Oxygen Potentials and Lattice Parameter of Irradiated BWR Fuek

The oxygen potentials and lattice parameter of oxide fuels (UO 2 and UO 2 -2 w/0Gd 2 O 3 ) irradiated in commercial BWRs have been measured by using a solid electrolyte galvanic cell technique and X-ray diffractometry. The fuel burn-up was 13-30 GWd/t for the former measurements and 6-35 GWd/t for t...

Full description

Saved in:
Bibliographic Details
Published inJournal of nuclear science and technology Vol. 28; no. 5; pp. 409 - 417
Main Authors UNE, Katsumi, TOMINAGA, Yasuo, KASHIBE, Shinji
Format Journal Article
LanguageEnglish
Published Taylor & Francis Group 01.05.1991
Subjects
BWR type reactors
fission products
gadolinium oxide
irradiation
lattice defects
lattice parameters
mixed oxide fuels
nonstoichiometry
O/M ratio
oxygen potential
radiation effects
thermodynamic properties
uranium dioxide
Online AccessGet full text

Cover

More Information
Summary:The oxygen potentials and lattice parameter of oxide fuels (UO 2 and UO 2 -2 w/0Gd 2 O 3 ) irradiated in commercial BWRs have been measured by using a solid electrolyte galvanic cell technique and X-ray diffractometry. The fuel burn-up was 13-30 GWd/t for the former measurements and 6-35 GWd/t for the latter. The oxygen potentials at 750°C for irradiated UO 2 ranged from −420 kJ/mol at the fuel rim to −480 kJ/mol at the fuel center. The corresponding values for irradiated U0 2 -2 w/0Gd 2 O 3 ranged from −460 to −540 kJ/mol. The lattice parameter near the fuel rim in the irradiated UO 2 increased with burn-up, and was distinctly larger than that at the fuel center. This lattice dilatation was mainly due to the accumulation of radiation defects, not to a decrease in O/M ratio, and was almost recovered after the annealing at 1,600°C for 5 h.
ISSN:0022-3131
1881-1248
DOI:10.1080/18811248.1991.9731376