b'with a gas inlet and electric leads.min to 650 . At 460the sample[4.]M.S. Veshchunov, V.E. Shestak, On the vacuum side of this flange,disappeared from view. This isModelling of fission gas release these leads are connected to ashown in Figure 3. Evaluation of thefrom irradiated UO2 fuel un-microheater onto which is placed areleased gases further showed 85Krder high-temperature anneal-ceramic holder, AlN or SiC, whichhad been released during the testing. ing conditions, J. Nucl. Mater. contains the sample. For the TiHxThis first heating of nuclear fuel in430 (2012) 8289. doi:https://foil test AlN was used, while the fuelthe Fuel Heating and Visualizationdoi.org/10.1016/j.jnuc-test used a 3D-printed SiC holder. ItSystem demonstrates a key capabilitymat.2012.06.048.was found that the AlN holder wasat ORNL to evaluate and observe[5.]L.O. Jernkvist, A review of more durable but the SiC holderfission gas release in local sections ofanalytical criteria for fission was more readily manufacturablenuclear fuel. Additional capabilitygas induced fragmentation of into the required form. Because ofimprovements are being investigatedoxide fuel in accident conditions, cracking concerns in the SiC, thein data collection and sampleProg. Nucl. Energy. 119 (2020) maximum temperature of the initialretention for future experiments. 103188. doi:10.1016/j.pnu-fuel test was set to 650and the TiHx sample was able to be heatedReferences:cene.2019.103188.to 760 . [1.]C. Le Gall, S. Reboul, L. Fayette, T.[6.]M. Tonks, D. Andersson, R. Deva-To test large gas volume detection,Blay, I. Zacharie-Aubrun, I. Flines,nathan, R. Dubourg, A. El-Azab, the TiHx sample was prepared withK. Hanifi, I. Roure, P. Bienvenu,M. Freyss, F. Iglesias, K. Kulacsy, G. a calculated 0.21 mmol H 2 , sufficientF. Audubert, Y. Pontillon, J.L.Pastore, S.R. Phillpot, M. Welland, to create a pressure change of 900Hazemann, MOX fuel micro- Unit mechanisms of fission gas Pa within the chamber. Heating thestructural evolution during therelease: Current understanding sample at rate of 20 /min to 760 .VERDON-3 and 4 tests, J. Nucl.and future needs, J. Nucl. Mater. Optical observation of the sampleMater. 531 (2020). doi:10.1016/j. 504 (2018) 300317. doi:10.1016/J.throughout the test can be seenjnucmat.2020.152015. JNUCMAT.2018.03.016.in Figure 2. In this test, the visible[2.]T. Vidal, L. Gallais, R. Burla, F.[7.]M. Bales, A. Chung, J. Corson, area of the foil sample was partiallyMartin, H. Capdevila, S. Clment,L. Kyriazidis, Interpretation of shielded by the alumina insulatedY. Pontillon, Optical system forResearch on Fuel Fragmentation, thermocouple wires. Clear gasreal-time monitoring of nuclearRelocation, and Dispersal at High evolution was found in this test withfuel pellets at high tempera- Burnup, Res. Inf. Lett. Off. Nucl. a calculated gas release of 0.18 mmolture, Nucl. Eng. Des. 357 (2020)Regul. Res. (2021) RIL 2021-13.H 2 , similar to the estimated 0.21110383. doi:10.1016/J.NUCENG- [8.]N. Capps, Y. Yan, A. Raftery, Z. mmol H 2calculated initially to be inDES.2019.110383. Burns, T. Smith, K. Terrani, K. the sample. [3.]Y. Pontillon, M.P. Ferroud-Plattet,Yueh, M. Bales, K. Linton, Inte-The fuel test was accomplished withD. Parrat, S. Ravel, G. Ducros, C.gral LOCA fragmentation test on 0.8 mm 3fuel piece with a burnupStruzik, I. Aubrun, G. Eminet, J.high-burnup fuel, Nucl. Eng. Des. of 84 GWd/kgU. This fuel was takenLamontagne, J. Noirot, A. Harrer,367 (2020) 110811. doi:10.1016/j.from the same fuel segment that wasExperimental and theoreticalnucengdes.2020.110811.LOCA tested as NA#2 in Referenceinvestigation of fission gas release [8].This sample was removed fromfrom UO2 up to 70 GWd/t under the outer edge of a fuel pellet bysimulated LOCA type conditions: cutting three grooves around theThe GASPARD program, Proc. sample normal to the interface2004 Int. Meet. LWR Fuel Perform. and then cutting out a 1 mm thick(2004) 490499.slice. This piece was loaded onto the SiC holder and heated at 25 /2022|AFC ACCOMPLISHMENTS 99'