Molybdenum-99 Isotope Production Preparation at Sandia National Laboratories [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1998.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Additional Creators:
- Sandia National Laboratories
United States. Department of Energy
United States. Department of Energy. Office of Scientific and Technical Information
- `Q&c M. J. McDonald, S. D. Carson, S. W. Longley, E. J. Parma, M. E. Vern `~ I@ .,., Sandia National Laboratories*, P. .0. Box 5800, Albuquerque, NM, 8 W? 1$ tl?;:q `f. (3 . 8 /'~ Abstract This report was prepared as an account of work sponsored byanagency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. loading on the Cintichem targets. These tests were designed to gain process knowledge prior to processing an irradiated target. The chemical separation tests were performed in a fime hood During cold testing, several tests were performed on individual components of the process to complete, a series of `hot' tests was designed to process irradiated targets. These were designed to optimize the process, identify problems prior to processing higher inventory targets, and to the shielded containment box (SCB). Table 1 is a summary of the tests performed prior to the Test Target Power Post irradiation Total inventory 99M0 inventory (kW)/ Irradiation decay (hrs) (TBq*) /decay (TBq)/decay Time (hrs) inventory (TBq) inventory(TBq) in the processing boxes as color comparisons. Product quality control testing was conducted for all the tests and the results were compared to The production process generates a high activity acidic liquid waste. Several waste stabilization processing box. The cement, in addition to stabilizing the waste, neutralized the waste resulting The processing hardware and fixtures were developed in parallel to the cold tests and tested in a that expected during processing. During processing, precautions will be taken to minimize the Island incident. The facility consisted of shielded glove boxes, unshielded glove box lines and the the facility for production operations; the glove box lines and shielded glove boxes, all the new configuration will have six windows, four extraction boxes and a waste packaging box on the shielding. The walls and windows of the processing boxes will have the equivalent 150 of the purification box will be considerably less than the processing boxes with dose being from only `gMo. The increased wall thickness will reduce the dose levels to boxes will have under the box transport systems to move material into and out of the boxes. prior to FDA requiring process validation and, consequently, had not pertlormed a process
- Published through SciTech Connect.
Creation and Future Legacy of Stockpile Stweardship and Isotope Production, Applications, and Consumption; Albuquerque, NM; 1/24-27/1998.
Carson, S.D.; Vernon, M.E.; McDonald, M.J.; Longley, S.W.; Parma, E.J.
- Funding Information:
View MARC record | catkey: 14346660