• Corpus ID: 59592294

Computational Methods for the Integrated Deterministic and Probabilistic Safety Assessment of a Simplified Cooling Circuit for a Tokamak Superconducting Magnet

  title={Computational Methods for the Integrated Deterministic and Probabilistic Safety Assessment of a Simplified Cooling Circuit for a Tokamak Superconducting Magnet},
  author={R. Bellaera},
The objective of this thesis is considering the safety analysis of the simplified cooling system of a single module of the ITER Central Solenoid in a cold test facility to classify the different abnormal transients and identify the components failure that may drive the system into a Loss-Of-Flow Accident. The IDPSA framework is applied for the first time to a fusion system to study the dynamic response of the system. Two different operating condition are considered: a first simplified case, in… 


Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil
The ITER tokamak is under construction in France and the EU hopes to produce the first kWh from the magnetically-confined fusion reactor DEMO by mid of this century. The superconducting magnet system
Analysis of a Protected Loss of Flow Accident (LOFA) in the ITER TF Coil Cooling Circuit
In moving toward ITER operation, the detailed analysis of fault conditions for the magnets becomes of increasing importance, to verify that the magnet protection system can safely manage them without
Comprehensive safety analysis code system for nuclear fusion reactors I: Model and analyses of overpower events for the International Thermonuclear Experimental Reactor
A comprehensive safety analysis code system has been proposed for the quantitative investigation of the safety of nuclear fusion reactors such as the International Thermonuclear Experimental Reactor
Safety Analysis of the 70 kA ITER HTS Current Lead Demonstrator
  • R. Heller
  • Physics
    IEEE Transactions on Applied Superconductivity
  • 2009
For the superconducting magnet system of the International Thermonuclear Experimental Reactor, ITER, 60 current leads for a total current of more than 2500 kA are needed. The use of High Temperature
Preliminary Safety Analysis of ITER
A comprehensive set of analyses of postulated event sequences provides the demonstration that the consequences of enveloping scenarios are well within acceptable limits, and that even for hypothetical events involving two or more independent failures, the public and environmental impacts remain limited.
Quench Analysis of an ITER TF Coil
Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC)
The first step of the validation of the recently developed thermal-hydraulic code 4C is presented. We study the transient evolution during a so-called standard 25 kA safety discharge of the