Please use this identifier to cite or link to this item: http://hdl.handle.net/10603/279561
Title: Coupled field finite element analyses for the design of fusion reactor components against transient plasma induced electromagnetic loads
Researcher: Ravi, P. R.
Guide(s): Sankhavara, C. D.
Keywords: Engineering and Technology,Engineering,Engineering Mechanical
Fusion Reactor
IN-DEMO
ITER
Plasma
Plasma Instabilities
PPCS
SST-1
Tokamak
VDE
University: RK University
Completed Date: 29/01/2020
Abstract: quotFusion Energy is considered to be the most promising energy source for the next generation. Based on this, 35 nations across the globe collaborated to build and operate the biggest fusion experiment, namely, the ITER project. Other running machines such as the TFTR(USA); JET(UK); JT-60-SA(Japan); SST-1(India); EAST(China); and KSTAR(Korea), are targeted towards achieving and proving magnetic confinement process. Presently, Demonstrative (DEMO) Power Plants in the ranges of 1 5 GW considered as the next generation option of tapping fusion energy. newlineThe research work embodied in this thesis aims at preparing a detailed theoretical work in solving sets of equations to arrive at the variables of reactor physics of DEMO Power plants to yield various plasma and machine parameters, and engineering layouts. The results obtained for many reactors like ITER (1000 MW) in France; European Power Plants PPCS(A 5000 MW), PPCS(B 3600 MW), PPCS(C 2410 MW), PPCS(D 2530 MW), and IN-DEMO (3300 MW) in India are compared with the corresponding published data of the respective reactors and found to be in close agreements. newlineXI newlineFurther, the research work focuses on delivering a method of Design by Analysis (DBA) on a proposed Single Model Concept to analyze various reactor operating conditions for plasma instabilities like vertical displacement events (VDE) and disruptions for both ITER as well as SST-1 tokamaks. A small scale Tokamak Simulating Experiment (TSE) to estimate plasma-induced currents (typically about 2kA) on a toroidal vessel are experimentally measured using Rogowski coils is conducted to validate the concept of DBA methods. newlineThe present work includes coupled-field electromagnetic analysis in DBA methods to solve the VDE induced disruption of the ITER case study where peak induced currents of 13.7 MA are obtained on the double-wall vacuum vessel, when compared to published values of 13.8 MA, at 44 milliseconds. In SST-1 case study, the total induced currents on vessel and cryostat due to VDE and disruption cases are est
Pagination: -
URI: http://hdl.handle.net/10603/279561
Appears in Departments:Faculty of Technology

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01_cover page.pdfAttached File18.32 kBAdobe PDFView/Open
02 certificate - ravi pragash.pdf167.56 kBAdobe PDFView/Open
03 declaration- ravi pragash.pdf194.67 kBAdobe PDFView/Open
05_table of contents.pdf112.69 kBAdobe PDFView/Open
06_list of tables.pdf351.45 kBAdobe PDFView/Open
07_list of figures.pdf116.58 kBAdobe PDFView/Open
08_ list of abbreviations.pdf13.15 kBAdobe PDFView/Open
09_abstract.pdf180.36 kBAdobe PDFView/Open
10_graphical abstract.pdf876 kBAdobe PDFView/Open
11_chapter 1.pdf557.27 kBAdobe PDFView/Open
12_chapter 2.pdf406.27 kBAdobe PDFView/Open
13_chapter 3.pdf122.82 kBAdobe PDFView/Open
14_chapter 4.pdf1.48 MBAdobe PDFView/Open
15_chapter 5.pdf1.89 MBAdobe PDFView/Open
16_chapter 6.pdf247.56 kBAdobe PDFView/Open
17_list of publication.pdf335.48 kBAdobe PDFView/Open
18_references.pdf138.15 kBAdobe PDFView/Open
19_appendix.pdf88.81 kBAdobe PDFView/Open
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