Irradiation Performance of Coated Fuel Particles with Fission Product Retaining Kernel Additives

1982 ◽  
Vol 56 (1) ◽  
pp. 81-92 ◽  
Author(s):  
R. Förthmann
Author(s):  
R. J. Lauf

Fuel particles for the High Temperature Gas-Cooled Reactor (HTGR) contain a layer of pyrolytic silicon carbide to act as a miniature pressure vessel and primary fission product barrier. Optimization of the SiC coating with respect to fuel performance involves four areas of study: (a) characterization of as-deposited SiC coatings; (b) thermodynamics and kinetics of chemical reactions between SiC and fission products; (c) irradiation behavior of SiC in the absence of fission products; and (d) the combined effects of irradiation and fission product interactions. This paper reports the behavior of SiC deposited on fissile fuel particles and irradiated to fast neutron fluences typical of HTGR fuel at end-of-life.


2000 ◽  
Vol 131 (1) ◽  
pp. 36-47 ◽  
Author(s):  
Kazuo Minato ◽  
Kazuhiro Sawa ◽  
Toshio Koya ◽  
Takeshi Tomita ◽  
Akiyoshi Ishikawa ◽  
...  

1970 ◽  
Vol 8 (5) ◽  
pp. 417-431 ◽  
Author(s):  
P. E. Reagan ◽  
E. L. Long ◽  
J. G. Morgan ◽  
J. H. Coobs

1979 ◽  
Vol 87 (2-3) ◽  
pp. 367-374 ◽  
Author(s):  
Kousaku Fukuda ◽  
Katuichi Ikawa ◽  
Kazumi Iwamoto

1997 ◽  
Vol 249 (2-3) ◽  
pp. 142-149 ◽  
Author(s):  
Kazuo Minato ◽  
Toru Ogawa ◽  
Kousaku Fukuda ◽  
Hajime Sekino ◽  
Isamu Kitagawa ◽  
...  

2009 ◽  
Vol 385 (2) ◽  
pp. 372-386 ◽  
Author(s):  
M. Barrachin ◽  
R. Dubourg ◽  
M.P. Kissane ◽  
V. Ozrin

Author(s):  
R. J. Lauf ◽  
D. N. Braski

Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain layers of pyrolytic carbon and silicon carbide, which act as a miniature pressure vessel and form the primary fission product barrier. Of the many fission products formed during irradiation, the noble metals are of particular interest because they interact significantly with the SiC layer and their concentrations are somewhat higher in the low-enriched uranium fuels currently under consideration. To study fission product-SiC interactions, particles of UO2 or UC2 are doped with fission product elements before coating and are then held in a thermal gradient up to several thousand hours. Examination of the SiC coatings by TEM-AEM after annealing shows that silver behaves differently from the palladium group.


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