CFD analysis of coolant flow in the nuclear reactor VVER440 [PDF]
Applied and Computational Mechanics, 2007 The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the reactor pressure vessel (RPV) outlet and under the RPV head.
Katolický J. +3 more
doaj
On the lifetime of the first mirrors in the diagnostic systems of the international thermonuclear experimental reactor [PDF]
, 2006 Plasma diagnostic systems will be necessary tools for the future success of the International Thermonuclear Experimental Reactor (ITER) both to better understand the physics involved in magnetically confined burning plasma and for the protection of the
Temmerman, Gregory de
core +1 more source
EPJ Web of Conferences, 2016 The 2D/1D synthesis methodology has been used to calculate the fast neutron (E > 1.0 MeV) exposure to the beltline region of the reactor pressure vessel.
Lim Mi Joung +3 more
doaj +1 more source
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions
Science and Technology of Nuclear Installations, 2022 In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants.
Shilei Han +3 more
doaj +1 more source
Computational and Experimental Research in Materials and Renewable Energy, 2023 System failure in nuclear reactors can cause degradation of a reactor core, allowing melting and relocation of the corium to the lower plenum in the nuclear reactor system.
Muhamad Irfan +3 more
doaj +1 more source
Validation of RT(T0) for German reactor pressure vessel steels
, 2022 Art. 031405, 6 S.For the introduction of the new reference temperature RTT0 of the ASME Code Cases N-629 and N-631 into the German Standard KTA 3201.2, the applicability of RTT0 was validated by the reevaluation of the existing fracture toughness ...
Keim, E., Siegele, D., Nagel, G.
core +1 more source
Modelling thermal effects in agitated vessel and reactor design consideration [PDF]
, 2007 The knowledge of the heat transfer coefficient on the inner side of a heated vessel wall is of utmost importance for the design of agitated vessels. The present contribution deals with heat transfer in an agitated vessel containing non-Newtonian liquid ...
Chergui, Nacera +3 more
core
Probabilistic pressurized thermal shocks analyses for a reactor pressure vessel
, 2015 Both deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs).
Qian, Guian (author) +1 more
core +1 more source
An experimental and CFD study of liquid jet injection into a partially baffled mixing vessel: a contribution to process safety by improving the quenching of runaway reactions [PDF]
, 2008 Thermal runaway remains a problem in the process industries with poor or inadequate mixing contributing significantly to these incidents. An efficient way to quench such an uncontrolled chemical reaction is via the injection of a liquid jet containing a ...
Fletcher, David F. +3 more
core +1 more source
FastNano Liquid: An Automated Platform for Small‐Angle X‐ray Scattering‐Based Materials Discovery
Advanced Engineering Materials, EarlyView.We present FastNano Liquid, an automated small‐ and wide‐angle X‐ray scattering platform for the combined synthesis and characterization of (nano)materials. The platform is coupled to varied reactor workflows for both in situ studies of reaction kinetics and ex situ screening of synthesis conditions to support machine learning‐guided exploration ...
Pierre‐Baptiste Flandrin +16 more
wiley +1 more source