Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY

Hu, Tianliang; Cao, Liangzhi; Wu, Hongchun; Du, Xianan; He, Maogang

doi:10.1016/j.anucene.2017.05.002

Cited by 25 publications

(5 citation statements)

References 20 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…TANSY has been specially developed to study the characteristics of MSRs. As described in our previous paper, 9,10 TANSY already has the capability for the multi‐physics simulation of MSRs at steady‐state, and in this paper the code was extended by adding a depletion solver for the fuel‐cycle analysis. The neutron reaction rates is calculated by the coupled neutronics and thermal‐hydraulics simulation solver which was built using the OpenFOAM finite volume toolkit, 11,12 and the depletion solver determines the evolution of the material composition by solving the Bateman equation.…”

Section: Theory and Methodsmentioning

confidence: 99%

“…The neutron diffusion solver together with the coupled code was benchmarked against some benchmark problems and applied to some MSR designs as described in our previous papers 9,10,16,17 …”

Section: Theory and Methodsmentioning

confidence: 99%

“…So further studies are still necessary to analyze the effect of the special phenomena caused by the fluid fuel on the fuel cycle characteristics of MSRs. In this content, the TANSY 9 code system is developed for performing fuel cycle analysis, coupled neutronics and thermal‐hydraulics analysis and simulation of various fluid‐fuel systems. It has the ability to accurately model the behavior of MSRs, including the flow of the nuclides, the drift of DNPs, the online reprocessing, and the online feeding rate control to maintain criticality.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Cao

Yang

et al. 2020

Int J Energy Res

Self Cite

View full text Add to dashboard Cite

Summary The main feature of Molten Salt Reactors (MSRs) is the use of fluid fuel which continuously flows through the primary circuit. The adoption of fluid fuel in the MSRs leads to strong coupling between the neutronics, thermal‐hydraulics, fuel‐cycle, and salt reprocessing. To accurately model the special phenomena caused by fluid fuel, a code system named TANSY has been developed. The code system has the capability to simulate the online refueling, the online reprocessing, the flow of delayed neutron precursors and the drift of nuclides accurately. To verify the fuel‐cycle analysis capability of the code, neutronics benchmark problem of the Molten Salt Fast Reactor was simulated. The numerical solutions calculated by TANSY agree well with the reference results. After verification, it is applied to analyze the thermal feedback effect and nuclides flow effect on the characteristics of the fast‐spectrum MSRs. From the numerical results, it has been concluded that both effects have a small influence less than 1% on the time evolution of the actinides. But it is also found that the thermal feedback effect has a relatively high impact about 8% on the feeding rate of the fissile nuclide because of its influence on the criticality and neutron spectrum. The nuclides flow effect has a relatively high impact about 5% on the time evolution of the nonsoluble fission products such as 135Xe in the core because of the high reprocessing rate of such elements.

show abstract

Section: Theory and Methodsmentioning

confidence: 99%

“…The neutron diffusion solver together with the coupled code was benchmarked against some benchmark problems and applied to some MSR designs as described in our previous papers 9,10,16,17 …”

Section: Theory and Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Cao

Yang

et al. 2020

Int J Energy Res

Self Cite

View full text Add to dashboard Cite

show abstract

“…Penelitian ini membuka jalan bagi pengembangan MSFR dengan siklus bahan bakar uranium-plutonium. Hu et al (2017) telah melakukan analisis neutronik sekaligus termal-hidrolik pada suatu desain konseptual MSFR yang disebut MOSART (Molten Salt Actinide Recycler and Transmuter) berdaya 2400 MWth. Perkasa (2018) telah melakukan analisis neutronik MSFR berdaya termal 3000 MWth dengan variasi konfigurasi bahan bakar dan didapatkan hasil bahwa konfigurasi penggunaan bakar Th + U-233 memiliki koefisien multiplikasi efektif yang lebih konstan sepanjang masa operasi reaktor.…”

Section: Pendahuluanunclassified

Analisis Ukuran Teras dan Rasio H/D pada Molten Salt Fast Reactor dalam Tinjauan Neutronik

Azurah¹,

Fitriyani²,

Permana³

2021

JFU

View full text Add to dashboard Cite

Telah dilakukan simulasi pada Molten Salt Fast Reactor (MSFR) berdaya 100 MWth untuk menganalisis pengaruh bentuk dan ukuran teras terhadap kinerja neutronik. Penelitian ini menggunakan kode komputasi SRAC (Standard Thermal Reactor Analysis Code System) yang dikembangkan oleh JAEA (Japan Atomic Energy Agency). Analisis dilakukan terhadap 9 variasi bentuk dan ukuran teras pada teras MSFR silinder dua dimensi (2-D) dengan peninjauan terhadap parameter neutronik yaitu faktor multiplikasi efektif,. Perhitungan neutronik dilakukan dengan mengatur komposisi bahan bakar dalam teras. Hasil perhitungan menunjukkan bahwa seluruh variasi model teras menghasilkan nilai faktor multiplikasi efektif di atas 1,0 pada awal masa operasi reaktor. Model teras C1 (volume teras 6 m3, bentuk teras tall) merupakan model teras yang paling baik dalam mempertahankan kekritisan reaktor dengan reactivity swing sebesar 0,0721.Â A simulation of 100 MWth Molten Salt Fast Reactor (MSFR) has been carried out to analyze the influence of core shape and size to its neutronic performance. This research used computational code SRAC (Standard Thermal Reactor Analysis Code System) developed by JAEA (Japan Atomic Energy Agency). Analysis has been done to 9 variation of core shape and size on two-dimensional (2-D) cylinder ofÂ MSFR in terms of neutronic parameter such as the effective multiplication factor with arrangement of fuel composition. The neutronic calculation shows that all of core type bring out the value of effective multiplication factor above 1,0Â in the beginning of reactor operation. C1 is the most optimum core model because it can maintain the criticality of the core reactor with reactivity swing value of 0,0721.

show abstract

“…Fiorina discussed the importance of the design enhancement needed for the fuel velocity and temperature of the MSFR core [5]. Hu developed a code to simulate the Molten Salt Reactors and reported 1200 K maximum temperature [6]. Li showed that The range of the temperature of the MSFR design is between the salt freezing point (838 K) and the melting point of the nickel alloy used in the core structure (approximately 1600 K) and these points must be considered as the margin points in the steady state and the transients analysis [5,7].…”

Section: Introductionmentioning

confidence: 99%

Safety Enhancement in the Molten Salt Fast Reactor (MSFR)

MOHAMED,

MOUSTAFA,

Mohamed

et al. 2023

Engineering Research Journal (Shoubra)

View full text Add to dashboard Cite

This study presents a new modification for the cooling circuit design of the Molten Salt Fast Reactor MSFR to solve the problem of high temperatures in the hot spots regions that affect the reactor safety. These high temperature regions appear as a result of the salt recirculation of the liquid fuel. This problem causes a decrease in the delayed neutron fraction value βeff.. This decrease in βeff. reduces the safety of the reactor because it shifts it more close to the prompt critical state. The new modification depends on distributing the flow between the side and the centre by adding a coolant circuit passes through the core centre from the bottom to the top. At the end of this study we see that this new design moderated the hot spots and reduced the maximum temperature to about 1120 k. This value is greater than the core outlet temperature by about 77 k and smaller than the maximum temperature of the benchmark design by about 160 k. The design also reduced the salt velocity from the benchmark value 3.9 m/s to the value 2.38 m/s.

show abstract

Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY

Cited by 25 publications

References 20 publications

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Analisis Ukuran Teras dan Rasio H/D pada Molten Salt Fast Reactor dalam Tinjauan Neutronik

Safety Enhancement in the Molten Salt Fast Reactor (MSFR)

Contact Info

Product

Resources

About