Applications of thermodynamics for predicting and understanding the performance of fast breeder reactor oxide fuels

Leitnaker, J.M.

doi:10.1016/0022-3115(74)90119-6

Cited by 17 publications

(6 citation statements)

References 12 publications

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“…7.6 were calculated by assuming a constant neodymium valence of 3+; this approach demonstrates the significant effect of the U-RE interaction on promoting the uranium valence above 4+. Leitnaker 15 has reported the existence of Uo.6Euo.4O1.95 at 900° C and at a CO/ C0 2 ratio of 10; these data are shown in Fig. 7.6 and coincide exactly with Wadier's results.…”

Section: Review Of Oxide Fuel Chemistrysupporting

confidence: 83%

Irradiation performance of HTGR fertile fuel in HFIR target capsules HT-12 through HT-15. Part I. Experiment description and fission product behavior

Kania¹,

Lindemer²,

Morgan³

et al. 1977

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Sixteen types of Biso-coated designs, on TI1O2 kernels, were irradiated in High Flux Isotope Reactor target capsules HT-12 through HT-15. This report addresses the description of the experiment and extensive postirradiation analyses and experiments to determine fertile-particle burnup, fuel coating failures, and fission product behavior. Several low-temperature isotropic (LTI) pyrocarbon coatings, which "survived" according to visual inspection, were shown to have developed permeability during irradiation. These particles were irradiated at temperatures si 250° C and to burnups >8% fission per initial heavy-metal atom (FIMA). No evidence of permeability was found in similar particles irradiated at temperatures-1550° C and burnups-16% FIMA. Failures due to permeability were not detectable by visual inspection but required a more extensive investigation by the 1000°C gaseous chlorine leaching technique. Maximum particle surface operating temperatures were found to be approximately 300° C in excess of design limits of 900° C (low-temperature magazines) and 1250°C (high-temperature magazines). The extremes of high temperatures and fast neutron fluences up to 1.6 X 10 22 neutrons/cm 2 produced severe degradation and swelling of the Poco* graphite magazines and sample holders. The amount of krypton + xenon released into the void space in the kernels of intact TI1O2 particles was found to be primarily burnup dependent and reached about 90% at design burnup. Oxygen release per fission was found to be a function of temperature and burnup with the empirical expression 0//= (a + bf) ex.p(-Q/RT) representing data from TI1O2 particles irradiated in the target facility and stored out-of-reactor for about two years. The oxygen release was significantly affected by the interaction of urania with sesquioxides of yttrium plus rare-earth elements. The irradiated particles showed complete retention of fission products 106 Ru and 144 Ce at the extremes of temperature and bumup, whereas 137 Cs and 125 Sb were lost under the same conditions. Cesium loss was 20 to 40% for bumups of 6 to 16% FIMA in the impermeable coatings and about 65% in particles with defective coatings at the higher temperatures. Cesium loss at the lower temperatures and burnups was <1%. Cesium diffusion coefficients in the bare kernels of the same coated particles ranged from 1 X 10" 17 to 2 X 10"' 5 cm 2 /sec, increasing with burnup. "Chemical Technology Division. tGrade AFX-5Q manufactured by Poco Graphite Inc., a subsidiary of Union Oil Company, Decatur, Texas. "Deposition rates are quoted for ORNL particles only. Mean value ± standard deviation. c Density values for ORNL particles are design values. General Atomic density measurements made on parent particle batch or calculated. e OPTAF values obtained from procedure described in D. W. Stevens, "Optical Anisotropy in Nearly Isotropic Pyrolytic Carbons," pp. 167-68 in 11th Biennial Conference on Carbon, June 4-8, 1973, CONF-730601, Sponsored by the American Carbon Committee and Oak Ridge National Laboratory. ^OR...

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Section: Review Of Oxide Fuel Chemistrysupporting

confidence: 83%

Irradiation performance of HTGR fertile fuel in HFIR target capsules HT-12 through HT-15. Part I. Experiment description and fission product behavior

Kania¹,

Lindemer²,

Morgan³

et al. 1977

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“…Such interpretation could explain the observed distortion and even amorphisation (at 30% Pd content) of the crystalline oxide matrix. Several authors report on the decrease of the UO 2 fluorite unit cell size due to dissolved fission product atoms in irradiated and simulated spent fuels [34,[53][54][55][56]. Lucuta et al, who investigated the microstructural features of SIMFUEL by XRD, ascribe the lack of Pd diffraction peaks to the small concentration of the noble metal in the UO 2 matrix [57].…”

Section: Preparation Of Uo 2 -Pd Thin Films At Room Temperaturementioning

confidence: 97%

Development of fuel-model interfaces: Characterization of Pd containing UO2 thin films

Stumpf¹,

Seibert²,

Gouder³

et al. 2010

Journal of Nuclear Materials

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“…Short-range radial migration of 2-144 RHO-BWI-ST-7 A number of fission products remain in solid solution with UO2. These elements include the actinides and the rare earth elements (0' Boyle and Others, 1969;Leitnaker, 1974). Some SrO may also go into solid solution with UO2 at elevated temperatures (Sari and Others, 1979).…”

Section: 622mentioning

confidence: 99%

Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

Smith¹

1980

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Applications of thermodynamics for predicting and understanding the performance of fast breeder reactor oxide fuels

Cited by 17 publications

References 12 publications

Irradiation performance of HTGR fertile fuel in HFIR target capsules HT-12 through HT-15. Part I. Experiment description and fission product behavior

Irradiation performance of HTGR fertile fuel in HFIR target capsules HT-12 through HT-15. Part I. Experiment description and fission product behavior

Development of fuel-model interfaces: Characterization of Pd containing UO2 thin films

Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

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