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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
J. W. Boyle, H. A. Mahlman
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 492-500
Technical Paper | doi.org/10.13182/NSE57-A25414
Articles are hosted by Taylor and Francis Online.
Concentrated thorium nitrate solution has been proposed as a blanket material in power-breeder reactors. The radiation stability, especially of the nitrate group, is therefore of considerable importance. The radiation-induced decomposition of thorium nitrate solutions was studied as a function of concentration, type of radiation (fission recoils, pile radiations, gamma rays), temperature, and total energy absorbed. The principal products were H2 and O2 from decomposition of the water, and N2, O2, and oxides of nitrogen from decomposition of the nitrate. Hydrogen yield decreased with increasing thorium nitrate concentration, a behavior similar to that for uranium solutions. Nitrogen yield was independent of temperature, but increased with increasing nitrate concentration and with increasing linear energy transfer along the paths of the ionizing particles. The 100-ev yield of N2 in 2.73 molal solution was 0.06 for fission particle decomposition, 0.006 for pile radiation (mixed fast neutrons and γ rays) and 0.001 for γ radiation alone. The oxide of nitrogen produced with the largest yield was N2O and amounted to about ten per cent of the N2 yield. In-pile autoclave measurements indicated little radiation-induced back reaction of the nitrogen.