scholarly journals Benchmark specifications and data requirements for initial modeling of the China experimental fast reactor.

2010 ◽  
Author(s):  
T. H. Fanning
Keyword(s):  
Fast Reactor ◽  
China Experimental Fast Reactor ◽  
Data Requirements

CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor

2018 ◽  
Author(s):  
Jing Chen ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
Kui Zhang ◽  
Mingjun Wang ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Power Distribution ◽  
Three Dimensional ◽  
Reactor Core ◽  
Heat Removal ◽  
The Core ◽  
Computational Fluid Dynamics Cfd ◽  
Heat Removal System ◽  
China Experimental Fast Reactor ◽  
Full Core

As the first developmental step of the sodium-cooled fast reactor (SFR) in China, the pool-type China Experimental Fast Reactor (CEFR) is equipped with the openings and inter-wrapper space in the core, which act as an important part of the decay heat removal system. The accurate prediction of coolant flow in the reactor core calls for complete three-dimensional calculations. In the present study, an investigation of thermal-hydraulic behaviors in a 180° full core model similar to that of CEFR was carried out using commercial Computational Fluid Dynamics (CFD) software. The actual geometries of the peripheral core baffle, fluid channels and narrow inter-wrapper gap were built up, and numerous subassemblies (SAs) were modeled as the porous medium with appropriate resistance and radial power distribution. First, the three-dimensional flow and temperature distributions in the full core under normal operating condition are obtained and quantitatively analyzed. And then the effect of inter-wrapper flow (IWF) on heat transfer performance is evaluated. In addition, the detailed flow path and direction in local inter-wrapper space including the internal and outlet regions are captured. This work can provide some valuable understanding of the core thermal-hydraulic phenomena for the research and design of SFRs.

Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation

2020 ◽  
Vol 148 ◽  
pp. 107710
Author(s):  
Tuan Quoc Tran ◽  
Jiwon Choe ◽  
Xianan Du ◽  
Hyunsuk Lee ◽  
Deokjung Lee
Keyword(s):  
Monte Carlo ◽  
Fast Reactor ◽  
Monte Carlo Calculation ◽  
Start Up ◽  
China Experimental Fast Reactor

Probabilistic Distribution of Parameters Applied to PFM Analysis for Piping in China Experimental Fast Reactor

2013 ◽  
Author(s):  
Min Qi ◽  
Yueying Wang ◽  
Jia Liu
Keyword(s):  
Fracture Mechanics ◽  
Fast Reactor ◽  
Safety Assessment ◽  
Small Sample Size ◽  
Research Work ◽  
Assessment Method ◽  
Small Sample ◽  
Probabilistic Distribution ◽  
Structure Dimension ◽  
China Experimental Fast Reactor

The safety assessment method based on probabilistic fracture mechanics (PFM) is well applied to pressure vessel and piping. The PFM analysis is more reasonable and reliable than determinate fracture mechanics (DFM) method. In PFM analysis, the uncertainty of main assessment parameters, such as loads, material character parameters, structure dimension and defect sizes are considered to be random, and the probabilistic distribution of these parameters are determined with the theory of probability statistics. Related to the practical engineering of China experimental fast reactor (CEFR), this paper has done some research work on the parameters probabilistic distribution, and a method was given to determine the optimum fitting probabilistic distribution function of parameters applied to PFM analysis for piping in the small sample size. The work of this paper makes the foundation of the further probabilistic safety assessment of CEFR piping.

Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor

2013 ◽  
Author(s):  
Xiaoliang Chen ◽  
Zhendong Fan ◽  
Xiaoxian Chen ◽  
Dingsheng Hu
Keyword(s):  
Low Power ◽  
Neutron Spectrum ◽  
Fast Reactor ◽  
Reaction Rate ◽  
Gamma Ray ◽  
Activation Method ◽  
Activity Measurement ◽  
Axial Distribution ◽  
Rate Distribution ◽  
China Experimental Fast Reactor

China Experimental Fast Reactor (CEFR) has completed physics start-up tests in 2010 and connected the grid on 40%FP in 2011. The reaction rate distribution, neutron spectrum are some important parameters for CEFR neutron field. In order to measure these parameters some low power irradiation tests using foil activation method have been done in CEFR core. Two kinds of special irradiation test subassemblies have been developed and fabricated for irradiation in CEFR core. And a digital high purity Germanium gamma-ray spectrometer system has been established for foil activity measurement. After dozens of low power irradiation tests in CEFR core, the radial and axial distribution of 235U and 238U fission reaction rate have been measured. The distribution of 238U capture reaction rate in CEFR core was also obtained in these tests. The experimental values of reaction rate are according with the calculation values well. Neutron spectrum was measured by means of multifoil activation method. And a neutron spectrum adjusting code was also compiled to determine the neutron spectrum.

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

2013 ◽  
Author(s):  
Jin Wang ◽  
Donghui Zhang ◽  
Wenjun Hu ◽  
Lixia Ren
Keyword(s):  
Fast Reactor ◽  
Nuclear Energy ◽  
Circuit Simulation ◽  
Thermal Power ◽  
Physical Models ◽  
Primary Circuit ◽  
Cooling Channel ◽  
Simulation Code ◽  
Wide Range ◽  
China Experimental Fast Reactor

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.

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

2018 ◽  
Vol 4 (4) ◽  
Author(s):  
Bie Yewang ◽  
Zhang Donghui ◽  
Xiong Wenbin ◽  
Li Huwei ◽  
Wu Mingyu ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Detection System ◽  
Failure Detection ◽  
Advantages And Disadvantages ◽  
Transfer Capability ◽  
Fuel Failure ◽  
Design Characteristics ◽  
Failure Location ◽  
China Experimental Fast Reactor

As the first fast reactor of China, the safety of China Experimental Fast Reactor (CEFR) is extremely important, and will decide the future of Chinese fast reactor project. The fuel failure detection system of CEFR provides surveillance and protection for the first barrier-fuel cladding of CEFR, so it is one of the most important systems for the safety of CEFR. As tag gas method is an important method for fuel-failure location in fast reactor, CEFR has a medium-term and long-term plan of using this method to locating failed fuel assemblies. This paper introduces the main principle of tag gas method, summarizes the application of this method, and compares the advantages and disadvantages of each fuel failure location method. Combining the design characteristics of CEFR, this work analyzes the selection principle of tag gas isotopes and the effects on heat transfer capability of fuel element while tag gas filled in. Meanwhile, according to the detection ability of mass spectrometer and the foreign advanced utilization experiences of tag gas method, some suggestions are provided.

Numerical Simulation and Analysis of Temperature Fluctuation in Core Outlet Zone of China Experimental Fast Reactor

2013 ◽  
Author(s):  
Huanjun Zhu ◽  
Yijun Xu
Keyword(s):  
Fast Reactor ◽  
Temperature Fluctuation ◽  
Mechanical Damage ◽  
Low Frequency ◽  
Normal Operation ◽  
Large Temperature ◽  
Control Rod ◽  
Sector Model ◽  
And Control ◽  
China Experimental Fast Reactor

As for the fast reactor, the temperature fluctuation in core outlet zone in normal operation was an important and typical thermal hydraulic phenomenon. In certain conditions, these temperature fluctuations can lead to thermal-mechanical damage to the Upper Core Structures (UCS). In this paper, the temperature fluctuation in Core Outlet Region of China Experimental Fast Reactor (CEFR) was numerically simulated and researched using the CFD software FLUENT. In the simulation process, LES turbulence method was used for the turbulent model selection. For the mesh generation, 1/4 sector model was built considering the layout of the symmetry and very small-size cell was used for satisfied with the Corant number. At the same time the core outlet temperatures and flows of the coolant in each subassembly under reactor rated power was used as the boundary conditions. The simulation shows that the temperature fluctuation was mainly concentrated in the zone between the fuel subassembly and control rod assembly for the large temperature difference of these subassemblies CEFR was operated in normal conditions. The largest fluctuation amplitude was 19°C and the remarkable frequency was below 5Hz. It belongs to typically low frequency fluctuation. The conclusion was useful for further experimental work and reactor operation.

The Measurement and Analysis of CEFR Sodium Void Reactivity Effect

2013 ◽  
Author(s):  
Keyuan Zhou ◽  
Hong Yu ◽  
Yun Hu ◽  
Xiaoliang Chen ◽  
Zhi Gang ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Test Method ◽  
Test Results ◽  
Reactivity Effect ◽  
Data Support ◽  
Start Up ◽  
Measurement And Analysis ◽  
China Experimental Fast Reactor ◽  
Calculation Analysis

Measuring of Sodium Void Reactivity Effect (SVRE), one of the most important tests in China Experimental Fast Reactor (CEFR) physical start-up, is described in the paper, including test method, test results and evaluation of test results. The results met to the test requirement and the sign base of CEFR TIB Accident Special Inspect System. The calculation analysis of CEFR SVRE test has been completed, which provides data support before the test and verifies the reliability of the calculation systems after the test. The technology for analysis and measuring of SVRE in sodium-cooled fast reactor has been accumulated through the research of this test.

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