NDLI: A Study and Development of Primary Circuit Simulation Code for China Experimental Fast Reactor

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Wang, Jin Zhang, Donghui Hu, Wenjun Ren, Lixia
Copyright Year	2013
Abstract	A fast reactor is one of recommended candidates of Generation IV nuclear energy systems, which would meet wide requirements such as sustainability, safety and economics for nuclear energy development. To be the China’s first fast reactor, China Experimental Fast Reactor (CEFR) typical technical options are following: 65 MW thermal power and 20 MW electric power, three circuits of sodium-sodium-water, integrated pool type structure for the primary circuit. To establish modular simulation system for sodium fast reactor, the code which simulated the thermal-hydraulic behavior of primary circuit was developed. The physical models include reactor core, reactor vessel cooling channel, pumps, protection vessel, intermediate heat exchangers, ionization chamber cooling channel, cold sodium pool, hot sodium pool, inlet plenum, and pipes, etc. The code could compute coolant pressures, flow rates, and temperatures in the primary circuit. This module was designed for analysis of a wide range of transients. Although based on CEFR, it can treat an arbitrary arrangement of components.
Sponsorship	Nuclear Engineering Division
File Format	PDF
ISBN	9780791855799
DOI	10.1115/ICONE21-15790
Volume Number	Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
Conference Proceedings	2013 21st International Conference on Nuclear Engineering
Language	English
Publisher Date	2013-07-29
Publisher Place	Chengdu, China
Access Restriction	Subscribed
Subject Keyword	Water Temperature Circuits Electricity (physics) China Fast neutron reactors Sustainability Coolants Safety Economics Cooling Reactor vessels Vessels Heat exchangers Flow (dynamics) Ionization chambers Thermal energy Transients (dynamics) Nuclear power Simulation Sodium Generation iv reactors Pumps Pipes Sodium fast reactors
Content Type	Text
Resource Type	Article

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