Results 51 to 60 of about 24,364 (164)

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Science and Technology of Nuclear Installations, 2010
Decay Heat Removal (DHR) is a fundamental safety function which is often accomplished in the advanced LWRs relying on natural phenomena. A typical passive DHR system is the two-phase flow, natural circulation, closed loop system, where heat is removed by
Davide Papini, Antonio Cammi
doaj   +1 more source

Conceptual study of ferromagnetic pebbles for heat exhaust in fusion reactors with short power decay length

Nuclear Materials and Energy, 2015
Ferromagnetic pebbles are investigated as high heat flux (q∥) plasma facing components in fusion devices with short power decay length (λq) on a conceptual level.
N. Gierse, J.W. Coenen, C. Thomser, A. Panin, Ch. Linsmeier, B. Unterberg, V. Philipps   +6 more
doaj   +1 more source

Safety analysis of increase in heat removal from reactor coolant system with inadvertent operation of passive residual heat removal at no-load conditions

Nuclear Engineering and Technology, 2015
The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant
Ge Shao, Xuewu Cao
doaj   +1 more source

Investigations for the substantiation of high-temperature nuclear power generation technology using fast sodium-cooled reactor for hydrogen production and other innovative applications (Part 1)

Nuclear Energy and Technology, 2016
Neutronics and thermal physics studies of BN-VT reactor installation with 600-MW thermal power demonstrated the possibility in principle to achieve the required parameters of high-temperature fast reactor for production of large quantities of hydrogen on
S.G. Kalyakin, F.A. Kozlov, A.P. Sorokin, G.P. Bogoslovskaya, A.P. Ivanov, M.A. Konovalov, A.V. Morozov, V.Yu. Stogov   +7 more
doaj   +1 more source

Verification of the ability of safe activation of the isolated DHR loop of the ALLEGRO reactor in the event of an accident with complete loss of power

Nuclear Engineering and Technology
The development of the ALLEGRO gas-cooled demonstration reactor dates back to the early days of Generation 4 reactors. A more detailed conceptual design is currently being developed, which includes thermohydraulic studies of the reactor's safety features.
Pavel Zácha, Václav Železný
doaj   +1 more source

Research on Behavior of Natural Circulation of Coolant in Primary Circuit System of Pool Type Fast Reactor

Yuanzineng kexue jishu
Thermal-hydraulic phenomenon of coolant in the primary circuit of pool type fast reactor under accident decay heat removal conditions is complicated because the layout of direct heat exchanger.
CHENG Daoxi, ZHANG Xuefeng, DU Kaiwen, ZHAI Weiming, QI Xiaoguang, ZHOU Ping, YU Song, MA Xiaoyao, LI Ruizhi
doaj   +1 more source

Passive decay heat removal for solid breeder blanket

Passive decay heat removal for solid breeder blanket
Decay heat produced by neutron irradiation causes temperature rise of blanket under loss of cooling events. Temperature rise becomes large with increase of neutron wall loading (NWL). NWL is expected to increase in DEMO compared to ITER. The transient temperature response of solid breeder blanket was evaluated by using finite element method assuming ...
openaire  

BWR decay heat removal system appraisal

, 1978
J. E. Kelly, R. C. Erdmann
openaire   +2 more sources

Modeling and Simulation of Multi-Pulse Femtosecond Laser Ablation of WC-6Co Cemented Carbide. [PDF]

Micromachines (Basel)
Wang J, Xu H, Zhang S, Fu L.
europepmc   +1 more source

Runaway uncoupling in 2,4-dinitrophenol poisoning: Clinical and mitochondrial observations from two cases. [PDF]

Toxicol Rep
Lindeman E, Sommer T, Leffler M, Sekine S, Elmér E, Sjövall F, Wallquist W.   +6 more
europepmc   +1 more source