Results 31 to 40 of about 273,037 (331)
Revista Investigaciones y Aplicaciones Nucleares, 2019 With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research
José Antonio Sarta +1 more
doaj +1 more source
, 2017 There are two type of High Temperature Gas Reactor (HTGR), prismatic and pebble bed. Pebble Bed type has unique configuration because the fuels are randomly distributed inside the reactor core.
D. Irwanto, T. Setiadipura, A. Pramutadi
semanticscholar +1 more source
International Journal of Energy Research, 2021 In this paper, development and preliminary validation of an in‐house code LETHAC (lead‐based fast reactor thermal‐hydraulic analysis code) is introduced.
Shi Wei +6 more
semanticscholar +1 more source
Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor
Science and Technology of Nuclear Installations, 2021 This paper presents results of steady-state thermal-hydraulic analysis for the designed working core of the Dalat Nuclear Research Reactor (DNRR) using the PLTEMP/ANL code. The core was designed to be loaded with 92 low-enriched uranium (LEU) VVR-M2 fuel
Kien C Nguyen +4 more
semanticscholar +1 more source
Variational assimilation for xenon dynamical forecasts in neutronic using advanced background error covariance matrix modelling [PDF]
, 2013 Data assimilation method consists in combining all available pieces of information about a system to obtain optimal estimates of initial states.
Argaud, Jean-Philippe +5 more
core +4 more sources
Thermal Science, 2021 A methodology of design and analysis of thermal-hydraulic performance for a single pass 1-1 counter-current flow shell and tube heat exchanger (CCFSTHE) TEMA E type has been established.
Elmokhtar Elouardi +2 more
semanticscholar +1 more source
MATEC Web of Conferences, 2018 The lowering of the temperature graph in the lower-level heat networks is often carried out by a mixture of coolant from the return pipeline at mixing pumping stations in order to maintain the set temperature of the mixed water. In this case, part of the
Tokarev Vyacheslav, Novitsky Nikolay
doaj +1 more source
COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM
Acta Polytechnica CTU Proceedings, 2018 The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems.
Filip Osusky +4 more
doaj +1 more source
CFD Analysis of Scaled Wire-wrapped rod Bundle Cooled by LBE [PDF]
E3S Web of Conferences, 2019 Lead bismuth eutectic (LBE) is one of the most potential materials for coolant for Lead based reactor and Accelerator Driven Systems (ADS). Thermal-hydraulic behaviour of LBE in fuel assembly is a key issue for development of the systems. To get a deeper
LYU Kefeng +3 more
doaj +1 more source
Development of multi-physics calculation method in lead cooled fast reactor code system MOSASAUR
Nuclear Engineering and TechnologyA full-core three-dimensional multi-physics calculation method was researched based on the Lead cooled fast reactor (LFR) code system MOSASAUR, which is focused on both core steady-state and transient analyses of LFR. In the previous version of MOSASAUR,
Bin Zhang +3 more
doaj +1 more source