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- W158648711 abstract "As a participant in the VIPEX-pressurized water reactor (PWR) international program organized by Belgonucleaire and CEN-SCK (Belgium), Korea Atomic Energy Research Institute had the opportunity to verify the neutron and gamma transport code HELIOS against a PWR critical experiment loaded with high-plutonium-content mixed-oxide (MOX) fuels. Two mock-ups, ALL-MOX and GD-MOX, were investigated at the VENUS critical facility, which consisted of typical 17 X 17 PWR fuel assemblies, driver, and water reflector regions. In the ALL-MOX mock-up core, a standard MOX assembly was loaded at the center of the core, which was surrounded by four UO{sub 2} fuel assemblies. In the GD-MOX mock-up core, the central MOX assembly was replaced with a GD-MOX fuel assembly. Therefore, the only difference between the ALL-MOX and the GD-MOX mock-up was the existence of 20 UO{sub 2} fuel rods bearing Gd{sub 2}O{sub 3} in the central assembly, which made the critical water level higher. For the simulation of a hot-full-power (HFP) moderator condition at room temperature, aluminum microtubes and -rods were inserted into MOX and UO{sub 2} fuel assemblies, respectively. In each mock-up, the critical water level, reactivity effect of water level, axial bucklings, horizontal rodwise fission rate distribution, and detector responses were measured. Themore » horizontal rodwise fission rate distribution was inferred from gamma scanning data.« less" @default.
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- W158648711 date "1997-12-01" @default.
- W158648711 modified "2023-09-27" @default.
- W158648711 title "HELIOS verification using PWR critical experiments loaded with MOX fuels" @default.
- W158648711 hasPublicationYear "1997" @default.
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