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Robin Grimes part
| Question | Answer |
|---|---|
| Components for the Nuclear Fuel Assembly | The fissile substance A host matrix - usually an oxide or metal metal cladding - to protect and prevent fission gases escaping. Additional fittings |
| fuel compositions | metal/oxide/nitride/carbide/flouride |
| fuel forms | single phase/solid solution/composite |
| fuel packing | pellet/particle/liquid |
| nuclear fuel cycle | mine//conversion//enrichment//fabrication//reactor//storage //repro and recyle |
| alterntive fuel cycles | once through300000yrs modified open (actinide and fission product waste)9000yrs fully closed (burn actinides)30yrs |
| influence of fission products on fuel performance | Chemical Volumetric Thermal |
| 5 metal particles | Mo, Ru, Rh, Pd, Tc |
| Dissolved within the uranium dioxide matrix | Ba, Zr, Y and the lanthanides, |
| Precipitated as a separate oxide phase | Ba, Sr, Sn, Zr, Mo, Cs, Rb |
| Volatile elements | Kr, Xe, Te, I, Br, Cs |
| What Do We Want | high burn-up structural/chemical stability at high temp and radiation Effective cladding int reprocessing proliferation resistant 50:50 Transuranic to uranium ratio Fabrication simple Optimise thermal conductivity Retain fission products |
| possible sites/structures that might accommodate fission products in polycrystalline UO2 | Dissolved within the material, precipitated in an oxide phase, precipitated within metal particles or precipitated within microvoids Volatile elements either released from the UO2 matrix or held within small bubbles |
| Xe and Kr Fission Gas Release | insoluble intragranular bubbles. gas moves back into the lattice, to grain boundaries by solid state and radiation enhanced diffusion intergranual bubbles at grain boundaries grow and coalese - inter-connected pathways vent to fuel – clad gap. |
| “apparent” diffusion coefficient iincludes | thermally activated diffusion, radiation assisted diffusion |
| processes that will occur during the burn‐up of fuel that will alter the conductivity | At higher temperatures Frenkel defects, increase in the thermal conductivity. stoichimetry and content of plutonium, additional scattering centres - thermal conductivity decreases porosity reduces the thermal conductivit |
| Universal Radiation Damage Concepts | Displacive radiation damage is initiated upon formation of Frenkel pair defects in the lattice. Frenkel pair defects in irradiated material > equilibrium thermodynamic conc response is determined by the fate of these excess Frenkel pairs |
| Chemical Rate Theory: fate of irradiation-induced point defects | production and recombination. anitsite formation. nucleation and growth rate of interstitial loops/dislocations. |
Created by:
emmaperry
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