Document Type
Annual Report
Publication Date
2006
First page number:
64
Last page number:
65
Abstract
The ultimate objective of this project is to develop technology to detect and accurately measure quantities of higher actinides in processing systems without taking frequent samples. These systems include used fuel receipt, separations batches, and pipelines. A variety of measurements may be combined to calculate flow rates of actinide elements with a to-be-determined precision. Nuclear and decay characteristics of materials during processing will be acquired, conceptual designs of monitoring systems will be developed, radiation transport studies will be conducted to develop an understanding of operational regimes, and experiments will be performed to confirm performance. Radiation transport and scoping studies will be conducted to investigate combined gamma-ray, neutron, and active and passive detection techniques to measure quantities and isotopic constituents contained during separations and intermediate storage. Scoping and design studies will first be performed using validated data sets (decay properties and reaction cross sections) and the radiation transport code MCNPX. Basic measurements will then be performed and compared to predictions.
Keywords
Actinide elements – Separation; Radioactive wastes — Purification; Reactor fuel reprocessing; Spent reactor fuels
Controlled Subject
Actinide elements--Separation; Radioactive wastes--Purification; Reactor fuel reprocessing
Disciplines
Nuclear | Nuclear Engineering
File Format
File Size
146 KB
Language
English
Rights
COPYRIGHT UNDETERMINED. For more information about this rights statement, please visit http://rightsstatements.org/vocab/UND/1.0/
Repository Citation
Beller, D.,
Kernan, W.
(2006).
Combined Radiation Detection Methods for Assay of Higher Actinides in Separation Processes (AFCI).
64-65.
Available at:
https://digitalscholarship.unlv.edu/hrc_trp_safeguards/8