Published October 16, 2018 | Version v1
Report

Overview of Disruptions with JET-ILW

  • 1. Culham Centre for Fusion Energy (CCFE), Culham Science Centre, Abingdon (United Kingdom)
  • 2. Instituto Superior Técnico (IST), 1049-001 Lisbon (Portugal)
  • 3. ENEA for EUROfusion, via E. Fermi 45, 00044 Frascati (Roma) (Italy)

Description

Full text: This paper presents an analysis of disruptions occurring during JET-ILW plasma operations covering the period from #80128 up to #92504. The total number of disruptions was 1951, including 466 MGI (massive gas injection), VDE (vertical displacement event) and error field correction coil experiments, which led to intentional disruptions; hence the average disruption rate is 16.1%. MGI has been routinely used in protection mode both to terminate pulses when the plasma is at risk of disruption, and to mitigate against disruptions, in total 896 shots were ended by MGI. The subset of 913 natural disruptions, which were not affected by special dedicated experiments or MGI protection, was used for analysis of predisruptive plasma behaviour. The predisruptive plasma parameters of the natural disruptions are Ip = (0.82-3.14) MA, toroidal field Bt = (0.98-3.36) T, q95 = (1.52-9.05), li = (0.58-1.86), p = (0-1.1), volume average plasma density ne = (0.2-8.5)1019/m3 , X-point (317 shots) and limiter (596 shots) configurations. Apart from 21 exceptional cases, the MGI was triggered by n = 1 locked mode (523 shots) or by the disruption itself, specifically by d Ip/dt (207 shots) or by toroidal loop voltage (145 shots). On JET, only the locked mode was treated as either a precursor or the cause of disruptions. However, long lasting locked modes (≥ 100 ms) do exist prior to disruption in 75% of cases. Though, 10% of nondisruptive pulses have a locked mode which eventually vanished without disruption. The plasma current quench (CQ) may result in 3D equilibria, termed as asymmetrical disruptions, which are accompanied by sideways forces. Unmitigated VDEs generally have significant plasma current toroidal asymmetries. The unmitigated disruptions also have large plasma current asymmetries presumably because there is no plasma vertical position control during CQ. However, MGI is a reliable tool to mitigate 3D effects and accordingly sideways forces. The vessel structure loads depend on the force impulse and force time behaviour or rotation. The toroidal rotation of 3D equilibria is of particular concern because of potential resonance with the natural frequencies of the vessel components in large tokamaks such as ITER. The amplitude-frequency interdependence is important, since a simultaneous increase of amplitude and frequency would potentially create the most challenging load conditions. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 219
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50050400
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ELECTRIC CURRENTS; GAS INJECTION; ITER TOKAMAK; PLASMA DENSITY; PULSES
Descriptors DEC
CLOSED PLASMA DEVICES; CURRENTS; FLUID INJECTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Collaborations
JET Contributors
Secondary number(s)
IAEA-CN--258-241