Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials

A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents

(2020) Mona Ajami et al.   PROGRESS IN NUCLEAR ENERGY

Uranium nitride tristructural-isotropic fuel particle

(2020) Kurt A. Terrani et al.   JOURNAL OF NUCLEAR MATERIALS

Preparation of tetragonal zirconia microspheres as surrogate precursor for uranium nitride microspheres

(2020) Shijiao Zhao et al.   NUCLEAR ENGINEERING AND DESIGN

Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS

(2020) A. Pourrostam et al.   Nuclear Engineering and Technology

Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches

(2020) Mohamed Y.M. Mohsen et al.   PROGRESS IN NUCLEAR ENERGY

Improvement of the VVER-1200 Fuel Cycle by Introducing Thorium with Different Fissile Material in Blanket-Seed Assembly

(2019) A. Abdelghafar Galahom   NUCLEAR SCIENCE AND ENGINEERING

Evaluation of accident tolerant cladding materials in a severe accident of the BNPP

(2019) H. Ebrahimgol et al.   ANNALS OF NUCLEAR ENERGY

Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review

(2018) Wei Zhou et al.   ANNALS OF NUCLEAR ENERGY

Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors

(2018) Iyad Al-Qasir et al.   ANNALS OF NUCLEAR ENERGY

Thermal stability investigation technique for uranium nitride

(2016) V.G. Baranov et al.   ANNALS OF NUCLEAR ENERGY

Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle

(2016) F. Faghihi et al.   PROGRESS IN NUCLEAR ENERGY

A physical model for evaluating uranium nitride specific heat

(2012) V.G. Baranov et al.   JOURNAL OF NUCLEAR MATERIALS

Shut-down margin study for the next generation VVER-1000 reactor including 13×13 hexagonal annular assemblies

(2011) Farshad Faghihi et al.   ANNALS OF NUCLEAR ENERGY

Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core

(2010) S. Safaei Arshi et al.   PROGRESS IN NUCLEAR ENERGY