Radiation transport analyses for IFMIF design by the Attila software using a Monte-Carlo source model

W. Arter, M. J. Loughlin

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

Accurate calculation of the neutron transport through the shielding of the IFMIF test cell, defined by CAD, is a difficult task for several reasons. The ability of the powerful deterministic radiation transport code Attila, to do this rapidly and reliably has been studied. Three models of increasing geometrical complexity were produced from the CAD using the CADfix software. A fourth model was produced to represent transport within the cell. The work also involved the conversion of the Vitenea-IEF database for high energy neutrons into a format usable by Attila, and the conversion of a particle source specified in MCNP wssaformat to a form usable by Attila. The final model encompassed the entire test cell environment, with only minor modifications. On a state-of-the-art PC, Attila took approximately 3 h to perform the calculations, as a consequence of a careful mesh 'layering'. The results strongly suggest that Attila will be a valuable tool for modelling radiation transport in IFMIF, and for similar problems. Crown

Original languageEnglish
Pages (from-to)89-96
Number of pages8
JournalFusion Engineering and Design
Volume84
Issue number1
DOIs
StatePublished - Jan 2009
Externally publishedYes

Funding

We are grateful to M. Frisoni and S. Simakov for assistance as noted in the text. This work was jointly funded by the United Kingdom Engineering and Physical Sciences Research Council and by EURATOM. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

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