Published November 2018 | Version v1
Journal article

Shutdown dose rate calculation along the ITER IVVS port

  • 1. ENEA, Fusion and Technology for Nuclear Safety and Security Department, ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy)
  • 2. Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, D 76344 Eggenstein-Leopoldshafen (Germany)
  • 3. Fusion for Energy, Calle Josep Pla 2, Torres Diagonal Litoral B3, Barcelona (Spain)
  • 4. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)

Description

Highlights: • TER IVVS system: shutdown dose rate in the port cell at 1 day after shutdown. • Combined use of the R2S and Advanced D1S methods. • High resolution maps of shutdown dose rate with a statistical uncertainty within 1%. • Shutdown dose rate is below the design limit of 10 μSv/h. • 24Na decay from concrete activation is responsible for most of the dose rate. - Abstract: The ITER In-Vessel Viewing System (IVVS) consists of six identical units located at the B1 level of the Tokamak complex, at lower ports 3, 5, 9, 11, 15 and 17. It can be used for visual inspection of the plasma chamber in between plasma pulses. This work is devoted to the nuclear analyses performed for the latest design of the IVVS, to assess the shutdown dose rate (SDDR) in the port cell (PC) and the gallery at 1 day after shutdown in order to verify the design limit in the maintenance area. This analysis was performed through a combined use of the R2S method, for the activation of components from the vacuum vessel VV up to the bioshield, and Advanced D1S method for activation of components from the bioshield up to the gallery. Several MCNP calculations have been performed to transport neutrons and decay gammas up to the bioshield, then, by means of secondary sources, the radiation field has been extended in the PC up to the gallery. This strategy allowed to provide high resolution (voxel size 10 × 10 × 10 cm3) maps of shutdown dose rate in the PC with a statistical uncertainty within ±1% and in the gallery with a statistical uncertainty within ±20%. The consistency of the SDDR results obtained by the two codes at the interface highlighted the reliability of the coupled techniques used in the present analyses. Moreover it is assessed that the design target of 10 μSv/h in the PC is satisfied for the IVVS port.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2018.05.025

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2018.05.025;
PII
S0920379618304526;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
136
Journal Issue
Part B
Journal Page Range
p. 1404-1407
ISSN
0920-3796
CODEN
FEDEEE

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51011802
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DOSE RATES; INTERFACES; ITER TOKAMAK; MAINTENANCE; NEUTRON TRANSPORT; PLASMA; RELIABILITY; RESOLUTION; SHUTDOWN
Descriptors DEC
CLOSED PLASMA DEVICES; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.