BELLA: a multi-point dynamics code for safety-informed design of fast reactors
S Bortot, E Suvdantsetseg, J Wallenius - Annals of Nuclear Energy, 2015 - Elsevier
In this paper, the multi-point dynamics code BELLA and its benchmarking with respect to
SAS4A/SASSYS-1 is described for a small fast reactor cooled with natural convection of lead …
SAS4A/SASSYS-1 is described for a small fast reactor cooled with natural convection of lead …
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors
R Bonifetto, S Dulla, P Ravetto, LS Richard… - Nuclear Engineering and …, 2013 - Elsevier
A new multi-physics simulation tool–FRENETIC (Fast REactor NEutronics/Thermal-
hydraulICs)–is presented for the quasi-3D analysis of a lead-cooled fast reactor core with …
hydraulICs)–is presented for the quasi-3D analysis of a lead-cooled fast reactor core with …
The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)
M Tesinsky, Y Zhang, J Wallenius - Annals of Nuclear Energy, 2012 - Elsevier
The Unprotected Loss-of-Flow (ULOF) transient and the Unprotected Transient-Over-Power
(UTOP) have been evaluated for the European Lead-cooled SYstem (ELSY) for americium …
(UTOP) have been evaluated for the European Lead-cooled SYstem (ELSY) for americium …
Analytical models for a small LFR core dynamics studies
Analytical models for the study of a small Lead-cooled Fast Reactor (LFR) demonstrator
(DEMO) core dynamics, in a control-oriented perspective, have been developed aimed at …
(DEMO) core dynamics, in a control-oriented perspective, have been developed aimed at …
The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel
M Tesinsky, J Wallenius, M Jolkkonen, Y Zhang - Annals of Nuclear Energy, 2012 - Elsevier
The Unprotected Loss-of-Flow transient (ULOF) and the Unprotected Transient-Over-Power
(UTOP) have been evaluated for a modified design of the European Lead-cooled SYstem …
(UTOP) have been evaluated for a modified design of the European Lead-cooled SYstem …
[图书][B] Stability analysis of a natural circulation lead-cooled fast reactor
Q Lu - 2014 - search.proquest.com
This dissertation is aimed at nuclear-coupled thermal hydraulics stability analysis of a
natural circulation lead cooled fast reactor design. The stability concerns arise from the fact …
natural circulation lead cooled fast reactor design. The stability concerns arise from the fact …
Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor
LC Juárez‐Martínez… - International Journal of …, 2021 - Wiley Online Library
Summary The HTTR‐GT/H2 plant is a nuclear power cogeneration plant for hydrogen
production. The hydrogen production is based on the thermochemical sulfur‐iodine cycle …
production. The hydrogen production is based on the thermochemical sulfur‐iodine cycle …
Transient analysis of SUNRISE-LFR with an updated version of BELLA plant simulator
A Persico - 2020 - politesi.polimi.it
This thesis work is about the dynamical behavior of advanced nuclear systems, in particular
lead-cooled fast reactors (LFRs). As they are currently under study and development, it is …
lead-cooled fast reactors (LFRs). As they are currently under study and development, it is …
Implementation of an autonomous reactivity control system in a small lead-cooled fast reactor
This paper describes the design, implementation and characterisation of an Autonomous
Reactivity Control (ARC) system in a small modular lead-cooled fast reactor. The aim of this …
Reactivity Control (ARC) system in a small modular lead-cooled fast reactor. The aim of this …