Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

Dwijayanto, R. Andika Putra; Hermawan, Dedy Prasetyo

doi:10.17146/tdm.2020.22.2.5893

Cited by 4 publications

(2 citation statements)

References 15 publications

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“…Considering the front-end of nuclear power generation, the option is to replace uranium as a primary fuel to thorium [8][9][10][11]. Since thorium has smaller atomic and mass numbers than uranium, the former must capture at least seven successive neutron captures prior to transmuting into TRU.…”

Section: Introduction mentioning

confidence: 99%

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

Dwijayanto,

Miftasani,

Harto

2023

Tri Dasa Mega

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The accumulation of spent nuclear fuel (SNF) is presently considered as a hindrance of the massive deployment of nuclear power plant, especially regarding the transuranic (TRU) elements. Eliminating TRU through transmutation is one of the most feasible alternative as a technical solution to solve the issue. This study explores the possibility of TRU transmutation using molten salt reactor (MSR) in a heterogeneous configuration, where a solid TRU is coated inside the fuel channel filled with liquid salt fuel. Such configuration is proposed to allow higher TRU loading into fluoride salt mixture without compromising the safety of the reactor. TRU coating was applied in consecutively outward radial fuel channel layers with coating thicknesses of 2.5 mm and 5 mm. Calculation was performed using MCNP6.2 radiation transport code and ENDF/B-VII.0 neutron cross section library. From the results, TRU coating with smaller thickness and positioned closer to the centre of the core exhibit higher transmutation efficiency due to exposure to higher neutron flux. Highest transmutation efficiency was achieved at 67.93% after 160 days of burnup. This shows a potential of achieving highly efficient TRU using heterogeneous configuration in MSR core.

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Section: Introduction mentioning

confidence: 99%

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

Dwijayanto,

Miftasani,

Harto

2023

Tri Dasa Mega

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“…It offers many advantages compared to conventional light water reactors (LWR), such as passive safety systems, atmospheric operating pressure, high operating temperature, and no fuel fabrication requirement. Its online reprocessing capability enables MSR to achieve breeding in thermal spectrum using thorium fuel cycle while maintaining high fuel burnup [1][2][3].…”

Section: Introduction mentioning

confidence: 99%

Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

et al. 2021

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Passive Compact Molten Salt Reactor (PCMSR) is a thermal breeder molten salt reactor (MSR) developed in Universitas Gadjah Mada, Indonesia, run in thorium fuel cycle. Its design was initially developed using deterministic code SRAC2006 but has never been compared with other codes. This paper attempts to compare PCMSR neutronic design using Monte Carlo codes MCNP6 and Serpent-2 with ENDF B/VII.0 continuous neutron cross-section library. The reactor was run in a pure thorium fuel cycle with lithium fluoride as its carrier salt. The analyzed parameters were effective multiplication factor (k eff ), temperature coefficient of reactivity (TCR), void coefficient of reactivity (VCR), and conversion ratio (CR). The result shows that there are several important discrepancies between the original calculation and this research. The Monte Carlo calculations implied that PCMSR core was able to be critical using lower fissile concentration than previously designed, but failed to reach CR above unity. While the TCR value was found to be negative, the VCR value was positive up until the 10 % void fraction. The PCMSR core suffered from ineffective neutron moderation and high neutron leakage. These findings imply that the previous PCMSR neutronic design is inaccurate. For PCMSR to be able to operate as a thermal breeder MSR, geometrical modifications must be performed to improve neutron moderation and reduce neutron leakage.

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Preliminary assessment of solid TRU layer for transmutation in molten salt reactor

Dwijayanto,

Harto,

Khakim

2023

CHEMISTRY BEYOND BORDERS: INTERNATIONAL CONFERENCE ON PHYSICAL CHEMISTRY: The 1st Annual Meeting of the Physical Chemistry Divi

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Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

Cited by 4 publications

References 15 publications

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

Preliminary assessment of solid TRU layer for transmutation in molten salt reactor

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