DocumentCode
1344728
Title
Neutron methods for monitoring the blending of enriched UF6 gas
Author
Stromswold, D.C. ; Peurrung, A.J. ; Reeder, P.L. ; Sunberg, D.S.
Author_Institution
Pacific Northwest Lab., Richland, WA, USA
Volume
44
Issue
3
fYear
1997
fDate
6/1/1997 12:00:00 AM
Firstpage
563
Lastpage
567
Abstract
Blending a highly enriched UF6 gas stream with low-enrichment material reduces the excess supply of highly enriched uranium that must be closely controlled for nonproliferation of nuclear weapons. Computer simulations and feasibility experiments show that inducing fission in 235U provides means for monitoring the blending process. Detecting delayed fission neutrons or gamma rays after fission products drift downstream in the gas gives a measure of 235 U content and flow velocity. At very low UF6 gas pressures (5 mm Hg) where the downstream signal is too weak for use, an alternative technique based on attenuation of thermal neutrons passing through the UF6 gives a measure of 235U content
Keywords
fission reactor fuel preparation; neutron detection; uranium compounds; 5 mmHg; 235U content; U; UF6; UF6 gas pressure; blending; computer simulations; delayed fission neutrons; enriched UF6 gas; fission products; flow velocity; gamma rays; thermal neutrons; Computer simulation; Computerized monitoring; Delay; Fluid flow measurement; Gamma ray detection; Gamma ray detectors; Gamma rays; Neutrons; Nuclear weapons; Velocity measurement;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/23.603711
Filename
603711
Link To Document