Design of the in-wall shielding for the ITER neutral beam port
Creators
- 1. National Fusion Research Institute, Yuseong-gu, Daejeon (Korea, Republic of)
- 2. Il-Sung Co.: 917 Wonsan-Li, Onsan-Eub, Ulsan (Korea, Republic of)
- 3. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)
Description
The ITER neutral beam port is composed of connecting duct, port extension and port stub extension. The spaces between inner and outer shells of the port extension and port stub extension are filled with pre-assembled blocks, called in-wall shielding. The main purpose of IWS is to provide neutron shielding for the superconducting magnet, thermal shield and cryostat from the main vessel during plasma operation. In order to provide effective neutron shielding capability with the cooling water, 40 mm thick flat plates (steel type 304B4) are used in almost all areas of the volume between port shells. The IWS is composed of shield plates, upper/lower brackets and bolt/nut/washers. Major activities during design work are to develop installation concept of the IWS blocks for easy assembly into port structures and to perform structural analysis to assess sufficient strength, fabrication feasibility study and 3D modeling including drawing works. In this paper, major results of mechanical design are introduced. First, the design requirements for IWS and the developed IWS designs for easy assembly into the port structure are introduced. Second, is introduced the engineering analysis results to assess structural integrity. And then the fabrication feasibility study results are presented for major fabrication processes. Lastly, conclusion and future works are mentioned.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2012.02.083Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2012.02.083;
- PII
- S0920-3796(12)00156-1;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 87
- Journal Issue
- 7-8
- Journal Page Range
- p. 1055-1059
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 10. international symposium on fusion nuclear technology
- Acronym
- ISFNT-10
- Dates
- 11-16 Sep 2011
- Place
- Portland, OR (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44037129
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINERS; COOLING; CRYOSTATS; DUCTS; FEASIBILITY STUDIES; ITER TOKAMAK; NEUTRAL PARTICLES; NEUTRONS; PARTICLE BEAMS; PLASMA; PLATES; SHIELDING; STEELS; SUPERCONDUCTING MAGNETS; THERMAL SHIELDS; THREE-DIMENSIONAL CALCULATIONS; WATER
- Descriptors DEC
- ALLOYS; BARYONS; BEAMS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CONTROL EQUIPMENT; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELEMENTARY PARTICLES; EQUIPMENT; FERMIONS; HADRONS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MAGNETS; NUCLEONS; OXYGEN COMPOUNDS; SHIELDS; SUPERCONDUCTING DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; THERMOSTATS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.