Thermofluid MHD studies in a model of Indian LLCB TBM at high magnetic field relevant to ITER

Swain, P. K.; Koli, Pratik; Ghorui, S.; Mukherjee, Pinaki; Deshpande, Arvind

doi:10.1016/j.fusengdes.2019.111374

Cited by 16 publications

(13 citation statements)

References 19 publications

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“…For the purpose of MHD calculations, the breeder modules can be assumed as perfectly insulating and only the bounding walls must be considered to estimate the equivalent wall conductivity. Geometrical parameters are consistent with those reported in [51], and are collected in Table 8. Thermo-physical properties of RAFMS and Li-Pb are evaluated at the reference temperature of 623 K and the flow is assumed to be purely isothermal.…”

Section: Sudden Cross-section Variationssupporting

confidence: 81%

“…In itself, this is not considered satisfactory to assess the reliability of the code, thus more complex systems are analysed, i.e., two Test Blanket Modules (TBMs) concepts, to demonstrate the capability of the various subroutines of the MHD module to operate together and produce physical results. For this purpose, the numerical analysis performed by Swain et al in [51] on the Lithium Lead Ceramic Breeder (LLCB) TBM at fusion-relevant magnetic field intensity is repeated with RELAP5 and an excellent quantitative agreement is found on the total pressure drop and local pressure profile.After that, the experimental data produced by the campaign carried out by KIT researchers on a Helium Cooled Lithium Lead (HCLL) TBM mock-up have been considered to further demonstrate the performance of the code against a more realistic benchmark [33]. The module geometry is simulated with the code and, again, an excellent agreement is found in terms of pressure drop prediction.…”

Section: Verification and Validation (Vandv)mentioning

confidence: 99%

“…Furthermore, also the total 3D loss is well predicted by the code, that provides accurate results if compared with the ones of Equation (19). [51].…”

Section: Sudden Cross-section Variationsmentioning

confidence: 99%

“…Numerical MHD studies at high magnetic field for such complex configurations are rare and they provide precious results for the system codes verification phase. In [51], an exhaustive thermal-hydraulic analysis is performed; for the aim of this work, however, the attention is focused on the pressure drop outcomes.…”

Section: Sudden Cross-section Variationsmentioning

confidence: 99%

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Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

et al. 2021

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Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and a moving electro-conductive fluid, are crucial for the design of magnetic-confinement fusion reactors and, specifically, for the design of the breeding blanket concepts that adopt liquid metals (LMs) as working fluids. Computational tools are employed to lead fusion-relevant physical analysis, but a dedicated MHD code able to simulate all the phenomena involved in a blanket is still not available and there is a dearth of systems code featuring MHD modelling capabilities. In this paper, models to predict both 2D and 3D MHD pressure drop, derived by experimental and numerical works, have been implemented in the thermal-hydraulic system code RELAP5/MOD3.3 (RELAP5). The verification and validation procedure of the MHD module involves the comparison of the results obtained by the code with those of direct numerical simulation tools and data obtained by experimental works. As relevant examples, RELAP5 is used to recreate the results obtained by the analysis of two test blanket modules: Lithium Lead Ceramic Breeder and Helium-Cooled Lithium Lead. The novel MHD subroutines are proven reliable in the prediction of the pressure drop for both simple and complex geometries related to LM circuits at high magnetic field intensity (error range ±10%).

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Section: Sudden Cross-section Variationssupporting

confidence: 81%

Section: Verification and Validation (Vandv)mentioning

confidence: 99%

“…Furthermore, also the total 3D loss is well predicted by the code, that provides accurate results if compared with the ones of Equation (19). [51].…”

Section: Sudden Cross-section Variationsmentioning

confidence: 99%

Section: Sudden Cross-section Variationsmentioning

confidence: 99%

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Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

et al. 2021

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“…Early generation fusion reactors will operate with modest FW loads. In fact, different types of ferritic martensitic steels are continuing subject of recent works, such as utilizations austenitic SS in Russian studies, 42 reduced activation ferritic martensitic steel, 43 Korean developed ferritic martensitic steel 44 and India‐specific ferritic martensitic steel 45 . Under consideration of all these aspects, SS304 is selected as the FW material in a group of the calculations to be on conservative side.…”

Section: Numerical Calculationsmentioning

confidence: 99%

Study on the fusion reactor performance with different materials and nuclear waste actinides

Şahi̇n

Sahiner

et al. 2020

Int J Energy Res

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Summary In this study, both pure fusion blanket and fusion‐fission (hybrid) reactor blanket performance were investigated and discussed separately in two phases. In the first phase, a Monte Carlo radiation damage analysis has been performed for stainless steel (SS304, SS316, and oxide dispersion strengthened (ODS)), molybdenum, vanadium, and tungsten as the first wall (FW) materials, in combination with selected tritium breeders. The main technical parameters for fusion reactors, such as tritium breeding ratio, fusion energy multiplication factor (M), displacement per atom (DPA), and gas production (He, H) have been evaluated. All numerical calculations have been carried out in spherical geometry with MCNP6 code package using continuous energy cross‐sections from the ENDF/B‐VIII.0 library, except DPA calculations. Instead of the ENDF/B‐VIII.0 library, the 30‐group CLAW‐IV library was employed for DPA calculations. Structural material selection for the FW respect to radiation damage limits and reactor performance for energy production and tritium has been concluded. Conventional thermal reactors, such as light water reactors andCanada Deuterium Uranium (CANDU) reactors are producing substantial quantities of transuranic elements, which represent serious nuisance and permanent hazard potential. On the other hand, they become fissionable material under high energetic fusion neutron irradiation and multiply the fusion energy. In the second phase, the investigations are extended to the incineration of minor actinides (MA) in the fusion‐fission (hybrid) mode. The transmutation history of MA nuclear waste is included. MA are added into the first zone of the coolant in TRi‐structural ISOtropic particle TRISO particles with a volume fraction of 6%. The transformation scenario for all MA by SS 304 steel FW is practically the same as with the ODS FW.

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Influence of PbLi hydraulic path and integration layout on MHD pressure losses

Tassone

Caruso

Nevo

2020

Fusion Engineering and Design

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Thermofluid MHD studies in a model of Indian LLCB TBM at high magnetic field relevant to ITER

Cited by 16 publications

References 19 publications

Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

Study on the fusion reactor performance with different materials and nuclear waste actinides

Influence of PbLi hydraulic path and integration layout on MHD pressure losses

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