The release of fission products from uranium oxycarbide fuel in simulated HTGR fuel elements during irradiation in the HFR Petten over a range of temperatures and with periodic injections of water vapor
An irradiation experiment (HFR-B1) was conducted in the High Flux Reactor (HFR) Petten with fuel elements containing HTGR coated particles of uranium oxycarbide (UCO) fuel, 8.9% of which had exposed fuel kernels. This provided a known source for the study of the release of fission products from fuel kernels. Three separated and independently operated capsules with on-line monitoring of gaseous release were irradiated simultaneously under a variety of conditions. During the irradiation, measurements were made of released kryton and xenon isotopes and, in capsule 3, of the reaction products CO, CO(2), H(2), H(2)O and CH(4) resulting from graphite hydrolysis.
Bibliographic Reference: Paper presented: Jahrestagung Kerntechnik, Bonn (DE), May 3-7, 1992
Availability: Available from (1) as Paper EN 36566 ORA
Record Number: 199210194 / Last updated on: 1994-12-02
Original language: en
Available languages: en