Abu Khalid Rivai

Study Plan for Material Corrosion Test in Lead and Bismuth Eutectic at High Temperature

A concept of steam lift pump type lead-bismuth cooled fast reactor (SLPLFR) is proposed as high temperature and high efficiency Pb-Bi cooled fast reactors. Fe-Al alloy-surface treated steels and ceramics of SiC, Si3 N4 and SiC/SiC composites have been chosen as candidates of cladding and structural materials, respectively. A corrosion test plan is proposed, where compatibility of steels applied with Al-Fe alloy-surface treatment and the ceramics will be tested in high temperature Pb-Bi flow. A conceptual design of a test apparatus for the corrosion test is provided.Copyright

Corrosion Behaviors of Al-Steel-Sputtering-Treated Steel and SiC/SiC Composites in High Temperature LBE at Low Oxygen Concentration

Corrosion tests of Al and SS-304-sputtering-surface treated STBA26 (9Cr.1Mo.0.1Si) and SiC/SiC composites with BN (boron nitride) coating has been conducted in high temperature LBE of 700 deg. C at low oxygen concentration of 6.8 x 10{sup -7} wt% and the behavior was analyzed. The sputtering technique was used to protect the steel from corrosion. The thickness of sputtering-treated layer was 21.45 {mu}m. All specimens were immersed in LBE in a pot for 1000 hours. The STBA26 (9Cr.1Mo.0.1Si) without surface treated were also tested for comparison with sputtering-treated steels. The results showed that sputtering-treated layer still remained on the base of STBA26. No penetration of LBE was observed in this layer. The layer could protect the steel from penetration of LBE. The result also showed that thin layer which contains aluminum oxide and chromium oxide was formed on the surface-treated layer, and it protected the base area. On the contrary, the penetration in base area was observed in the as received STBA26. In SiC/SiC composites, there appeared cracks in a thin surface area and LBE penetrated deeply into the material. The corrosion did not occur in this SiC/SiC composite in the high temperature LBE. (authors)

Design Study of Small Lead-Cooled Fast Reactors Using SiC Cladding and Structure

Effects of SiC cladding and structure on neutronics of reactor core for small lead-cooled fast reactors have been investigated analytically. The fuel of this reactor was uranium nitride with 235 U enrichment of 11% in inner core and 13% in outer core. The reactors were designed by optimizing the use of natural uranium blanket and nitride fuel to prolong the fuel cycle. The fuels can be used without reshuffling for 15 years. The coolant of this reactor was lead. A calculation was also conducted for steel cladding and structure type as comparison with SiC cladding and structure type. The results of calculation indicated that the neutron energy spectrum of the core using SiC was slightly softer than that using steel. The SiC type reactor was designed to have criticality at the beginning of cycle (BOC), although the steel type reactor could not have critical condition with the same size and geometry. In other words, the SiC type core can be designed smaller than the steel type core. The result of the design analysis showed that neutron flux distributions and power distribution was made flatter because the outer core enrichment was higher than inner core. The peak power densities could remain constant over the reactor operation. The consumption capability of uranium was quite high, i.e. 13% for 125 MWt reactor and 25% for 375 MWt reactor at EOC.Copyright

Design Study of 300 MWt PWR Fueled With UO2 Coated Fuel Particle

A neutronic design was performed for 300 MWt Pressurized Water Reactor (PWR) with UO2 compacts made of coated fuel particles (CFP) comparing that with sintered pellets made of UO2 powder as ordinary fuel type. UO2 CFP type was enriched 4.8% of 235 U and UO2 ordinary type was enriched 5% of 235 U. Both reactors were operated with single batch refueling system with a cycle period of 3 years. The purpose of the design was to investigate the applicability of UO2 CFP type to PWR comparing with UO2 ordinary type that commonly used for PWR. The calculation was done with SRAC (Standard Reactor Analysis Code) computer code and nuclear library of JENDL-33. The results of calculation showed that k-effective for both type of fuel could be maintained at critical condition for 3 years operation without refueling. The k-effective and the Doppler coefficients have been calculated for all types of fuel at 600 K and 900 K degrees. The results of calculation showed that for all types of fuel Doppler coefficient was negative, which was good for inherent safety characteristic. The size optimization design showed that the active core dimensions of UO2 CFP type reactor was about 2 times larger than the UO2 ordinary type reactor.Copyright