Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1978.9735581
Reference14 articles.
1. Emmerich, K. M. 1969.“Application Related Phenomena for Zirconium and its Alloys”, ASTM STP 458 252ASTM.
2. Comparison of Rupture Data from Irradiated Fuel Rods and Unirradiated Cladding
3. Effects of Heating Rate and Pressure on Expansion of Zircaloy Tubing During Sudden Heating Conditions
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