Consideration of Nuclear Criticality When Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff-I: Nuclear Criticality Constraints
This paper presents the mass, concentration, and volume required for a critical event to occur in homogeneous mixtures of fissile material and various other geologic materials. The fissile material considered is primarily highly enriched uranium spent fuel; however, 239 Pu is considered in some case...
Saved in:
Published in | Nuclear technology Vol. 144; no. 2; pp. 201 - 221 |
---|---|
Main Authors | , , |
Format | Journal Article |
Language | English |
Published |
La Grange Park, IL
Taylor & Francis
01.11.2003
American Nuclear Society |
Subjects | |
Online Access | Get full text |
Cover
Loading…
Summary: | This paper presents the mass, concentration, and volume required for a critical event to occur in homogeneous mixtures of fissile material and various other geologic materials. The fissile material considered is primarily highly enriched uranium spent fuel; however,
239
Pu is considered in some cases. The non-fissile materials examined are those found in the proposed repository area at Yucca Mountain, Nevada: volcanic tuff, iron rust, concrete, and naturally occurring water. For
235
U, the minimum critical solid concentration for tuff was 5 kg/m
3
(similar to sandstone), and in goethite, 45 kg/m
3
. The critical mass of uranium was sensitive to a number of factors, such as moisture content and fissile enrichment, but had a minimum, assuming almost 100% saturation and >20% enrichment, of 18 kg in tuff as Soddyite (or 9.5 kg as UO
2
) and 7 kg in goethite. For
239
Pu, the minimum critical solid concentration for tuff was 3 kg/m
3
(similar to sandstone); in goethite, 20 kg/m
3
. The critical mass of plutonium was also sensitive to a number of factors, but had a minimum, assuming 100% saturation and 80-90% enrichment, of 5 kg in tuff and 6 kg in goethite. |
---|---|
Bibliography: | ObjectType-Article-2 SourceType-Scholarly Journals-1 ObjectType-Feature-1 content type line 23 |
ISSN: | 0029-5450 1943-7471 |
DOI: | 10.13182/NT03-4 |