Published October 16, 2018 | Version v1
Report

First Mirror Test in JET for ITER: Complete Overview After Three Campaigns in JET with ITER-Like Wall

  • 1. KTH Royal Institute of Technology, Stockholm (Sweden)
  • 2. Culham Centre for Fusion Energy (CCFE), Culham Science Centre, Abingdon (United Kingdom)
  • 3. Warsaw University of Technology, 00-661 Warsaw (Poland)
  • 4. Laboratory for Plasma Physics, ERM/KMS, Brussels (Belgium)

Description

Full text: Metallic first mirrors are essential plasma-facing components (PFC) in all optical spectroscopy and imaging systems used for plasma diagnosis. First mirror test (FMT) has been carried out at the JET tokamak with the ITER-like wall (JET-ILW). Over 120 test Mo mirrors were exposed in JET during the entire project. The aim is to provide an overview of results obtained for mirrors exposed during: i) the third ILW campaign, ILW3, 2015-2016, 23.6 h plasma; ii) all three campaigns, i.e., ILW 1-3: 2011-2016, 62 h in total; and iii) a comparison to results in JET-C. Examinations were done by optical, electron and ion beam techniques. The total reflectivity of all mirrors in the main chamber has decreased by 2-3% from the initial value. All of them are coated by a very thin codeposit (5-15 nm) containing D, Be, C and O. This has affected the optically active layer (15-20 nm on Mo) and led to increased diffuse reflectivity. No W and N have been found on the surface. All mirrors from the divertor lost reflectivity by 20-80%. There are significant differences in the surface state dependent on the location and exposure time. Reflectivity loss is connected predominantly with the codeposition of Be and some C species. The thickest layers have been found in the outer divertor: 850 nm after ILW1-3, indicating the average growth rate of 4 pm/s. The layers thickness is not directly proportional to the exposure time. Nitrogen, tungsten and nickel are on all mirrors from the divertor. The highest N and W contents are in the inner divertor: N reaches 1 x 1017/cm2, W is up to 3.0 x 1016/cm2, while the greatest Ni content is in the outer leg: 2.5 x 1017/cm2. The results obtained for the main chamber mirrors allow some optimism regarding the diagnostics reliability in ITER. Tests done in JET-C and JET-ILW show that the degradation of optical properties in a machine with metal PFC is distinctly smaller than in the carbon surrounding. However, a long-term exposure and off-normal events may change surface properties of the mirrors. Laser- or plasma induced cleaning techniques of tokamak mirrors have not brought any positive results. There are some indications that single crystal mirrors may be cleaned more efficiently than polycrystalline. Search for engineering solutions for mirror exchange in a reactor should not be abandoned especially for the divertor mirrors. (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. 211
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
50050393
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; FIRST WALL; ION BEAMS; ITER TOKAMAK; JET TOKAMAK; MONOCRYSTALS; NICKEL; PLASMA DIAGNOSTICS; REFLECTIVITY; RELIABILITY; SPECTROSCOPY; TUNGSTEN
Descriptors DEC
BEAMS; CLOSED PLASMA DEVICES; CRYSTALS; ELEMENTS; METALS; OPTICAL PROPERTIES; PHYSICAL PROPERTIES; REFRACTORY METALS; SURFACE PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS

Optional Information

Collaborations
JET Contributors
Secondary number(s)
IAEA-CN--258-257