Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

2018 ◽  
Vol 4 (2) ◽  
Author(s):  
Xiong Wenbin ◽  
Xie Qin ◽  
Li Huwei ◽  
Yang Sengai ◽  
Mao Huan ◽  
...  
Keyword(s):  
Monte Carlo ◽  
International Atomic Energy Agency ◽  
Fast Reactor ◽  
Physical Parameters ◽  
Energy Agency ◽  
Safety Review ◽  
The Core ◽  
Calculation Results ◽  
Design Values ◽  
China Experimental Fast Reactor

The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.

Simulation Calculation of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

2017 ◽  
Author(s):  
Xiong Wen-bin ◽  
Cao Jian ◽  
Xie Qin ◽  
Wang Zhan-yong ◽  
Wang Chuang ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Nuclear Safety ◽  
Core Model ◽  
Physical Parameters ◽  
Safety Review ◽  
The Core ◽  
Simulation Calculation ◽  
Calculation Results ◽  
Design Value ◽  
China Experimental Fast Reactor

The whole core model of CEFR is established according to the parameters of China Experimental Fast Reactor which are given by IAEA-TECDOC-1531, and the physical parameters of CEFR are simulated with the MCNP4a program. The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design value, which successfully demonstrates the reliability of this MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.

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

Magnetic properties of a bi-fullerene-like structure, X60-Y60, with RKKY interactions in the Blume–Capel model

2018 ◽  
Vol 32 (04) ◽  
pp. 1850031 ◽  
Author(s):  
T. Sahdane ◽  
A. Mhirech ◽  
L. Bahmad ◽  
B. Kabouchi
Keyword(s):  
Monte Carlo ◽  
Magnetic Properties ◽  
Physical Parameters ◽  
Nano Particle ◽  
Interaction Type ◽  
The Core ◽  
Spherical Surfaces ◽  
Metropolis Monte Carlo

In this paper, we study the influence of the physical parameters on the thermal and magnetic properties of a nano-particle of bi-fullerene-like structure X[Formula: see text]-Y[Formula: see text] separated by nonmagnetic spherical surfaces, using the Metropolis Monte Carlo (MC) simulations. The coupling between the two spheres containing the spins [Formula: see text] = 3/2 and the spins S = 7/2 belongs to the core and shell, respectively. This study is based on the RKKY (Ruderman–Kittel–Kasuya–Yoshida) interaction type. To complete this work, we carry out the hysteresis cycles of the studied system for different nonmagnetic surface (NMS) numbers.

Review planned for Fukushima waste-water release

Physics World ◽  
2021 ◽  
Vol 34 (10) ◽  
pp. 12ii-12ii
Author(s):  
Michael Banks
Keyword(s):  
Waste Water ◽  
International Atomic Energy Agency ◽  
Nuclear Reactor ◽  
Atomic Energy ◽  
Water Release ◽  
Energy Agency ◽  
Safety Review

The International Atomic Energy Agency (IAEA) is to conduct a safety review of the planned discharge of millions of tonnes of treated waste water from the Fukushima nuclear reactor into the ocean.

Putting Statistics Into the Statistical Energy Analysis of Automotive Vehicles

1993 ◽  
Author(s):  
Clark J. Radcliffe ◽  
Xian Li Huang
Keyword(s):  
Monte Carlo ◽  
Energy Analysis ◽  
Computational Effort ◽  
Design Tool ◽  
Physical Parameters ◽  
Statistical Energy Analysis ◽  
Mean Values ◽  
Interior Spaces ◽  
The Monte Carlo Method ◽  
Design Values

Abstract Sound and vibration transmission modeling methods are important to the design process for high quality automotive vehicles. Statistical Energy Analysis (SEA) is an emerging design tool for the automotive industry that was initially developed in the 1960’s to estimate root-mean-square sound and vibration levels in structures and interior spaces. Although developed to estimate statistical mean values, automotive design application of SEA needs the additional ability to predict statistical variances of the predicted mean values of sound and vibration. This analytical ability would allow analysis of vehicle sound and vibration response sensitivity to changes in vehicle design specifications and their statistical distributions. This paper will present an algorithm to extend the design application of the SEA method through prediction of the variances of RMS responses of vibro-acoustic automobile structures and interior spaces from variances in SEA automotive model physical parameters. The variance analysis is applied to both a simple, complete illustrative example and a more complex automotive vehicle example. Example variance results are verified through comparison with a Monte Carlo test of 2,000 SEA responses whose physical parameters were given Gaussian distributions with means at design values. Analytical predictions of the response statistics agree with the statistics generated by the Monte Carlo method but only require about 1/300 of the computational effort.

Putting Statistics into the Statistical Energy Analysis of Automotive Vehicles

1997 ◽  
Vol 119 (4) ◽  
pp. 629-634 ◽  
Author(s):  
C. J. Radcliffe ◽  
X. L. Huang
Keyword(s):  
Monte Carlo ◽  
Energy Analysis ◽  
Computational Effort ◽  
Design Tool ◽  
Physical Parameters ◽  
Statistical Energy Analysis ◽  
Mean Values ◽  
Interior Spaces ◽  
The Monte Carlo Method ◽  
Design Values

Sound and vibration transmission modeling methods are important to the design process for high quality automotive vehicles. Statistical Energy Analysis (SEA) is an emerging design tool for the automotive industry that was initially developed in the 1960’s to estimate root-mean-square sound and vibration levels in structures and interior spaces. Although developed to estimate statistical mean values, automotive design application of SEA needs the additional ability to predict statistical variances of the predicted mean values of sound and vibration. This analytical ability would allow analysis of vehicle sound and vibration response sensitivity to changes in vehicle design specifications and their statistical distributions. This paper will present an algorithm to extend the design application of the SEA method through prediction of the variances of RMS. responses of vibro-acoustic automobile structures and interior spaces from variances in SEA automotive model physical parameters. The variance analysis is applied to both a simple, complete illustrative example and a more complex automotive vehicle example. Example variance results are verified through comparison with a Monte Carlo test of 2,000 SEA responses whose physical parameters were given Gaussian distributions with means at design values. Analytical predictions of the response statistics agree with the statistics generated by the Monte Carlo method but only require about 1/300 of the computational effort.

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

2017 ◽  
Author(s):  
Xiong Wen-bin ◽  
Yan Xiu-ping ◽  
Wang Bo ◽  
Wang Zhan-yong ◽  
Bie Ye-wang ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Physical Properties ◽  
Nuclear Power ◽  
Reactor Core ◽  
Physical Parameters ◽  
Safety Review ◽  
The Future ◽  
Design Values ◽  
Ap1000 Reactor

This study investigates the reactor core physical properties of the AP1000, which applies the MCNP4a program to model the AP1000 reactor core with the parameters and data from the DCD (19th Edition) of the AP1000 Nuclear Power Plant, which has been submitted to the NRC. The model is applied to calculate and verify the physical parameters of AP1000 core design. The results match well with the design values in the DCD of the AP1000 nuclear power plant. The design values have been calculated by the KENO-Va program, which proves the correctness of the MCNP model. The model will be improved and applied for safety review and verification analysis of AP1000 nuclear power plant in the future.

Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory

2017 ◽  
Author(s):  
Hu Xiao ◽  
Chen Xiao Liang
Keyword(s):  
Neutron Source ◽  
Fast Reactor ◽  
Thermal Power ◽  
Reactor Vessel ◽  
Monte Carlo Code ◽  
Construction Time ◽  
Mcnp Simulation ◽  
The Core ◽  
China Experimental Fast Reactor ◽  
Loading Scheme

An innovative small modular sodium cooled fast reactor called S1 is designed by China Institute of Atomic Energy (CIAE). As an encapsulated nuclear source with thermal power of 3MW, S1 is characterized by small volume, light weight, high safety and sound reliability. The S1 systems adopt modularization, by which the core will be loaded in a factory and filled with sodium, then shipped to the assembled onsite, thus the construction time for S1 can be substantially reduced. In this paper, the Monte Carlo code MCNP is used to calculate the loading scheme of S1. Considering factory’s special conditions for loading and active chemical property of sodium, a special loading pattern is adopted for S1 — loading fuel first, then sodium filling. Ensure that the neutron source and detectors are well matched during loading, and detector counting rate is no less than 2cps when only neutron source but no fuel exists in the core. Three positions where the 252Cf neutron source is placed are studied in this paper: (1) at the center of the core; (2) at the middle of outside core plane; (3) at the bottom of outside the reactor vessel. Through MCNP simulation calculations and comparison of large resulting data, it finds the neutron source should be reasonably placed at the bottom of the reactor vessel where 252Cf strength is 105 s−1 neutrons, and the ex-core detectors are distributed symmetrically at the center of outside core plane; the most befitting moderator material of detector surface is methacrylate-C5H8O3. In this paper, 1/N extrapolation method is used during loading and kinds of loading schemes have been studied with reference to the principles of China experimental fast reactor (CEFR) and regulations of relevant research reactors, and 5-batch loading scheme is finally chosen as the optimal loading scheme. S1 is prepared for sodium filling at 250 °C. It shows that neutron flux variation of core can be more reliably monitored when the ex-core detectors are placed about 120cm away from the center core through MCNP simulation calculation. Such arrangement can also meet the monitoring requirements for loading and sodium filling.

scholarly journals MODELLING ASTRID-LIKE SODIUM-COOLED FAST REACTOR WITH SERPENT-DYN3D CODE SEQUENCE

2021 ◽  
Vol 247 ◽  
pp. 02028
Author(s):  
Wojciech Rydlewicz ◽  
Emil Fridman ◽  
Eugene Shwageraus
Keyword(s):  
Monte Carlo ◽  
Fuel Assembly ◽  
Fast Reactor ◽  
Power Distribution ◽  
Fast Reactors ◽  
The Core ◽  
Fuel Assemblies ◽  
Complex Core ◽  
Nodal Diffusion ◽  
Full Core

This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium-cooled Fast Reactors (SFRs) with complex core geometries, such as the ASTRIDlike design. The core is characterised by a highly heterogeneous configuration and was likely to challenge the accuracy of the Serpent-DYN3D sequence. It includes axially heterogeneous fuel assemblies, non-uniform fuel assembly heights and large sodium plena. Consequently, the influence of generation and correction methods of various homogenised, few-group crosssections (XS) on the accuracy of the full-core nodal diffusion DYN3D calculations is presented. An attempt to compare the approximate time effort spent on models preparation against the accuracy of the result is made. Results are compared to reference full-core Serpent MC (Monte Carlo) solutions. Initially, XS data was generated in Serpent using traditional methods (2D single assemblies and 2D super-cells). Full core calculations and MC simulations offered a moderate agreement. Therefore, XS generation with 2D fuel-reflector models and 3D single assembly models was verified. Super-homogenisation (SPH) factors for XS correction were applied. In conclusion, the performed work suggests that Serpent-DYN3D sequence could be used for the analysis of highly heterogeneous SFR designs similar to the studied ASTRID-like, with an only small penalty on the accuracy of the core reactivity and radial power distribution prediction. However, the XS generation route would need to include the correction with SPH factors and generation of XS with various MC models, for different core regions. At a certain point, there are diminishing returns to using more complex XS generation methods, as the accuracy of full-core deterministic calculations improves only slightly, while the time effort required increases significantly.

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