tritium breeder
Recently Published Documents


TOTAL DOCUMENTS

64
(FIVE YEARS 19)

H-INDEX

12
(FIVE YEARS 3)

2021 ◽  
Vol 410 ◽  
pp. 126960
Author(s):  
Wei Zhang ◽  
Changda Zhu ◽  
Jian Yang ◽  
Qingsong Chen ◽  
Long Wang ◽  
...  

Author(s):  
Juemin Yan ◽  
Nanlin He ◽  
Xiaojun Chen ◽  
Chengjian Xiao ◽  
Lin Jie Zhao ◽  
...  

Energies ◽  
2021 ◽  
Vol 14 (2) ◽  
pp. 449
Author(s):  
Baoping Gong ◽  
Hao Cheng ◽  
Yongjin Feng ◽  
Xiaofang Luo ◽  
Long Wang ◽  
...  

In the tritium breeding blanket of nuclear fusion reactors, the heat transfer behavior and thermal-mechanical response of the tritium breeder pebble bed are affected by the inner packing structure, which is crucial for the design and optimization of a reliable pebble bed in tritium breeding blanket. Thus, the effect of pebble size distribution and fixed wall effect on packing structure and contact force in the poly-disperse pebble bed were investigated by numerical simulation. The results show that pebble size distribution has a significant influence on the inner packing structure of pebble bed. With the increase of the dispersion of pebble size, the average porosity and the average coordination number of the poly-disperse pebble bed gradually decrease. Due to the influence of the fixed wall, the porosity distribution of the pebble bed shows an obvious wall effect. For poly-disperse pebble bed, the influenced region of the wall effect gradually decreases with the increase of the dispersion of pebble size. In addition, the gravity effect and the pebble size distribution have an obvious influence on the contact force distribution inside the poly-disperse pebble bed. The majority of the contact force are weak contact force that is less than the average contact force. Only a few of pebbles have strong contact force that is greater than average contact force. This investigation can help in analyzing the pebble crushing characteristics and the thermal hydraulic analysis in the poly-disperse tritium breeder pebble bed.


2021 ◽  
Vol 4 (1) ◽  
pp. 921-926
Author(s):  
Juemin Yan ◽  
Nanlin He ◽  
Xiaojun Chen ◽  
Chengjian Xiao ◽  
LinJie Zhao ◽  
...  

2021 ◽  
Vol 247 ◽  
pp. 15004
Author(s):  
Ivan A. Kodeli ◽  
Maurizio Angelone ◽  
Davide Flamini

To assure tritium self-sufficiency in future fusion reactors such as DEMO the accuracy of TRP calculations has to be demonstrated within the design uncertainties. A new neutronics experiment representing a mock-up of the Water Cooled Lithium Lead (WCLL) Test Blanket Module (TBM) is under preparation at the Frascati neutron generator (FNG) with the objective to provide an experimental validation of accuracy of nuclear data and neutron transport codes for the tritium production rate (TPR) calculations. The mock-up will consist of LiPb bricks, EUROFER plates and Perspex substituting water. The mock-up will be irradiated by 14 MeV neutrons at the FNG facility, and the TPR and detector reaction rates will be measured using Li2CO3 pellets and activation foils placed at different positions up to about 55 cm inside the mock-up. Computational pre-analyses for the design of the WCLL neutronics experiment using the SUSD3D sensitivity/uncertainty (S/U) code system is described and compared with the results of some similar FNG experiments performed in the past, in particular the FNG HCPB Tritium Breeder Module Mock-up (2005) and FNG-HCLL Tritium Breeder Module Mock-up (2009). The objective of the pre-analysis is to provide the calculated nuclear responses including the uncertainties due to the uncertainties in nuclear data and thus contributes to the optimisation of the design of the experimental set-up.


2021 ◽  
pp. 867-914
Author(s):  
Biranchi M. Tripathi ◽  
A. K. Tyagi ◽  
Deep Prakash

Sign in / Sign up

Export Citation Format

Share Document