Head-end reprocessing studies with irradiated high temperature gas-cooled reactor (HTGR) fuels Page: 3 of 6
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was a peak of 7.11, with a mean value of 5.64%. Fifty ruel rods, 621.0 3 ,
were used for this studw.
The fuel rods were visual': inspected, crushed, and burned in :he
fluidized-bed Drimar! burner at 3730C in 93% ]-5% 02 at a fluidizina velaciy
of 0.3 n/s. The cyclone fines and filter fines, co-ecte- from :te or-gas
during the burning operation, were weighed and analyzed. The burner product
was weighed, and the fertile fraction (bare Th0Q microspneres) was separated
235
from the fissile fraction (Sic coated, 3 UC, particles) by dissolving in 13 M
HNO -0.1 Al -0.05 F (Thorex reagent). The insoluble fraction was sieved
through a 60-mesh sieve (250 _n) to recover rae coated parricles frot tne
insoluble fission -r3durs. The insolul' fraction and samples of the disS'olr"
solution were analyzed. The --rd articles were processed b' crusnn in
roll crusher with a 250 .M gap and by burning in the fluidized--ed seconar':
burner at 375'C in 502 . 20%0 at a velcit' or 0.76 m/s. The burner product
was weighed and dissolve., in Thorex reagent. The -soluble residue was dried
and weighed. Samoles of the dissolver selutica and residue were sumittea for
analt'ses.
The e'-eriaecnt was analvzad b: three methods: (I) weight balances measured
for each operation, (2) carbon balance calculations based on in-line flow ac :n-
line 0 and CO analyzers, and (3) heavy metals and missionn product daa oaained
b'; analytical ::ethods. The results of these methods were compared witi each other
and with the expected values based on fuel fabrication parameters :an rae
irradiation history.3
Calculations of carbon balances from on-line instrumentation showed tha
307.S g of carbon could be accounted for in the off-gases from the primary
burner. The expected weight loss was 303 g. The primary burner product ash,
however, was about 20 ' short of the expected value. The SiC coated particle-1y -
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Fitzgerald, C.L. & Vaughen, V.C.A. Head-end reprocessing studies with irradiated high temperature gas-cooled reactor (HTGR) fuels, article, January 1, 1980; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1060744/m1/3/: accessed March 28, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.