spallation target
Recently Published Documents


TOTAL DOCUMENTS

171
(FIVE YEARS 32)

H-INDEX

15
(FIVE YEARS 1)

Author(s):  
R. Esposito ◽  
M. Calviani ◽  
O. Aberle ◽  
M. Barbagallo ◽  
D. Cano-Ott ◽  
...  

2021 ◽  
Vol 32 (9) ◽  
Author(s):  
Wei-Wei Qiu ◽  
Wu Sun ◽  
Jun Su
Keyword(s):  

Author(s):  
Matthew Scheel ◽  
Keith Woloshun ◽  
Eric Olivas

Abstract The next-generation neutron spallation target station, the Target-Moderator-Reflector System (TMRS) Mk. IV, will be installed in 2021. This iteration features an unprecedented, water-cooled, third internal target aptly named the Upper Target. With the Upper Target designed completely by analysis, a complementary empirical investigation was undertaken to ascertain target conformance to those computational results which deemed the cooling efficacious. Three facets of the target were designated for verification: displacement under hydraulic load, critical fluid velocities, and the characteristic heat transfer coefficient. With the potential for flow maldistribution under excessive displacements, static pressure testing was performed. Discrepancies of an order of magnitude became evident between empirical and simulated displacements, 1.499 mm vs. 0.203 mm, respectively. A closed water flow loop reproducing the flow parameters intrinsic to the TMRS Mk. IV was constructed. Utilizing particle image velocimetry, global fluid dynamics were observed to be analogous to computer simulation. Furthermore, crucial velocities such as those at the point of beam impingement were met or exceeded, thus satisfying cooling requirements by preponderance. A graphite susceptor mirroring nominal beam geometry was coupled to a solenoid coil to replicate a prodigious peak heat flux of 169 W/cm2 via induction heating. Matching peak heat flux within 3% engendered a heat transfer coefficient 80% that of simulation. Consistent with analysis, the local heat transfer coefficient sufficiently mitigated nucleate/flow boiling. In summary, the analytically-derived Upper Target design empirically demonstrated sufficient cooling despite quixotic beam conditions and unforeseen displacements.


Author(s):  
Abdesslam Lamrabet ◽  
Abdelmajid Maghnouj ◽  
Jaouad Tajmouati ◽  
Mohamed Bencheikh

2021 ◽  
pp. 109792
Author(s):  
Chia-Nien Lin ◽  
Shin-Rong Wu ◽  
Shang-Chien Wu ◽  
Der-Sheng Chao ◽  
Jenq-Horng Liang

Author(s):  
Hironari Obayashi ◽  
Hidemitsu Yoshimoto ◽  
Satoshi Kita ◽  
Kenichi Yamaki ◽  
Tao Wan ◽  
...  

Author(s):  
Toshinobu Sasa ◽  
Shigeru Saito ◽  
Hironari Obayashi ◽  
Gen Ariyoshi
Keyword(s):  

Materials ◽  
2021 ◽  
Vol 14 (6) ◽  
pp. 1393
Author(s):  
Yong Wang ◽  
Tongmin Zhang ◽  
Qing Liao ◽  
Junyuan Yang ◽  
Weigang Gu ◽  
...  

A modern Chinese ferritic/martensitic steel SIMP, is a new perspective nuclear structural material for the spallation target in accelerator driven sub-critical system. In this work, aimed at exploring the radiation resistance properties of this material, we investigate the differences between simultaneous Fe and He ions irradiation and He implantation of SIMP steel pre-irradiated by Fe self-ions. The irradiations were performed at 300 °C. The radiation-induced hardening was evaluated by nano-indentation, while the lattice disorder was investigated by transmission electron microscopy. Clear differences were found in the material microstructure after the two kinds of the ion irradiation performed. Helium cavities were observed in the co-irradiated SIMP steel, but not the case of He implantation with Fe pre-irradiation. In the same time, the size and density of Frank loops were different in the two different irradiation conditions. The reason for the different observed lattice disorders is discussed.


2021 ◽  
Vol 1024 ◽  
pp. 27-40
Author(s):  
Kenji Kikuchi

Material choices for liquid lead bismuth spallation target are some of austenitic stainless steel, ferrite martensitic steel and cold-worked austenitic stainless steel. In order to ensure materials resistance to irradiation and corrosion as well as compatibility with lead bismuth, it is appropriate to lower the incident proton current density and the process temperature, in which temperature range engineering design can control to work, especially in ADS (Accelerator-Driven nuclear transmutation System) concept. The lower limit temperature is determined from the physical melting temperature and the engineering efficiency of the steam generator involved in process control. The material related issues for liquid lead bismuth are mass loss by impinging secondary flow, wettability at the device interface for ultrasonic waves application, detachable control of the slag in the flowing system, stabilized electrical resistance between the material and the liquid lead bismuth interface. Electromagnetic fluid analyses show how flow rate relates electrical resistivity of flow channel material.


Sign in / Sign up

Export Citation Format

Share Document