Development of a Molten Salt Reactor specific depletion code MODEC

Xia, Siyou; Chen, Jingen; Guo, Wenbin; Cui, De-Yang; Han, Jianlong; Wu, Jianhui; Xiang-Zhou, Cai

doi:10.1016/j.anucene.2018.09.032

Cited by 26 publications

(9 citation statements)

References 16 publications

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“…For the depletion calculation of MSR, an in-house program called TMCBurnup, which couples the TRITON in the SCALE6.1 program [ 31 ] and a novel depletion code MODEC, was developed in our previous work [ 32 , 33 ]. The flowchart of TMCBurnup is shown in Figure 2 [ 33 ].…”

Section: General Description Of Mcfr and Analysis Methodologymentioning

confidence: 99%

Minor Actinides Transmutation Performance in a Closed Th–U Cycle Based on Molten Chloride Salt Fast Reactor

Chen

Cui

et al. 2022

Materials

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The molten chloride salt fast reactor (MCFR) with a closed Th–U fuel cycle is receiving more and more attention due to its excellent performance, such as high solubility of actinides, superior breeding capacity, and good inherent safety. In this work, the neutronics performances for different minor actinides (MA) loadings and operation modes are analyzed and discussed based on an optimized MCFR. The results indicate that online continuous reprocessing can significantly increase the transmutation performance of MAs. In addition, MA loadings have an obvious effect on the neutronics characteristics of the MCFR, and it is helpful for improving the MA transmutation capability and 233U breeding performance, simultaneously. When MA = 5 mol%, the average annual MA transmutation mass and incineration mass can achieve about 53 kg and 13 kg, respectively, and the corresponding annual net production of 233U is 250 kg. When MA = 33.5 mol%, the annual MA transmutation mass and incineration mass can be about 310 kg and 77 kg, respectively, and the corresponding annual net production of 233U is 349 kg. However, when the MA loadings exceed 10%, the corresponding keff will exceed 1.1 for decades, even if only Th is continuously fed online. The results also indicate that the transmutation ratio (TR) and incineration ratio (IR) of MA increase and reach maximum values in the first decades for all the different MA loadings, which means MA may be fed into the fuel salt to improve its transmutation capability. Moreover, though MA loading will increase the level of radiotoxicity of the core in the early stage of burnup, the radiotoxicity of MA will drop rapidly after a brief rise during the operation. It can also be found that the temperature coefficient of reactivity (TCR) of all different MA loadings can be negative enough to maintain the safety of the MCFR during the whole operation, although it decreases in the beginning of life (BOL) with the increasing MA loading. Furthermore, the evolution of an effective delayed neutron fraction (EDNF) is also researched and discussed, and the EDNF varies most significantly when loading MA = 35.5 mol%, with a range of 273 to 310 pcm over the entire 100 years of operation.

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Section: General Description Of Mcfr and Analysis Methodologymentioning

confidence: 99%

Minor Actinides Transmutation Performance in a Closed Th–U Cycle Based on Molten Chloride Salt Fast Reactor

Chen

Cui

et al. 2022

Materials

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“…Namun demikian, kombinasi kedua paket program ini belum pernah digunakan untuk reaktor jenis Molten Salt Reactor (MSR). Kajian kritikalitas reaktor MSR banyak dilakukan dengan paket program berbasis Monte Carlo [7,8]. Meskipun demikian beberapa peneliti ada yang menggunakan metode deterministik [9,10].…”

Section: Pendahuluanunclassified

Analisis Akurasi Paket Program Wimsd-5b/Citation Dalam Perhitungan Kritikalitas Reaktor Msre Accuration Analysis of the Wimsd-5b/Citation Codes on the Criticality Calculation of the Msre Reactor

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Tamaza²,

Sid'qon³

2021

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Paket program WIMSD-5B/CITATION telah digunakan sebagai perangkat analitik kekritisan berbagai jenis reaktor dan memberikan hasil yang memuaskan. Meskipun demikian, paket program ini belum pernah digunakan untuk menganalisis kekritisan reaktor jenis MSR (Molten Salt Reactor). Dalam penelitian ini program WIMSD-5B/CITATION dianalisis akurasinya untuk menghitung kritikalitas reaktor MSRE (Molten Salt Reactor Experiment), yaitu reaktor MSR yang pernah dioperasikan sebagai fasilitas eksperimen. Tujuan penelitian ini adalah untuk mengetahui akurasi WIMSD-5B/CITATION untuk menghitung kritikalitas bahan bakar Tipe C di reaktor MSRE. Kritikalitas teras reaktor MSRE dihitung dengan 6 kelompok energi neutron dengan model geometri R-Z. Hasil perhitungan menunjukkan model sel yang menempatkan celah di tengah grafit (Model 1) lebih baik dibanding dengan sel yang menempatkan celah bahan bakar di luar grafit (Model 2). Namun demikian perbedaan relatif antara hasil perhitungan dan n hasil eksperimen masih tinggi yaitu 7,23%. Akurasi perhitungan kritikalitas didominasi oleh faktor model geometri sel dan teras. Pengaruh signifikan juga bersumber dari data jumlah void dan komposisi pengotor Li-6. Hasil penelitian juga menunjukkan bahwa fluks neutron dan faktor puncak daya radial di teras MSRE sangat sensitif terhadap model sel bahan bakar.

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“…MODEC has a strong capability for accurately tracking the evolution of isotopes within and outside of the core to ensure the accuracy of calculation. 25 Besides, to solve the depletion equation two depletion algorithms are embedded: the transmutation trajectory analysis and the Chebyshev rational approximation method. In addition, the fictive decay constant method is applied to simulate the online reprocessing.…”

Section: Iib Calculation Toolmentioning

confidence: 99%

“…Compared with ORIGEN-S, the validity of the performance of MODEC in burnup calculations with online reprocessing and continuously refueling is proved. 25 The flowchart of TMCBurnup is shown in Fig. 2.…”

Section: Iib Calculation Toolmentioning

confidence: 99%

Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor

Xia

Chen

et al. 2020

Nuclear Science and Engineering

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The molten chloride salt fast reactor (MCFR) with Th-U fuel cycle is attracting more and more attention because of its excellent performance, such as high solubility of actinides, superior breeding capacity, low waste production, and high inherent safety. First of all, the breeding capability of an MCFR at equilibrium state was optimized by an in-house automated optimization program. Based on an optimized MCFR, an investigation of Th-U cycle performance was performed. Due to the lack of available 233 U in nature, transuranium (TRU), low-enriched uranium (LEU), and Pu were employed as the startup fissile materials, and two different transition scenarios, a breeding and burning (B&B) scenario and a pre-breeding and burning (PBB) scenario were studied. The results show that the breeding performance in an MCFR is attractive and that the Th-U fuel transition can be achieved smoothly by using LEU, Pu, or TRU as startup fissile materials. In the B&B scenario, the average net 233 U production rate in the LEU-started, TRU-started, and Pu-started modes during 200-year operation is 374, 321, and 323 kg/a, respectively, at the reprocessing rate of 200 L/day. While in the PB&B scenario the average annual 233 U production is about 570 kg for all startup cases at a reprocessing rate of 40 L/day, and the corresponding doubling time is about 9.6 years. Besides, the values of the fuel Doppler coefficient and density coefficient are negative, and the total temperature coefficient of reactivity in all scenarios is below −8 pcm/K. In addition, the value of radiotoxicity of the Th-U cycle in an MCFR is lower than that in other molten salt reactors like the molten-salt breeder reactor and the molten fluoride salt reactor due to the lower buildup of fission products and TRU under its hard spectrum.

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Development of a Molten Salt Reactor specific depletion code MODEC

Cited by 26 publications

References 16 publications

Minor Actinides Transmutation Performance in a Closed Th–U Cycle Based on Molten Chloride Salt Fast Reactor

Minor Actinides Transmutation Performance in a Closed Th–U Cycle Based on Molten Chloride Salt Fast Reactor

Analisis Akurasi Paket Program Wimsd-5b/Citation Dalam Perhitungan Kritikalitas Reaktor Msre Accuration Analysis of the Wimsd-5b/Citation Codes on the Criticality Calculation of the Msre Reactor

Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor

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