronic performance and fuel economy of a Molten Salt Reactor
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inferred← citeshttps://doi.org/10.1016/j.anucene.2025.111257openalex-snapshot
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A strongly connected component-based block solver for accelerated multi-node flowing-fuel depletion calculations
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Possible impacts of molten salt reactors on the International Monitoring System
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Economic evaluation of thorium oxide production from monazite using alkaline fusion method
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Influences of reprocessing separation efficiency on the fuel cycle performances for a Heavy Water moderated Molten Salt Reactor
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Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2024.113049openalex-snapshot
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Neutronics and thermal-hydraulics coupled analysis on dimensional change and lifespan of graphite components in small modular molten salt reactor
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Robust controller design strategies with improved performance for MSBR core
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