Coupled field finite element analyses for the design of fusion reactor components against transient plasma induced electromagnetic loads

dc.contributor.guideSankhavara, C. D.
dc.coverage.spatialMechanical Engineering
dc.creator.researcherRavi, P. R.
dc.date.accessioned2020-03-03T06:56:31Z
dc.date.available2020-03-03T06:56:31Z
dc.date.awarded14/10/2020
dc.date.completed29/01/2020
dc.date.registered05/01/2014
dc.description.abstractquotFusion 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
dc.description.noteReferences p. 108-118, Appendix p. 121
dc.format.accompanyingmaterialNone
dc.format.dimensions-
dc.format.extent-
dc.identifier.urihttp://hdl.handle.net/10603/279561
dc.languageEnglish
dc.publisher.institutionFaculty of Technology
dc.publisher.placeRajkot
dc.publisher.universityRK University
dc.relationNo. of References 104
dc.rightsuniversity
dc.source.universityUniversity
dc.subject.keywordEngineering and Technology,Engineering,Engineering Mechanical
dc.subject.keywordFusion Reactor
dc.subject.keywordIN-DEMO
dc.subject.keywordITER
dc.subject.keywordPlasma
dc.subject.keywordPlasma Instabilities
dc.subject.keywordPPCS
dc.subject.keywordSST-1
dc.subject.keywordTokamak
dc.subject.keywordVDE
dc.titleCoupled field finite element analyses for the design of fusion reactor components against transient plasma induced electromagnetic loads
dc.title.alternative
dc.type.degreePh.D.

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