scholarly journals Distribution of fission products in Peach Bottom HTGR fuel element E11-07

1977 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.C. Bate
Keyword(s):  
Fuel Element ◽  
Fission Products ◽  
Htgr Fuel

scholarly journals Distribution of fission products in Peach Bottom HTGR fuel element E14-01

1977 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.L. Fairchild
Keyword(s):  
Fuel Element ◽  
Fission Products ◽  
Htgr Fuel

scholarly journals Distribution of fission products in Peach Bottom HTGR fuel element F03-01

1978 ◽  
Author(s):  
F.F. Dyer ◽  
R.P. Wichner ◽  
W.J. Martin ◽  
L.L. Fairchild
Keyword(s):  
Fuel Element ◽  
Fission Products ◽  
Htgr Fuel

scholarly journals Distribution of fission products in Peach Bottom HTGR fuel element E01-01

1978 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.L. Fairchild
Keyword(s):  
Fuel Element ◽  
Fission Products ◽  
Htgr Fuel

scholarly journals Distribution of fission products in Peach Bottom HTGR fuel element F05-05

1979 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.L. Fairchild
Keyword(s):  
Fuel Element ◽  
Fission Products ◽  
Htgr Fuel

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 Uniformity Assessment of TRISO Fuel Particle Distribution in Spherical HTGR Fuel Element Using Voronoi Tessellation and Delaunay Triangulation

2018 ◽  
Vol 2018 ◽  
pp. 1-6 ◽  
Author(s):  
Libing Zhu ◽  
Xincheng Xiang ◽  
Yi Du ◽  
Gongyi Yu ◽  
Ziqiang Li ◽  
...  
Keyword(s):  
Fuel Element ◽  
Delaunay Triangulation ◽  
Nearest Neighbor ◽  
Voronoi Tessellation ◽  
Fission Products ◽  
Fuel Particle ◽  
Volume Distribution ◽  
Triso Fuel ◽  
Triso Particles ◽  
Log Normal

Nonuniform distribution of tri-structural-isotropic (TRISO) fuel particles in a spherical fuel element (SFE) may increase the failure probability of the SFE in the high-temperature gas-cooled reactor, leading to the release of fission products. To evaluate the uniformity of the TRISO particles nondestructively, 3-dimensional cone-beam computed tomography is used to image the SFE, and TRISO particles are segmented. After TRISO particle positions are identified, the Voronoi tessellation and Delaunay triangulation are used to extract several geometric metrics. Results indicate that both the Voronoi volume distribution and the nearest neighbor-distance distribution follow the log-normal distributions, which provide strong evidence that the TRISO particles are approximately randomly uniformly distributed. Further study will be focused on validating the conclusion with more SFE data.

TESTING THE FILTERING PROCESS FOR SPENT ZINC MELT AFTER REMOVAL OF FUEL CLADDING WITH THE BOR-60 REACTOR SNF NITRIDE

2017 ◽  
Vol 18 (1) ◽  
pp. 25-28
Author(s):  
M. A. Kuzin ◽  
Keyword(s):  
Fuel Element ◽  
Spent Nuclear Fuel ◽  
Material Selection ◽  
Fission Products ◽  
Filter Material ◽  
Laboratory Apparatus ◽  
Fuel Cladding ◽  
Fuel Element Cladding ◽  
Intermetallic Particles ◽  
Selection For

Verification results of filtering process effectiveness of a zinc melt obtained after solving a fuel element cladding of the BOR-60 reactor with nitride spent nuclear fuel (SNF) in it are presented. The test was carried out in a laboratory apparatus for cleaning the zinc melt from slurries of fission products, fuel and intermetallic particles in a hot cell. A filter material selection for the filter elements is discussed. The possibility of using the filtering operation in compliance with a ratio of structural materials to zinc for regeneration of zinc after removal in it the fuel element cladding.

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