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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Charles W. Townley, James E. Howes, Jr., Gilbert E. Raines, Ward S. Diethorn, Duane N. Sttnderman
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 346-351
doi.org/10.13182/NSE61-A15376
Articles are hosted by Taylor and Francis Online.
A radiochemical technique has been developed for the determination of the release rates of short-lived fission gases from fuel specimens during irradiation. Fission-product gases with half-lives ranging from 1.7 sec to 3.9 min were employed in the development of the procedure. These were krypton-89, xenon-137, xenon-140, and xenon-141. The procedure involves the collection and analysis of the solid daughter products of these gases. The gases are swept through a long tube packed with stainless steel mesh, and the daughter products deposit on the mesh as they are formed. The mesh is analyzed radiochemically for the daughter species, strontium-89, cesium-137, barium-140, and cerium-141. From the results of these analyses, the release rates of the parent fission gases may be calculated with a knowledge of the transit time of the gases through the tran and the transport time from the point of release to the trap entrance.