Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Tran, Vinh Thanh; Tran, Hoai-Nam; Nguyen, Huu Tiep; Hoang, Van-Khanh; Ha, Pham Nhu Viet

doi:10.1155/2019/5769147

Cited by 8 publications

(6 citation statements)

References 18 publications

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“…Therefore, Am-241 is more likely to capture neutron, and consequently transmute the fastest. This result is consistent with previous studies in other type of reactors [10,11].…”

Section: Ma Incinerationsupporting

confidence: 94%

“…This efficiency only accounts for fissioned MA, not considering MA isotopes that were transmuted instead of fissioned. The efficiency is not too dissimilar with other references [11,24], but the required time was around twice as long.…”

mentioning

confidence: 49%

“…Fast reactor is usually preferred to incinerate MA and considered in many studies [1][2][3][4][5][6][7]. Nevertheless, MA incineration can also be performed in thermal reactor, both research reactor [8] and power reactor [9][10][11][12][13].…”

Section: Introductionmentioning

confidence: 99%

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Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation

Dwijayanto

Alfarisie

2021

gnd

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Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.

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“…Therefore, Am-241 is more likely to capture neutron, and consequently transmute the fastest. This result is consistent with previous studies in other type of reactors [10,11].…”

Section: Ma Incinerationsupporting

confidence: 94%

mentioning

confidence: 49%

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Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation

Dwijayanto

Alfarisie

2021

gnd

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“…In nuclear reactor, transmutation can be performed in both research reactor [17,18] and power reactor with various types of fission reactors. Conventional light water reactors (LWRs) have been studied to transmute TRU, either by using TRU wholly as a fuel rod [6,[19][20][21] or as coating layer [7,22]. Combining TRU with thorium ensures negative yield of TRU [23], due to the reason mentioned previously.…”

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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“…In a previous study [17], the feasibility of MA transmutation in VVER-1000 LEU fuel assembly [18] as burnable poison was studied and the results showed that the total MA transmutation rate of ~20% could be obtained. However, only the MA vector of the VVER-440 spent fuel was considered.…”

Section: Introductionmentioning

confidence: 99%

Study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions

Tran¹,

Vu²,

Hoang³

et al. 2021

Nucl. Sci. and Tech.

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The feasibility of transmutation of minor actinides recycled from the spent nuclear fuel in the VVER-1000 LEU (low enriched uranium) fuel assembly as burnable poison was examined in our previous study. However, only the minor actinide vector of the VVER-440 spent fuel was considered. In this paper, various vectors of minor actinides recycled from the spent fuel of VVER-440, PWR-1000, and VVER-1000 reactors were therefore employed in the analysis in order to investigate the minor actinide transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions. The comparative analysis was conducted for the two models of minor actinide loading in the LEU fuel assembly: homogeneous mixing in the UGD (Uranium-Gadolinium) pins and coating a thin layer to the UGD pins. The parameters to be analysed and compared include the reactivity of the LEU fuel assembly versus burnup and the transmutation of minor actinide nuclides when loading different minor actinide vectors into the LEU fuel assembly.

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Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Cited by 8 publications

References 18 publications

Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation

Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation

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

Study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions

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