Influence of radiation damage on diffusion of fission products in silicon carbide

2013 ◽  
Vol 10 (2) ◽  
pp. 208-215 ◽  
Author(s):  
Erich Friedland ◽  
Thulani Hlatshwayo ◽  
Nic van der Berg
Keyword(s):  
Silicon Carbide ◽  
Radiation Damage ◽  
Fission Products

Irradiation behavior of pyrolytic silicon carbide

1983 ◽  
Vol 41 ◽  
pp. 72-73
Author(s):  
R. J. Lauf
Keyword(s):  
Silicon Carbide ◽  
Fission Products ◽  
Thermodynamics And Kinetics ◽  
Neutron Fluences ◽  
Fuel Particles ◽  
Sic Coatings ◽  
Irradiation Behavior ◽  
Kinetics Of ◽  
Htgr Fuel

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 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) combined effects of irradiation and fission products. This paper reports the behavior of SiC deposited on inert microspheres and irradiated to fast neutron fluences typical of HTGR fuel at end-of-life.

scholarly journals Radiation damage thin coating of silicon carbide

2014 ◽  
Vol 510 ◽  
pp. 012010 ◽  
Author(s):  
Anna Bondareva ◽  
Galina Zmievskaya ◽  
Tatjana Levchenko
Keyword(s):  
Silicon Carbide ◽  
Radiation Damage ◽  
Thin Coating

Instrumentation for X-Ray Diffraction Studies of Highly Radioactive Samples

1958 ◽  
Vol 2 ◽  
pp. 107-115
Author(s):  
Vincent G. Scotti ◽  
James I. Mueller ◽  
John J. Little
Keyword(s):  
Radiation Damage ◽  
Gamma Ray ◽  
Pulse Height ◽  
Fission Products ◽  
Analytical Tool ◽  
Nuclear Engineering ◽  
X Ray Diffraction ◽  
X Ray ◽  
Background Ratio ◽  
Gamma Ray Irradiation

AbstractWith the advent of nuclear engineering, x-ray diffraction has become an important analytical tool in the study of radiation damage due to neutron and gamma-ray irradiation. The materials under study in this work have rdioactive levels up to 40 R/hr. at 17 centimeters combined β and γ. The activity of the various samples under study may be due to (n, γ) reactions or fission products or both.Data are presented to illustrate the use of sample shielding, detector shielding pulse height discrimination and the combination of all three aids in an effort to attain the most favorable peak to background ratio.

scholarly journals Influence of radiation damage on xenon diffusion in silicon carbide

2014 ◽  
Vol 332 ◽  
pp. 415-420 ◽  
Author(s):  
E. Friedland ◽  
K. Gärtner ◽  
T.T. Hlatshwayo ◽  
N.G. van der Berg ◽  
T.T. Thabethe
Keyword(s):  
Silicon Carbide ◽  
Radiation Damage

scholarly journals Influence of radiation damage on strontium and iodine diffusion in silicon carbide

2012 ◽  
Vol 425 (1-3) ◽  
pp. 205-210 ◽  
Author(s):  
E. Friedland ◽  
N.G. van der Berg ◽  
J.B. Malherbe ◽  
E. Wendler ◽  
W. Wesch
Keyword(s):  
Silicon Carbide ◽  
Radiation Damage ◽  
Iodine Diffusion

Radiation Damage in Diamond and Silicon Carbide

1956 ◽  
Vol 103 (5) ◽  
pp. 1184-1192 ◽  
Author(s):  
W. Primak ◽  
L. H. Fuchs ◽  
P. P. Day
Keyword(s):  
Silicon Carbide ◽  
Radiation Damage

scholarly journals Irradiation performance of pyrolytic silicon carbide coatings on fissile fuel particles

1984 ◽  
Vol 42 ◽  
pp. 418-419
Author(s):  
R. J. Lauf
Keyword(s):  
Silicon Carbide ◽  
Fission Product ◽  
Fission Products ◽  
Carbide Coatings ◽  
Fuel Particles ◽  
Irradiation Performance ◽  
Sic Coatings ◽  
Irradiation Behavior ◽  
Kinetics Of

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.

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