Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactor

Neutronic and burn‐up calculations of the ( ThO2‐UO2 ) pin cell benchmark using DRAGON5 and MCNP6 .2 codes with ENDF / B‐VIII .0 nuclear data library

(2021) Jamal Al Zain et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%

(2020) Joseph R. Burns et al.   ANNALS OF NUCLEAR ENERGY

Computational burnup analysis of the TRIGA Mark II research reactor fuel

(2020) Anže Pungerčič et al.   PROGRESS IN NUCLEAR ENERGY

A review of separation processes proposed for advanced fuel cycles based on technology readiness level assessments

(2019) P. Baron et al.   PROGRESS IN NUCLEAR ENERGY

Analyses and improvement of fuel temperature coefficient of rock-like oxide fuel in LWRs from neutronic aspect

(2019) Afroza Shelley   Nuclear Engineering and Technology

Minor Actinide Transmutation in GFR600

(2017) Zoltán Perkó et al.   NUCLEAR TECHNOLOGY

Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

(2016) Davide Chiesa et al.   ANNALS OF NUCLEAR ENERGY

Validation of simplified methods for fuel depletion calculations in gas-cooled fast reactors

(2013) Cecilia Martín-del-Campo et al.   ANNALS OF NUCLEAR ENERGY

MCNPX–BUCAL1 code to code verification through burnup analysis

(2013) B. El Bakkari et al.   ANNALS OF NUCLEAR ENERGY

Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor

(2013) B. Nacir et al.   ANNALS OF NUCLEAR ENERGY

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

(2011) M.B. Chadwick et al.   NUCLEAR DATA SHEETS