Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor

Rykhlevskii, Andrei; Bae, Jin Whan

doi:10.1016/j.anucene.2019.01.030

Cited by 46 publications

(21 citation statements)

References 18 publications

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“…Detailed fuel mass composition is given in Table 2. [22,23]. It is capable to absorb neutron, nevertheless, and transmute into U-235 then subsequently U-236, when neutron absorbed by U-235 did not fission.…”

Section: Methodsmentioning

confidence: 99%

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Dwijayanto

Husnayani²,

Zuhair³

2019

urania

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CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises low enriched uranium (LEU)-based fuel, which is the most viable option at the moment, it is possible for RDE to utilise other fuel, for example thorium-based and possibly even plutonium-based fuel. Different fuel yields different spent fuel characteristics, so it is necessary to identify the characteristics to understand and evaluate their handling and interim storage. This paper provides the study on the characteristics of thorium-fuelled RDE spent fuel, assuming typical operational cycle. ORIGEN2.1 code is employed to determine the spent fuel characteristics. The result showed that at the end of the calculation cycle, each thorium-based spent fuel pebble generates around 0,627 Watts of heat, 28 neutrons/s, 8.28x1012 photons/s and yield 192.53 curies of radioactivity. These higher radioactivity and photon emission possibly necessitate different measures in spent fuel management, if RDE were to use thorium-based fuel. Tl-208 activity, which found to be emitting potentially non-negligible strong gamma emission, magnified the requirement of proper spent fuel handling especially radiation shielding in spent fuel cask.Keywords: RDE, spent fuel, thorium, HTGR, Tl-208.

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Section: Methodsmentioning

confidence: 99%

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Dwijayanto

Husnayani²,

Zuhair³

2019

urania

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“…Serpent-2 for analyzing fuel cycle performance of MSRs [295,296]. It allows for generic geometry modeling, multi-flow capabilities, time-dependent feed and removal, and user-specified separation efficiencies.…”

Section: Rykhlevskii Et Al Developed the Open Source Tool Saltproc Which Expands The Capabilities Ofmentioning

confidence: 99%

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Clark¹,

Luxat²,

Higgins³

et al. 2020

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“…3,4 The inherent characteristics of the liquid fuel make it can be directly extracted from MSR or added to MSR, so this reactor can achieve online-fuel reprocessing without shutdown. 5 These features of MSR are particularly suitable for the application of thorium in nuclear energy. 6 As a result, MSR has also been recognized as the best type for Th-U fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

Evaporation behavior of ²³³Pa in FLiBeZr molten salt

et al. 2022

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Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor

Cited by 46 publications

References 18 publications

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Evaporation behavior of ²³³Pa in FLiBeZr molten salt

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Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor

Cited by 46 publications

References 18 publications

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Characteristics of Radionuclides on Thorium-Cycle Experimental Power Reactor Spent Fuel.

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Evaporation behavior of 233Pa in FLiBeZr molten salt

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Evaporation behavior of ²³³Pa in FLiBeZr molten salt