The fractal nature of the surface of uranium dioxide: A resolution of the short-lived/stable gas release dichotomy

Journal of Nuclear Materials

Volumn 295, Issue 2-3, 2001, Pages 133-148

  White, R J ^a  

^a OECD HALDEN REACTOR PROJECT   (Norway)

Author keywords

[No Author keywords available]

Indexed keywords

FISSION REACTIONS; FRACTALS; MATHEMATICAL MODELS; THERMAL DIFFUSION IN SOLIDS;

HALDEN GAS FLOW;

URANIUM DIOXIDE;

EID: 0035366092     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(01)00571-2     Document Type: Article

References (28)

1. The diffusion coefficient for fission gas atoms in uranium dioxide
2. 85Kr as a method of assessing fission gas release in CAGR fuel pins
3. The reliability of on-line fission gas release measurements in the study of fuel interlinkage and resintering phenomena
4. 2
5. 2 fuel and its application to the X-2-f loop test
6. 85Kr in the gas flow rig IFA-504
7. The communication of fission products in the interior of a fuel rod with particular emphasis on recent tests on the IFA-430 gas flow rig
8. An investigation of the intra-granular fission gas bubble distributions in CAGR fuel following power ramps in the Halden reactor
9. 2 fuel
10. The power and burn-up dependence of thermal and fission product release phenomena deduced from fuel irradiated in the gas flow rigs IFA-430 and IFA-504
11. An evaluation of diffusion coefficient data obtained from the start-up ramp of IFA-563 and comparison with data from the gas flow rigs IFA-504 and IFA-558