Experimental results from the VENUS-F critical reference state for the GUINEVERE Accelerator Driven System project

2011 ◽  
Author(s):  
W. Uyttenhove ◽  
P. Baeten ◽  
G. Ban ◽  
A. Billebaud ◽  
S. Chabod ◽  
...  
Keyword(s):  
Experimental Results ◽  
Reference State ◽  
Driven System ◽  
Accelerator Driven System ◽  
System Project

Experimental Results From the VENUS-F Critical Reference State for the GUINEVERE Accelerator Driven System Project

2012 ◽  
Vol 59 (6) ◽  
pp. 3194-3200 ◽  
Author(s):  
W. Uyttenhove ◽  
P. Baeten ◽  
G. Ban ◽  
A. Billebaud ◽  
S. Chabod ◽  
...  
Keyword(s):  
Experimental Results ◽  
Reference State ◽  
Driven System ◽  
Accelerator Driven System ◽  
System Project

Code Development and Target Station Design for Chinese Accelerator-Driven System Project

2016 ◽  
Vol 183 (1) ◽  
pp. 107-115 ◽  
Author(s):  
Han-Jie Cai ◽  
Fen Fu ◽  
Jian-Yang Li ◽  
Ya-Ling Zhang ◽  
Xun-Chao Zhang ◽  
...  
Keyword(s):  
Target Station ◽  
Driven System ◽  
Accelerator Driven System ◽  
System Project ◽  
Code Development

Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN

2014 ◽  
Author(s):  
Yonghong Tian ◽  
Wenxi Tian ◽  
Zhaoming Meng ◽  
Yingwei Wu ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Experimental Results ◽  
Inherent Safety ◽  
Nuclear Wastes ◽  
Light Water ◽  
Driven System ◽  
Channel Analysis ◽  
Accelerator Driven System ◽  
Gen Iv ◽  
Good Agreement

Lead-bismuth eutectic (LBE) cooled fast reactor, one of the six types of reactors in Gen-IV, has very good inherent safety and significant advantages in reducing and burning nuclear wastes, enhancing economy. Also LBE cooled accelerator driven system (ADS) has been a very innovative and potential waste burner. COBRA-EN is a mature, stable and widely-used sub-channel analysis code for light water cooled reactor but it couldn’t be applied in Pb-Bi-cooled reactor directly. Some modifications were made for COBRA-EN in the present work, then the code was named COBRA-PB and was suitable for the sub-channel analysis of Pb-Bi-cooled reactor. The modified code was verified and validated with CFX and experimental results. There was a good agreement between the two results. Then sub-channel analysis of Pb-Bi-cooled reactor was done with the modified code.

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

Transmutation of high-level nuclear waste by means of accelerator driven system

2013 ◽  
Vol 3 (1) ◽  
pp. 60-69 ◽  
Author(s):  
Hamid Aït Abderrahim ◽  
Didier De Bruyn ◽  
Gert Van den Eynde ◽  
Sidney Michiels
Keyword(s):  
Nuclear Waste ◽  
Driven System ◽  
High Level Nuclear Waste ◽  
Accelerator Driven System ◽  
High Level

Development and validation of burnup-transport code system OMCB for accelerator driven system

2017 ◽  
Vol 324 ◽  
pp. 360-371 ◽  
Author(s):  
Jin-Yang Li ◽  
Long Gu ◽  
Rui Yu ◽  
Nadezda Korepanova ◽  
Hu-Shan Xu
Keyword(s):  
Code System ◽  
Transport Code ◽  
Driven System ◽  
Accelerator Driven System ◽  
Development And Validation
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