Type of Publication
Year of Publication
2009
Authors

B.J. Merrill; R.L. Moore; P. Sharpe

Abstract

A beryllium dust oxidation model has been developed at the Idaho National Laboratory (INL) by the Fusion Safety Program (FSP) for the MELCOR safety computer code. The purpose of this model is to investigate hydrogen production from beryllium dust layers on hot surfaces inside a fusion reactor vacuum vessel (VV) during in-vessel loss-of-cooling accidents (LOCAs). This beryllium dust oxidation model accounts for the diffusion of steam into a beryllium dust layer, the oxidation of the dust particles inside this layer based on the beryllium-steam oxidation equations developed at the INL, and the effective thermal conductivity of this beryllium dust layer. This paper details this oxidation model and presents the results of the application of this model to a wet bypass accident scenario in the ITER device. (C) 2008 Elsevier B.V. All rights reserved.

DOI

10.1016/j.fusengdes.2008.11.065

Volume

84

Notes

Times Cited: 2 25th Symposium on Fusion Technology Sep 15-19, 2008 Rostock, GERMANY Max Planck Inst Plasmaptys 2

Pagination

1285-1288

Number
11
ISSN Number

0920-3796