NDLI: Three Dimensional Neutronics Analysis of the ITER First Wall/Shield Module 13

Content Provider	IEEE Xplore Digital Library
Author	Smith, B. Wilson, P.P.H. Sawan, M.E.
Copyright Year	2007
Description	Author affiliation: Univ. of Wisconsin, Madison (Smith, B.; Wilson, P.P.H.; Sawan, M.E.)
Abstract	Radiation shielding and energy removal for ITER are provided by an array of first wall/shield modules (FWS). Nuclear analysis of the shield modules is important for understanding their performance and lifetime in the system. While one-dimensional (1-D) analysis provides an adequate first approximation, three-dimensional (3-D) analysis is needed to validate the 1-D analysis and resolve fine geometric details that result from heterogeneities in the module. Using MCNPX-CGM, a coupling of traditional MCNPX with the Common Geometry Module (CGM), high-fidelity 3-D neutronics analysis is now possible. Particles are transported in the CAD geometry reducing analysis time, eliminating input error, and preserving geometric detail. A detailed 3-D CAD model of FWS module 13 is inserted into a 1-D radial approximation including homogenized representations of the inboard FWS, plasma, and vacuum vessel (VV). A 14.1 MeV uniform source between the inboard and outboard sides is used to simulate the ITER plasma. Reflecting boundary conditions approximate the full extent of ITER in the poloidal and toroidal directions. Heating, radiation damage, and helium production profiles through module 13 are determined using high-resolution mesh tallies. In the front manifold of the shield block, heating and helium production were found to be lower in steel than the homogenized 1-D model suggests. Peaking in nuclear heating and helium production in steel is observed at the interface with adjacent water zones.
Starting Page	1
Ending Page	4
File Size	850667
Page Count	4
File Format	PDF
ISBN	9781424411931
DOI	10.1109/FUSION.2007.4337910
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2007-06-17
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Plasma simulation Helium Production Geometry Plasma sources Heating Steel Performance analysis User-generated content Plasma transport processes helium production ITER shield modules nuclear heating
Content Type	Text
Resource Type	Article

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4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
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