Monte Carlo radiation shielding and activation analyses for the Diagnostic Equatorial Port Plug in ITER
- 1. Karlsruhe Institute of Technology KIT, Institute for Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)
- 2. ITER Organization, Route de Vinon sur Verdon, 13115, St. Paul lez Durance (France)
Description
Highlights: ► Systematic neutronics analyses were conducted to assess the ITER Equatorial Port Plug radiation shielding performance. ► Shielding optimization was achieved by parametric analyses of several design variants using the MCNP5, FISPACT-2007, and R2Smesh codes. ► Dominant effect of radiation streaming along the port plug gaps was recognized. ► Combination of the gap labyrinths and streaming stoppers or rails reduces shutdown doses by 2 orders of magnitude. ► Using the proposed shielding, the shutdown dose in the ITER port interspace is less than the personnel access limit of 100 μSv/h. - Abstract: This paper addresses neutronics aspects of the design development of the Diagnostic Generic Equatorial Port Plug (EPP) in ITER. To secure the personnel access at the EPP back-end interspace, parametric neutronics analyses of the EPP radiation environment have been performed and practical shielding solutions have been found. Radiation transport was performed with the Monte Carlo MCNP5 code. Activation calculations were conducted with the FISPACT-2007 inventory code. The R2Smesh approach was applied to couple transport and activation calculations. Newly created EPP local MCNP5 model was devised by extracting the EPP and adjacent blanket modules from the ITER Alite-4.1 model with proper modification of the EPP geometry in accordance with recent 3D CAD CATIA model. The EPP local model reproduces the EPP neutronically important features and allows investigation of the EPP neutronics effects in isolation from all other ITER components. Thorough EPP parametric analyses revealed dominant effect of gaps around EPP and several EPP design improvements were implemented as the outcomes of the analyses. Gap labyrinths and streaming stoppers inserted into the gaps were shown are capable to reduce the shutdown dose rate which is below the 100 μSv/h limit of personnel access and by 2 orders of magnitude less than the value in the model with straight gaps.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2012.02.003Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2012.02.003;
- PII
- S0920-3796(12)00058-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 87
- Journal Issue
- 5-6
- Journal Page Range
- p. 690-694
- 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
- 44037059
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVATION ANALYSIS; CLOSURES; COMPUTER CODES; DOSE RATES; ITER TOKAMAK; MONTE CARLO METHOD; OPTIMIZATION; PARAMETRIC ANALYSIS; PERSONNEL; RADIATION DOSES; RADIATION STREAMING; RADIATION TRANSPORT; SHIELDING; SHUTDOWN
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL ANALYSIS; CLOSED PLASMA DEVICES; DOSES; NONDESTRUCTIVE ANALYSIS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.