An Advanced Simulation based 3D Framework and Toolkit for Fire Protection and Fire Probabilistic Risk Analysis
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42 ENGINEERING↗
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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Experiment Assembly and Testing in Hot Cell in Support of Advanced Fuels Irradiation Testing
Follow-on experimentation of irradiated nuclear fuel is critical to understanding fuel behavior at different stages of the fuel lifecycle. Transient experiments using fuel with high burnup can enlarge understanding of fuel fragmentation, relocation and dispersal under various reactor accident situations. Assembling experiments with such fuel requires remote operations.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Enabling the Broader use of MOOSE for Nuclear Energy and Other Simulation
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42 ENGINEERING↗
High-temperature safety testing of irradiated AGR-1 Triso fuel - 18595
Three irradiated AGR-1 UCO TRISO fuel compacts were tested using a time-varying temperature profile with a peak temperature of 1695 deg. C, simulating a conduction cooldown event in a gas-cooled reactor. Of the approximately 12,378 fuel particles in this test, less than a single particle s inventory of Cs, Eu, Kr or Sr was released during the test, indicating that all TRISO layers in all particles remained intact. The transient nature of the test did not stress the fuel beyond what has been observed in isothermal tests within the same temperature range. It is anticipated that tests of this nature will be repeated using fuel from subsequent irradiations (e.g. AGR-2, which has both UCO and UO{sub 2} fuel compacts, and AGR-5/6/7, which has only UCO fuel). (authors)
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Electromagnetic Launch Modification
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43 PARTICLE ACCELERATORS↗
Post-irradiation 1600°C Heating Test of AGR-1 UCO Fuel Kernels
Five bare kernels were selected from the U.S. Advanced Gas Reactor (AGR) 1 irradiation experiment Compact 5-3-1 to perform post-irradiation safety tests. The safety test involved heating the kernels in the Fuel Accident Condition Simulator (FACS) furnace in the inert atmosphere to a peak temperature of 1600°C and isothermally holding at this temperature for about 47 hours while collecting fission products released. This test was to assess the retention of fission products in bare kernels without the effects of the other TRISO layers (buffer, IPyC, SiC, and OPyC) or the graphitic matrix material. The bare kernels released nearly 100% of cesium and antimony, while they were able to maintain about 30% of europium, 50% of strontium, and the majority of cerium and ruthenium. In addition, about 48% of the calculated inventory of Kr-85 released during the test, indicating that kernels were capable of retaining a considerable fraction of fission gas K-85 during irradiation.
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Post-irradiation 1600°C Heating Test of AGR-1 UCO Fuel Kernels
The Advanced Gas Reactor Fuel Development and Qualification (AGR) Program was established to perform research and development on tristructural isotropic (TRISO) coated-particle fuel to support deployment of high temperature gas-cooled reactors (HTGRs) . This talk will discuss the results from a post-irradiation heating test of five individual fuel kernels extracted from four TRISO fuel particles that were deconsolidated from an irradiated AGR-1 fuel compact.
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Refabrication of HERA-HBU-1
Refabrication of a commercially irradiated fuel segment has been completed for the HERA-HBU-1 experiment. This presentation recounts the refabrication process, and the results of performing refabrication in preparation for the HERA-HBU-1 experiment.
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗