Analysis of a Protected Loss of Flow Accident (LOFA) in the ITER TF Coil Cooling Circuit

@article{Savoldi2018AnalysisOA,
  title={Analysis of a Protected Loss of Flow Accident (LOFA) in the ITER TF Coil Cooling Circuit},
  author={Laura Savoldi and Roberto Bonifetto and Nicola Pedroni and Roberto Zanino},
  journal={IEEE Transactions on Applied Superconductivity},
  year={2018},
  volume={28},
  pages={1-9}
}
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 any damage to the magnets. A “protected” loss of flow accident in the ITER toroidal field coils, detected by the coil flow meters and managed by the central interlock system, is investigated here using the validated thermal–hydraulic code 4C. We simulate the entire sequence of events that is… 
Computational Methods for the Integrated Deterministic and Probabilistic Safety Assessment of a Simplified Cooling Circuit for a Tokamak Superconducting Magnet
TLDR
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 is considered.
Identification of the Postulated Initiating Events of Accidents Occurring in a Toroidal Field Magnet of the EU DEMO
TLDR
The initiating events of the most critical accident sequences in the EU DEMO magnet system (with special reference to the toroidal field magnets) are identified here, adopting first a functional analysis and then a failure mode, effects, and criticality analysis.
Metamodeling and On-Line Clustering for Loss-of-Flow Accident Precursors Identification in a Superconducting Magnet Cryogenic Cooling Circuit
TLDR
This work develops a three-step methodology for the prompt detection of LOFA precursors and applies the proposed technique to the simplified model of a cryogenic cooling circuit of a single module of the ITER Central Solenoid Magnet (CSM).

References

SHOWING 1-10 OF 23 REFERENCES
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
Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from the vacuum vessel reaches the superconducting toroidal field (TF) magnets, contributing to the
Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin
In the International Thermonuclear Experimental Reactor, the nuclear radiation escaping from the vacuum vessel reaches the superconducting toroidal field (TF) magnets, affecting the temperature
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
Thermal Behavior and Quench of the ITER TF System During a Fast Discharge and Possibility of a Secondary Quench Detection
During a fast discharge of the TF system, eddy currents and high associated heat production in the winding plates can induce a quench by heat transfer. A quasi 2D model based on the coupled GANDALF
Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code
The ITER toroidal field insert (TFI) coil is a single-layer Nb3Sn solenoid tested in 2016–2017 at the National Institutes for Quantum and Radiological Science and Technology (former JAEA) in Naka,
Progress in Europe of the Procurement of the EU ITER TF Coils
The ITER magnetic system includes 18 toroidal field (TF) coils constructed using a Nb3Sn cable-in-conduit superconductor. Each TF coil comprises a winding pack (WP) composed of seven double pancake
Verification of the predictive capabilities of the 4C code cryogenic circuit model
The 4C code was developed to model thermal-hydraulics in superconducting magnet systems and related cryogenic circuits. It consists of three coupled modules: a quasi-3D thermal-hydraulic model of the
Status of the ITER Cryodistribution
TLDR
The present design status and component configuration of the ITER Cryodistribution with all changes implemented which aim at process optimization and simplification as well as operational reliability, stability and flexibility are summarized.
...
...