Nuclear Engineering and Technology

Глобальная ядерная безопасность
Publié: (2023)

Ganendra: Majalah IPTEK Nuklir
Publié: (2018)

Urania
Publié: (2017)

Journal of Nuclear Fuel Cycle and Waste Technology
Publié: (2017)

He huaxue yu fangshe huaxue
Publié: (2021)

He jishu
Publié: (2022)

Nuclear Science and Technology Open Research
Publié: (2024)

Nuclear Materials and Energy
Publié: (2016)

Nuclear Analysis
Publié: (2025)

International Journal of Nuclear Security
Publié: (2016)

Nucleus
Publié: (2020)

Journal of Nuclear Engineering
Publié: (2021)

Radiation Physics and Engineering
Publié: (2020)

Science and Technology of Nuclear Installations
Publié: (2007)

مجله علوم و فنون هسته‌ای
Publié: (2023)

Journal of Radiation Research and Applied Sciences
Publié: (2024)

A simulation model for capacity planning of nuclear fuel plants for research reactors
par: Miguel L. N. Negro
Publié: (2021)

EPJ Nuclear Sciences & Technologies
Publié: (2016)

Journal for Peace and Nuclear Disarmament
Publié: (2018)

Revista Investigaciones y Aplicaciones Nucleares
Publié: (2020)

Quantification of effluents in the production of nuclear fuel
par: M. C. C. B. Sakai
Publié: (2021)

EUROPEAN EFFORTS TO CONTROL THE SPREAD OF ENRICHMENT AND REPROCESSING TECHNOLOGIES
par: Oliver Meier
Publié: (2012)

Long term comparison between reprocessed nuclear fuel cycles
par: F. B. G. L. Estanislau
Publié: (2022)

Power and Operations. Simondon and the Imaginaries of the Nuclear Industry
par: Ange Pottin
Publié: (2021)

A Conservative Sealed-Source Framework for Long-Term Stabilization of Fukushima Fuel Debris
par: Matsuura, Yoshihito
Publié: (2025)

Comparison of computer programs to analyze the irradiation performance of U-Mo monolithic fuel plates and UO2 cylindrical fuel rods in power reactors
par: André Luiz Candido Silva
Publié: (2021)

PRESENTATION OF THE RESULTS FOR DEUTERIUM RETENTION AND THERMAL RELEASE IN A NEW TYPE OF LOW ACTIVATION FERRITIC- -MARTENSITIC STEEL EUROFER
par: Sanja Lj. Korica
Publié: (2016)

Monitoring of Coolant Flow Rate and Velocity in the Hot Channel of the IPR-R1 TRIGA Reactor Core
par: Amir Zacarias Mesquita
Publié: (2010)

Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor
par: Aldo M. F. Lage
Publié: (2019)

Energy Science & Engineering
Publié: (2014)

Chapter Fast-Spectrum Fluoride Molten Salt Reactor (FFMSR) with Ultimately Reduced Radiotoxicity of Nuclear Wastes
par: Hirose, Yasuo
Publié: (2021)

Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal
par: Raíssa Oliveira Marques
Publié: (2020)

Experiments on One-Phase Thermally Stratified Flows in Nuclear Reactor Pipe Lines
par: Hugo Cesar Rezende
Publié: (2011)

Validation Analysis Methodology to Determine the Cadmium, Indium and Impurities Concentration in Nuclear Grade Silver-indium-cadmium Alloys
par: L. C. OLIVEIRA
Publié: (2022)

Nuclear Technology and Radiation Protection
Publié: (2010)

Potential advantages of molten salt reactor for merchant ship propulsion
par: Luiz Gonzaga de Freitas Neto
Publié: (2021)