The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

Effects of Fuel Density on Reactivity Coefficients and Kinetic Parameters of Pebble Bed Reactor

“…The structural components of the reactor core such as graphite reflectors were easily modeled while the coolant in the reflector side and especially, the reactor shutdown and control systems require special effort in modeling. The modeling and calculations performed in this study were demonstrated successfully in various publications [11][12][13][14][15][16][17][18][19][20][21][22].…”

Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

“…The fissile U‐233 can be created in a reactor or accelerator by bombarding Th‐232 and then recovered from irradiated thorium via chemical separation in a nuclear reprocessing facility. U‐233 generates enough neutrons per thermal neutron (the number of fission neutrons released per neutron absorbed, Table 1) to equal or exceed its consumption 20 . In this way, U‐233 acts as a catalyst for long‐term energy production from Th‐232, and it can virtually eliminate transuranic production 2 .…”

“…According to relevant studies, (Th‐ 233 U)O 2 fuel is a practical combination capable of self‐sustaining breeding in the thermal spectrum 3,20,21 . The fissile U‐233 can be created in a reactor or accelerator by bombarding Th‐232 and then recovered from irradiated thorium via chemical separation in a nuclear reprocessing facility.…”

“…U-233 generates enough neutrons per thermal neutron (the number of fission neutrons released per neutron absorbed, Table 1) to equal or exceed its consumption. 20 In this way, U-233 acts as a catalyst for long-term energy production from Th-232, and it can virtually eliminate transuranic production. 2 Indeed, U-233 is a more interesting material than U-235.…”

“…18,19 According to relevant studies, (Th-233 U)O 2 fuel is a practical combination capable of self-sustaining breeding in the thermal spectrum. 3,20,21 The fissile U-233 can be created in a reactor or accelerator by bombarding Th-232 and then recovered from irradiated thorium via chemical separation in a nuclear reprocessing facility. U-233 generates enough neutrons per thermal neutron (the number of fission neutrons released per neutron absorbed, Table 1) to equal or exceed its consumption.…”