Results 11 to 20 of about 3,559 (212)

Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model

open access: yesCase Studies in Thermal Engineering, 2022
The aim of this work is the development and testing of a simplified and fast-running model for thermomechanical analysis of a Lead-cooled Fast Reactor (LFR).
J. Centeno-Pérez   +5 more
doaj   +1 more source

Analysis of turbine pressure, feed water temperature and condenser back pressure on performance of power generation system for lead-based reactor

open access: yesCase Studies in Thermal Engineering, 2022
Lead-based reactors have high core outlet temperature and have the potential to achieve high performance of Power Generation System (PGS). The increase in the thermal performance of the PGS is really a key challenge for the lead-based reactor.
Muhammad Salman Khan, Yong Song, Chi Xu
doaj   +1 more source

Neutrons propagation in Lead: A feasibility study for experiments in the RSV TAPIRO fast research reactor [PDF]

open access: yesEPJ Web of Conferences, 2023
The increasing worldwide interest in Lead-cooled Fast Reactors (LFRs) substantiates the need to validate the analytical codes and methods used to support their design.
Fabrizio Valentina   +10 more
doaj   +1 more source

Impact of nuclear data evaluations on data assimilation for an LFR [PDF]

open access: yesEPJ Web of Conferences, 2020
The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear Energy Technology Platform that can meet future European energy needs.
Romojaro Pablo   +1 more
doaj   +1 more source

Reactor behavior comparisons for two liquid metal-cooled fast reactors during an event of loss of coolant

open access: yesCase Studies in Thermal Engineering, 2019
The aim of this paper is to present a fast-numerical tool based on the average channel approach to analyze the response of fast reactors under unprotected loss of flow events.
Alejandría-D. Pérez-Valseca   +4 more
doaj   +1 more source

Development and verification of lead-bismuth cooled fast reactor calculation code system Mosasaur

open access: yesFrontiers in Energy Research, 2023
Lead-bismuth cooled fast reactor calculation code system named MOSASAUR has been developed to meet the simulation requirements from LBFR engineering design.
Bin Zhang   +9 more
doaj   +1 more source

CORE DESIGN ACTIVITIES OF THE VERSATILE TEST REACTOR – CONCEPTUAL PHASE [PDF]

open access: yesEPJ Web of Conferences, 2021
The Versatile Test Reactor (VTR) is a new fast spectrum test reactor being developed in the United States under the direction of the US Department of Energy, Office of Nuclear Energy.
Heidet F., Roglans-Ribas J.
doaj   +1 more source

Low-power lead-cooled fast reactor for education purposes

open access: yesNuclear Energy and Technology, 2015
The possibility is examined to develop fast reactor for the purpose of implementation of research, education of undergraduate and doctoral students in handling innovative fast reactors and training specialists for atomic research centers and nuclear ...
D.S. Samokhin   +6 more
doaj   +1 more source

Design and R&D Progress of China Lead-Based Reactor for ADS Research Facility

open access: yesEngineering, 2016
In 2011, the Chinese Academy of Sciences launched an engineering project to develop an accelerator-driven subcritical system (ADS) for nuclear waste transmutation.
Yican Wu
doaj   +1 more source

In-Service Inspection & Repair strategy for newcleo Lead-cooled Fast Reactor

open access: yese-Journal of Nondestructive Testing, 2023
Newcleo is designing and building the next generation of nuclear lead-cooled fast reactors (LFRs) fueled with MOX. A fast-spectrum Small Modular Reactor of 30 MWe will be commissioned in 2030 (the Demonstrator) and a First-Of-Kind 200 MWe a few years ...
Andrea Barbensi   +3 more
doaj   +1 more source

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