Published January 1966 | Version v1
Report

Reaction of Flowing Steam with Stainless Steel-Clad and Zircaloy-2-Clad, UO2-Core Simulated Fuel Elements

Description

Experiments designed to simulate the environment of the fuel in a water-cooled power reactor following a loss-of-coolant accident have continued. In such a situation, the fuel would be subjected to a slowly rising temperature as a result of the heat generated by fission product decay. Typical accident calculations (ANL-6925, p. 215 and ANL-7055, p. 192) have indicated that, in the absence of effective countermeasures, average fuel temperatures would reach the melting point of the metal cladding in about 10 min.

Part of:
Chemical Engineering Division Semiannual Report

Additional details

Publishing Information

Imprint Title
Chemical Engineering Division Semiannual Report
Imprint Pagination
236 p.
Journal Page Range
p. 164-166
Report number
ANL--7225

Optional Information

Notes
3 ills.