Okolje za izračun toplotnih obremenitev na prvi steni fuzijskega reaktorja ITER

magistrsko delo magistrskega študijskega programa II. stopnje Strojništvo

Abstract

Tokamak ITER je konstruiran za tvorjenje fuzijsko-relevantnih plazem v trajanju od nekaj sto do tisoč sekund. Ti dolgi časi zahtevajo aktivno hlajenje prve stene, ki je direktno izpostavljena plazmi. Zaščita stene iz berilija (Be) je plazmi izpostavljena komponenta (PFC) za katero veljajo stroge omejitve gostote toplotnega toka na zunanji površini, da se izognemo kritičnim vrednostim toplotnega toka v povezanih hladilnih kanalih. Zato je zelo pomembno vnaprej podati oceno verjetnih toplotnih obremenitev in prenos toplote znotraj Be ščita za vpeljavo nadzornih algoritmov plazme v realnem času. Cilj magistrskega dela je izdelava dodatka za okolje SMITER, ki omogoča sledenje delcev magnetnim silnicam v fuzijskem reaktorju. Uporabite metodo končnih elementov in izdelajte dodatek, ki bo omogočal izračun temperature na hlajeni prvi steni reaktorja na podlagi porazdelitev toplotnih tokov, ki jih izračuna SMITER. Prenos toplote obravnavajte kot stacionaren. Izračunana porazdelitev temperatur na ščitu naj bo uporabljena za izdelavo sinetičnih diagnostičnih signalov za testiranje odziva ITER-jevih infrardečih diagnostičnih sistemov in kot vhod za nadzorne algoritme. Rezultate tega vmesnika na koncu primerjajte z izračuni temperatur, ki jih bo predložila organizacija ITER.

Keywords

magistrske naloge;Smiter;Elmer FEM;metoda končnih elementov;Euler-Rodriguesova formula;format VTK;fuzija;toplotna obremenitev;prenos toplote;plazma izračun temperatur;

Data

Language:	Slovenian
Year of publishing:	2018
Typology:	2.09 - Master's Thesis
Organization:	UL FS - Faculty of Mechanical Engineering
Publisher:	[M. Brank]
UDC:	621.039.6(043.2)
COBISS:	16424987
Views:	1100
Downloads:	321
Average score:	0 (0 votes)
Metadata:

Other data

Secondary language:	English
Secondary title:	A Framework for Computation of Heat Loads on ITER First Wall Panel
Secondary abstract:	The ITER tokamak is designed to produce fusion grade plasmas for durations of hundreds to thousands of seconds. These long durations require active cooling of the wall armour directly facing the plasma. Such actively cooled plasma-facing components (PFCs) have strict limits on the surface heat flux densities in order to avoid critical heat fluxes at interfaces with the cooling channels. These flux densities are lower for the 700m2 of beryllium (Be) main chamber PFCs than for the tungsten divertor targets and must be carefully monitored from the beginning of ITER operations, when the Be panels will be used for plasma start-up. It is thus extremely important to provide assessments of likely heat loading and thermal transfer within the Be armour for incorporation into real time plasma control algorithms. This thesis aims to make a contribution in this area by providing a plugin to the SMITER magnetic field line following code framework for finite element calculations in first wall panels subject to heat flux distributions on the front surface computed by SMITER. The primary output of this new module will be stationary surface temperature distributions allowing production of synthetic diagnostic signals for testing the response of ITER infra-red diagnostic systems and as input to control algorithms. Results from the interface developed in this work will be benchmarked against specific existing thermal calculations provided by the ITER organisation.
Secondary keywords:	Smiter;Elmer FEM;finite element method;CAD modelling;GEOM modul SMESH meshing;Euler-Rodrigues equation;VTK format;fusion;thermal loading;heat transfer;plasma temperature computation;
Type (COBISS):	Master's thesis/paper
Study programme:	0
Embargo end date (OpenAIRE):	1970-01-01
Thesis comment:	Univ. Ljubljana, Fak. za strojništvo
Pages:	XXVI, 131 str.
ID:	10958895