Oxide fuel element and blanket element development programs. Quarterly progress report, April-June 1978
Not Given Author
DIGCLAIMEB Nc1th.r ulcr Uili,dl Sro:cl Covcrnmant mr any . rgpm ther~lf. "gr any of their employee% makesanv wurranty. erpreu or implied. or arsum any legal liability or rsmnsibiiity for the amraw. mmpleieness, or v r e f v l n~~ of any infarmaiion. apparatus. ~r o d u a . or procea dircloM, or reprerents ihsl its u r vnruld not infringe privutcly owned rights. Reference herein to env rpmilic mmmrrixl nrr.l~lrl nmm,=x, pr by irsdo name. trademark. manulaclurer, or oiherwir. doer not nm-rily
... titute or imply its endor*menl. remmmendallbn. ar l w u~~l y uv tvc Usdcul Stater Goveinment or any agency thereof. The vie-and opinions of au1ho.r expreued herein do ml 1 OISTRIBUTIO~I OF THIS [IOCUhIEHT I S UNLIMITED -----. --. ---------. . . -. .-,----., s -----.---9 b) Experiment F9E -D. E. Plumlee, J. A. Ellis As part o f the F~E examination, the total fuel column for .the F9E-41' fuel pin was dissolved (except' for three metal lographic samples) and the gasses released were analyzed at LASL. These measurements indicated* that 1 8 . 1 2~~ (OOC) of f i~s i o n .~a s was retained in the fuel at the end of the irradiation. Fission gas volume of 1 6 9 . 6 2~~ ( 0 ' ) was obtained from the plenum . . of the fuel pin. These results indicate that roughly 10% of the fission gas . . . is retained in the fuel for the F9E fuel pins. The F9E fuel' pins operated . . in the range of 14 kw/ft at the start of irradiation .to 12 kw/ft at the end . .. of their irradiation to a peak burnup of about 11.5%. Based upon measured burnup of the fuel for the F9E-41.pin, the above fission gas volume corresponds to a yield of 0.246 gas atoms/fission. These results are somewhat lower than anticipated. Fissioning in the'fuel for the F9E-41 fuel pin was primarily due to U235 and Pu239. . Fission yields quoted for these isotopes are in' the range of 0.252-0.255 gas atoms/fission. c ) High cl addi ng .Temperature, Run-Beyond-Breach Experiment Fl 1 A JX141A, B) - The FllA experiment is a high cladding temperature irradiation, of unencapsulated mixed-oxide fuel rods in EBR-I1 . ~hirt~-seven rods in bypass flow subassembly XI41 began irradiation in run 60. They were discharged following run 68 at peak burnup of %5%. Interim examination showed no evidence of cladding breach, Nn anomalous condition was found 'in any of the three (Xl41) pins examined at LASL. The remaining 34 F11A rods, plus three F9E pins, were reconstituted as subassembly X141A at run 79. At the end of run BOA, fission gas activity appeared in the reactor cover gas, and EBR-I1 was shut down. Subassembly X141A was' identified as the leaker by cover gas analysis corresponding to the Fl lA xenon gas tag. subsequent gamma scanning of the pin plena. showed Fl l A-41 .' *The gas in the 1.5 inch total length of microscopic sections (out of 1.3.5 inches .of fuel ) was estimated from measurements on adjacent sections. * Phase 1-was a 10-day exposure (0.3% burnup) a t a maximum power of 57 kw/m (17.3 kw/ft) t o provide some fuel restructuring f o r selected rods during the fuel melting irradiation of Phase I 1 which involved a 10-minute exposure a t 69 kw/m (20.9 kw/ft) maximum. Subsequently, selected rods were irradiated f o r 17 days (0.5% b u r n u p ) in Phase I11 a t ' 55 kw/m (16.6 kw/ft) maximum.,. . **+ -.002 inch f o r void, -. + .005 inch f o r EGG and CGG, -+ .001 inch f o r fuel 0.d.