The study presents the analysis of reusability ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. are taken out from pressurized water reactor CANDU fuels. For this analysis, CANDU-37 having a total fission thermal power 2156 MW is considered 14 cases previous enrichment processes analysed by burning reactor. 3-D time-dependent critical burn up calculat...

Lead Slowing-Down Spectroscopy (LSDS) is a candidate for non-destructive assay of spent nuclear fuel (SNF) [4]. Research was collaborated via the Material Protection, Accounting, and Control Technology (MPACT) campaign under the Department of Energy. Researchers include: Pacific Northwest National Laboratory (PNNL), Los Alamos National Laboratory (LANL), University of Nevada Las Vegas (UNLV), R...

Zirconia-Magnesia Inert Matrix Fuel and Waste Form: Synthesis, Characterization and Chemical Performance in an Advanced Fuel Cycle by Kiel Steven Holliday Dr. Ken Czerwinski, Examination Committee Chair Professor of Chemistry Chair of the Department of Radiochemistry University of Nevada, Las Vegas There is a significant buildup in plutonium stockpiles throughout the world, because of spent nuc...

This study compares the proliferation resistance of DUPIC (Direct Use of Spent PWR Fuel in CANDU) fuel cycle with other fuel cycle cases. The other fuel cycles considered in this study are PWR of once-through mode (PWR-OT), PWR of reprocessing mode (PWR-MOX), in which spent PWR fuel is reprocessed and recovered plutonium is used for making MOX (Mixed Oxide), CANDU with once-through mode (CANDU-...

A liquid-fueled molten salt reactor (MSR) can be flexibly designed with a broad range of power density (PD) and neutron spectrum, both which have strong impact on the breeding performance fuel cycle. In this work, thermal single fluid double-zone Th-based MSR (SD-TMSR) an improved fast (IMSFR) different PDs ranging from 40 to 300 MWth/m3 are introduced evaluate performance. The results indicate...

The use of a lead slowing-down spectrometer (LSDS) is considered as a possible option for nondestructive assay of fissile material of used nuclear fuel. The primary objective is to quantify fissile isotopes, particularly 239Pu and 235U, via a direct measurement distinguishing them through their characteristic fission spectra in the LSDS. In this paper, we present several assay measurements perf...