Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects

UE Humphrey, MU Khandaker - Renewable and Sustainable Energy …, 2018 - Elsevier
This paper presented a review on the past, present and the future of thorium fuel cycle. The
aim of this study is to evaluate the developments in thorium fuel cycle, looking at the …

Minimization of the fission product waste by using thorium based fuel instead of uranium dioxide

AA Galahom - Nuclear Engineering and Design, 2017 - Elsevier
This research discusses the neutronic characteristics of VVER-1200 assembly fueled with
five different fuel types based on thorium. These types of fuel based on mixing thorium as a …

Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis

SB Alam, D Kumar, B Almutairi, PK Bhowmik… - … Engineering and Design, 2019 - Elsevier
In an effort to de-carbonise commercial freight ship**, there is growing interest in the
possibility of using nuclear propulsion systems. In this reactor physics study, we seek to …

Investigation of different burnable absorbers effects on the neutronic characteristics of PWR assembly

AA Galahom - Annals of Nuclear Energy, 2016 - Elsevier
There is an urgent need to find compact burnable BA materials as an alternative to the
traditional materials (B4C and Ag–In–Cd). These materials must possess higher density …

Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part II: Whole-core analysis

SB Alam, T Ridwan, D Kumar, B Almutairi… - … Engineering and Design, 2019 - Elsevier
Civil marine reactors face a unique set of design challenges. These include requirements for
a small core size and long core lifetime, a 20% cap on fissile loading, and limitations on …

Study of the possibility of using Europium and Pyrex alloy as burnable absorber in PWR

AA Galahom - Annals of Nuclear Energy, 2017 - Elsevier
The pursuit for an optimum burnable absorbers (BAs) takes a great interest due to their
importance for regulating and control the reactivity of the reactor. MCNPX code is used to …

Burnup optimization of once-through molten salt reactors using enriched uranium and thorium

ML Tan, GF Zhu, ZD Zhang, Y Zou, XH Yu… - Nuclear Science and …, 2022 - Springer
The advantages of once-through molten salt reactors include readily available fuel, low
nuclear proliferation risk, and low technical difficulty. It is potentially the most easily …

Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER-1200

AA Galahom - Annals of Nuclear Energy, 2020 - Elsevier
This paper aims to reach the most optimizing design of the VVER-1200 assembly to achieve
a significant consumption of weapons-grade plutonium (wgPu) vector. Different assembly …

Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium

XX Li, DY Cui, CY Zou, JH Wu, XZ Cai… - Nuclear Science and …, 2023 - Springer
To provide a reliable and comprehensive data reference for core geometry design of
graphite-moderated and low-enriched uranium fueled molten salt reactors, the influences of …

[HTML][HTML] Review of thorium-containing fuels in LWRs

MH Du Toit, F Van Niekerk, S Amirkhosravi - Progress in Nuclear Energy, 2024 - Elsevier
Stemming from a renewed interest in the suitability of thorium as fertile isotope, this study
presents an extensive survey of some of the recent advances on the use of thorium in light …