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Transient Behavior of TRIGA, a Zirconium-Hydride, Water-Moderated Reactor

Richard Stone, H. P. Sleeper, J. R., Ralph, H. Stahl, Gordon West

Nuclear Science and Engineering / Volume 6 / Number 4 / October 1959 / Pages 255-259

Technical Paper / dx.doi.org/10.13182/NSE59-A28840

This paper describes the transient behavior of TRIGA, a light-water-cooled reactor using fuel-moderator elements composed of uranium and zirconium hydride. The large, prompt negative temperature coefficient—an inherent characteristic of these fuel-moderator elements—limits reactor power transients primarily by means of fuel-element temperature rise rather than by void formation in the core. Step reactivity insertions of up to 1.6% resulted in peak powers of 250 Mw with no detectable boiling of the core water or expulsion of water from the core.