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- W2003428498 abstract "Abstract To simulate the nuclear fuel for High Temperature Engineering Testing Reactor (HTTR), fuel compact models using SiC-kernel coated particles instead of UO 2 -kernel coated particles were prepared under the same conditions as those for the real fuel compact. The mechanical and fracture mechanics properties were studied at room temperature. The thermal shock resistance and fracture toughness for thermal stresses of the fuel compact were experimentally assessed by means of arc discharge heating applied at a central area of the disk specimens. These model specimens were then neutron irradiated in the Japan Material Testing Reactor (JMTR) for fluences up to 1.7 × 10 21 n/cm 2 ( E ·> 29 fJ ) at 900° C ± 50° C . The effects of irradiation on a series of fracture mechanical properties were evaluated and compared with the cases of graphite IG-110 used as the core materials in the HTTR." @default.
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- W2003428498 date "1993-07-01" @default.
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- W2003428498 title "Fracture mechanical properties and neutron irradiation effects of fuel compacts for the HTTR" @default.
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- W2003428498 doi "https://doi.org/10.1016/0029-5493(93)90128-v" @default.
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