Published September 2012 | Version v1
Report

Disruption Impacts and their Mitigation Target Values

  • 1. ITER Organization, St. Paul lez Durance (France)
  • 2. CCFE, Culham Science Centre, Abingdon (United Kingdom)
  • 3. NRC 'Kurchatov Institute', Moscow (Russian Federation)
  • 4. Japan Atomic Energy Agency, Naka (Japan)
  • 5. Max-Planck-Institute fuer Plasmaphysik, Garching (Germany)

Description

Full text: Major disruptions (MD) and vertical displacement events (VDE) in ITER will be the cause of a variety of deleterious impacts due to the high stored thermal and magnetic energy. Extrapolation from the disruption database obtained on current tokamaks and the results of numerical simulations, demonstrate that the thermal loads which will be produced during the thermal quench (TQ) of MD and VDEs in ITER, will lead to large scale macroscopic melting of metallic plasma-facing components (PFC). During the current quench (CQ) phase, runaway electrons (RE) are expected to deposit severe thermal loads on PFCs. The electromagnetic (EM) loads due to halo and eddy currents during the CQ are a critically important factor in the mechanical design of the vacuum vessel (VV) and in-vessel components (IVC). For reliable operation and machine protection in ITER, mitigation of these heat and EM loads and REs during MDs and VDEs is mandatory. It is essential to realize high performance in the following three elements simultaneously for reliable mitigation: 1. High mitigation performance factor (high reduction of impact). 2. High prediction performance (high success rate simultaneously with low false rate). 3. Low disruptivity (by passive and active disruption avoidance). Proper target values of each element are of primary importance to achieve the overall mitigation performance required in ITER and to promote the physics R&D for the development of mitigation, prediction and avoidance systems and algorithms. In this paper, we will quantify proper target values for each element of mitigation based on the assessment of the impacts by heat and EM loads and REs using physics databases and modeling for the present ITER design. Key components like VV, IVC and PFC will be carefully examined to quantify these requirements. (author)

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

Additional details

Publishing Information

Imprint Title
24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
789 p.
Journal Page Range
p. 571
Report number
IAEA-CN--197

Conference

Title
24. IAEA Fusion Energy Conference
Acronym
FEC 2012
Dates
8-13 Oct 2012
Place
San Diego, CA (United States)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
45033990
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; COMPUTERIZED SIMULATION; EDDY CURRENTS; EXTRAPOLATION; FIRST WALL; ITER TOKAMAK; MITIGATION; RUNAWAY ELECTRONS; SAFETY
Descriptors DEC
CLOSED PLASMA DEVICES; CURRENTS; ELECTRIC CURRENTS; ELECTRONS; ELEMENTARY PARTICLES; FERMIONS; LEPTONS; MATHEMATICAL LOGIC; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Secondary number(s)
ITR/P1--14