Quarterly Progress Report on Fission Product Behavior in LWRs for the Period April-June 1979

Technical Report · Mon Oct 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/5853304· OSTI ID:5853304

Malinauskas, A. P. ^[1]; Lorenz, R. A. ^[1]; Collins, J. L. ^[1]; Osborne, M. F. ^[1]; Towns, R. L. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Tests BWR-2 and BWR-3 were performed during this report period; each test employed segment 4 from fuel rod F-6, bundle PH-006, which had been irradiated to approx. 12,7000 MWd/MT during cycle 1 of the Peach Bottom-2 boiling water reactor (BWR). The test segment was pressure-ruptured at 850°C in test BWR-2 and later heated at 1200°C for 25 min in flowing steam in test BWR-3. The results obtained to date in the BWR Test Series are summarized.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5853304
• Report Number(s): ORNL/NUREG/TM--348; NUREG/CR-1061
• Country of Publication: United States
• Language: English

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