Pu recycling in a full Th-MOX PWR core. Part I: Steady state analysis

Steady-state and transient core feasibility analysis for a thorium-fuelled reduced-moderation PWR performing full transuranic recycle

“…Most rod captures are for neutron energies of around 1000 eV, so the increase in rod worth for the WATU design may be partly explained by reduced thermal neutron availability for 233 U fissions. The SDM for the WATU design is comparable to conventional PWRs (Fridman and Kliem, 2011) and is high enough that the enrichment of 10 B in B in the control rods can be reduced somewhat.…”

“…For MOX cores, this is somewhat mitigated by the lower control rod worth due to the hard neutron spectrum (Fridman and Kliem, 2011). However, in this case the rod worth is similar to or greater than that for typical PWRs due to the use of enriched B 4 C rods.…”

“…This necessitates the use of control rods with enriched B 4 C pellets to maintain adequate shutdown margin (SDM) (Fridman and Kliem, 2011).…”

Simulate the effect of integral burnable absorber on the neutronic characteristics of a PWR assembly

“…The output results are compared with a previously published data. A variation of the infinity multiplication factor K inf at different Effective Full Power per Day (EFPD) is compared with that obtained by (Fridman and Kliem 2011) as shown in Fig. 3.…”

Thorium-based mixed oxide fuel in a pressurized water reactor: A beginning of life feasibility analysis with MCNP

“…Their work is complemented by that of Tsige-Tamirat, who also used Monte Carlo techniques to study the effect of Th-MOX fuel on a PWR's reactivity safety characteristics (Tsige-Tamirat, 2011). Burnup analyses of Th-MOX fuel for Pu disposition in PWRs have been performed by others: Fridman and Kliem (2011).…”