Actions for Observation of Porosity Reduction in a Densification-Prone Test Fuel Rod [electronic resource] : Data and Analysis

Email RIS file
Bookmark
Report an Issue

Observation of Porosity Reduction in a Densification-Prone Test Fuel Rod [electronic resource] : Data and Analysis

Published
Richland, Wash. : Pacific Northwest National Laboratory (U.S.), 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Pacific Northwest National Laboratory (U.S.) and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access
Free-to-read Unrestricted online access
Summary
Instrumented fuel assembly (IFA)-431 was irradiated in the Halden Boiling Water Reactor (HBWR) for the purpose of extending the steady-state data base. Rod 6 of this assembly began irradiation with UO₂ fuel of 92% theoretical density (TD) that was unstable with respect to in-reactor densification. Thermal resintering tests resulted in a final density of 95.3% TD while post-irradiation examination (PIE) indicated a final density of 96.5% TD. Observed microstructural changes were consistent with published densification studies; there was a marked depletion of submicrometer diameter pores and total pore volume. However, grain size increased only slightly, indicating that internal pellet temperatures did not reach the 1875K applied in resintering tests. Oensification was observed to increase the temperatures in rod 6, but temperatures did not become as high as for a sibling rod that simulated instantaneous densification. Temperatures calculated with U.S. Nuclear Regulatory Commission (NRC) fuel performance computer codes were generally higher than observed temperatures.
Report Numbers
E 1.99:pnl-3782
E 1.99: nureg/cr-2042
nureg/cr-2042
pnl-3782
Subject(s)
Note
Published through SciTech Connect.
10/01/1981.
"pnl-3782"
" nureg/cr-2042"
Lanning, D. D.; Cunningham, M. E.; Daniel, J. L.
Office of Nuclear Regulatory Research
Funding Information
DE-AC06-76RL01830
View MARC record | catkey: 14363149