First Report on Apparatus to Simulate In-Reactor Transient Heating Conditions in Oxide Fuel Columns
- 1 November 1973
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 20 (2) , 114-123
- https://doi.org/10.13182/nt73-a31347
Abstract
An apparatus has been developed that simulates, out-of-reactor, both in-reactor thermal gradients and heating rates in oxide fuel pellet stacks through direct electrical heating. Preliminary results of tests of both steady-state and transient operation indicate that fuel phenomena and fuel microstructures similar to those observed in actual in-reactor transients can be produced.Keywords
This publication has 3 references indexed in Scilit:
- Radiation‐Induced Creep of UO2Journal of the American Ceramic Society, 1973
- Creep behavior of ceramic nuclear fuels under neutron irradiationJournal of Nuclear Materials, 1972
- Electrical Conductivity of Uranium DioxideJournal of the American Ceramic Society, 1967