Published August 1967 | Version v1
Journal article

Recoil release of fission-gas from UO2

  • 1. Hitachi, Ltd., Central Research Laboratory, Kokubunji, Tokyo (Japan)

Description

The fission-gas released from in-core UO2 pellets was investigated with the helium-swept fuel irradiation facility installed in the Hitachi Training Reactor. It was found that the release rate of fission-gas increased gradually as irradiation continued for 5 hr under a constant thermal neutron flux of 1.0 x 1012 n/cm2•sec and at a fuel temperature of about 150℃. This observation indicates that a recoil-activated release mechanism may be more effective than direct-recoil release in the case of clad fuel in the region of temperature where fission-gas release rate is temperature independent. (author)

Availability note (English)

Available from DOI: https://doi.org/10.1080/18811248.1967.9732773

Additional details

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo) (Online)
Journal Volume
4
Journal Issue
8
Journal Page Range
p. 387-393
ISSN
1881-1248

Optional Information

Notes
8 refs., 11 figs.