Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors

To study behaviors of zircaloy-clad fuel during loss-of-coolant accidents in PWR, simulated fuel rods having five pressure levels were heated in steam or vacuum at heating rates between 3 and 47°C/sec. The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture open...

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Veröffentlicht in:	Journal of nuclear science and technology 1978-10, Vol.15 (10), p.736-744
Hauptverfasser:	FURUTA, Teruo, KAWASAKI, Satoru, HASHIMOTO, Masao, OTOMO, Takashi
Format:	Artikel
Sprache:	eng
Schlagworte:	atmosphere burst fuel cans fuel rods heating hydrogen loss of coolant reactor accidents steam temperature dependence thickness vacuum states zircaloy zirconium oxides
Online-Zugang:	Volltext
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