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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.
Massoud T. Simnad, Fabian C. Foushee, Gordon B. West
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 31-56
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31537
Articles are hosted by Taylor and Francis Online.
TRIGA fuel was developed around the concept of inherent safety. A core composition was sought that had a large prompt negative temperature coefficient of reactivity such that if all the available excess reactivity were suddenly inserted into the core, the resulting fuel temperature would automatically cause the power excursion to terminate before any core damage resulted. Experiments have demonstrated that zirconium hydride possesses a basic neutron-spectrum-hardening mechanism to produce the desired characteristic. Additional advantages include the facts that ZrH has a good heat capacity, that it results in relatively small core sizes and high flux values due to the high hydrogen content, that it has excellent fission-product retentivity and high chemical inertness in water at temperatures up to 100°C, and that it can be used effectively in a rugged fuel element size. Tens of thousands of routine pulses to the range of 500 to 800°C peak fuel temperatures have been performed with TRIGA fuel, and a core was pulse-heated to peak fuel temperatures in excess of 1100°C for hundreds of pulses before a few elements exceeded the conservative tolerances on dimensional change.