Accelerator driven system based on plutonium subcritical reactor and 660 MeV phasotron

1999 ◽  
Author(s):  
V. A. Arkhipov ◽  
V. S. Barashenkov ◽  
V. S. Buttsev ◽  
D. Chultem ◽  
S. Yu. Dudarev ◽  
...  
Keyword(s):  
Driven System ◽  
Accelerator Driven System ◽  
Subcritical Reactor

scholarly journals Swing Reactivity Calculation of Accelerator Driven System Subcritical Reactor 100 MWth

2020 ◽  
Vol 1485 ◽  
pp. 012001
Author(s):  
Sudarmono ◽  
Suwoto ◽  
A. Rohanda ◽  
EP. Hastuti ◽  
Y. Kasezas
Keyword(s):  
Driven System ◽  
Accelerator Driven System ◽  
Subcritical Reactor

scholarly journals Thermal Analysis for the Dense Granular Target of CIADS

2016 ◽  
Vol 2016 ◽  
pp. 1-7
Author(s):  
Kang Chen ◽  
Yongwei Yang ◽  
Yucui Gao
Keyword(s):  
Thermal Conductivity ◽  
Thermal Process ◽  
Target Material ◽  
Target Area ◽  
Spallation Target ◽  
Heat Deposition ◽  
Driven System ◽  
Accelerator Driven System ◽  
Accelerated Protons ◽  
Subcritical Reactor

For the China Initiative Accelerator Driven System (CIADS), the energy of the protons is 250 MeV, and the current intensity will reach 10 milliamperes. A new concept of a dense granular spallation target is proposed for which the tungsten granules are chosen as the target material. After being bombarded with the accelerated protons from the accelerator, the tungsten granules with high-temperature flow out of the subcritical reactor and the heat is removed by the heat exchanger. One key issue of the target is to remove the 2.5 MW heat deposition safely. Another one is the heat exchange between the target and the subcritical reactor. Based on the model of effective thermal conductivity, a new thermal code is developed in Matlab. The new code is used to calculate the temperature field of the target area near active zone and it is partly verified by commercial CFD code Fluent. The result shows that the peak temperature of the target zone is nearly 740°C and the reactor and the target are proved to be uncoupled in thermal process.

scholarly journals Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

2021 ◽  
Vol 9 ◽  
Author(s):  
Guan Wang ◽  
Long Gu ◽  
Di Yun
Keyword(s):  
Performance Analysis ◽  
Fuel Element ◽  
Design Evaluation ◽  
Analysis And Design ◽  
Driven System ◽  
The Future ◽  
Accelerator Driven System ◽  
Physics Performance ◽  
Performance Analysis And Design ◽  
Subcritical Reactor

The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.

scholarly journals Simulation of transients in ads reactors in three-dimensional geometry

2021 ◽  
Vol 9 (2B) ◽  
Author(s):  
José Rafael Nicolao Carneiro ◽  
Zelmo Rodrigues De Lima ◽  
Alessandro Da Cruz Gonçalves
Keyword(s):  
Three Dimensional ◽  
Particle Accelerator ◽  
Neutron Diffusion ◽  
Delayed Neutron ◽  
Driven System ◽  
The Subject ◽  
Accelerator Driven System ◽  
Critical Reactor ◽  
New Generation ◽  
Subcritical Reactor

Accelerator-Driven System, ADS, belong to the new generation of advanced reactors being developed that promise to drastically reduce the life of radioactive waste by, for example, the transmutation process. Subcritical reactor designs of the ADS type have attracted worldwide attention and are the subject of research and development in several countries. The purpose of this work is to simulate transients associated with ADS. It adopted the neutron diffusion model that leads the spatial kinetics equations. These equations are solved by the known numerical method of finite differences. The simulations are performed considering transients related to the variations in the intensity of the proton flux provided by the particle accelerator acting in a sub-critical reactor in three-dimensional geometry for two energy groups and six groups of delayed neutron precursors.

scholarly journals Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident

Materials ◽  
2021 ◽  
Vol 14 (8) ◽  
pp. 1818
Author(s):  
Di-Si Wang ◽  
Bo Liu ◽  
Sheng Yang ◽  
Bin Xi ◽  
Long Gu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Steam Generator ◽  
Metal Flow ◽  
Maximum Temperature ◽  
Steam Generator Tube ◽  
Driven System ◽  
Fuel Assemblies ◽  
Accelerator Driven System ◽  
The Impact ◽  
Steam Bubble

China is developing an ADS (Accelerator-Driven System) research device named the China initiative accelerator-driven system (CiADS). When performing a safety analysis of this new proposed design, the core behavior during the steam generator tube rupture (SGTR) accident has to be investigated. The purpose of our research in this paper is to investigate the impact from different heating conditions and inlet steam contents on steam bubble and coolant temperature distributions in ADS fuel assemblies during a postulated SGTR accident by performing necessary computational fluid dynamics (CFD) simulations. In this research, the open source CFD calculation software OpenFOAM, together with the two-phase VOF (Volume of Fluid) model were used to simulate the steam bubble behavior in heavy liquid metal flow. The model was validated with experimental results published in the open literature. Based on our simulation results, it can be noticed that steam bubbles will accumulate at the periphery region of fuel assemblies, and the maximum temperature in fuel assembly will not overwhelm its working limit during the postulated SGTR accident when the steam content at assembly inlet is less than 15%.

Experimental benchmarks on kinetic parameters in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly

2017 ◽  
Vol 105 ◽  
pp. 346-354 ◽  
Author(s):  
Cheol Ho Pyeon ◽  
Masao Yamanaka ◽  
Tomohiro Endo ◽  
Willem Fredrik G. van Rooijen ◽  
Go Chiba
Keyword(s):  
Kinetic Parameters ◽  
Critical Assembly ◽  
Driven System ◽  
Accelerator Driven System ◽  
Mev Protons
Sign in / Sign up

Export Citation Format

Share Document