Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Hai Quan Ho ◽  
Yuki Honda ◽  
Shimpei Hamamoto ◽  
Toshiaki Ishii ◽  
Shoji Takada ◽  
...  

Abstract The high temperature gas-cooled reactor (HTGR) has advantages for irradiation applications such as large space available for irradiation at reflector region and high thermal neutron spectrum with the graphite moderator. High temperature engineering test reactor (HTTR), a prismatic type of the HTGR, has been constructed to establish and upgrade the basic technologies for the HTGRs. Many irradiation regions are reserved in the HTTR to be served as a potential tool for an irradiation test reactor in order to promote innovative basic researches such as materials, fusion reactor technology, and radiation chemistry. This study shows the overview of some possible irradiation applications at the HTTRs including neutron transmutation doping silicon (NTD-Si) and Iodine-125 (125I) productions. The HTTR has possibility to produce about 40 tons of doped Si-particles per year for fabrication of spherical silicon solar cell. Besides, the HTTR could also produce about 1.8 × 105 GBq/yr of 125I isotope, comparing to 3.0 × 103 GBq of total 125I supplied in Japan in 2016.

2018 ◽  
Vol 140 ◽  
pp. 209-214 ◽  
Author(s):  
Hai Quan Ho ◽  
Yuki Honda ◽  
Shimpei Hamamoto ◽  
Toshiaki Ishii ◽  
Nozomu Fujimoto ◽  
...  

Author(s):  
Chenglong Wang ◽  
Yao Xiao ◽  
Jianjun Zhou ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
...  

The Fluoride-salt-cooled High temperature Reactor (FHR) is new reactor concept-about a decade old which is mainly on going in China and U.S. The preliminary thermal-hydraulic studies of the Fluoride salt cooled High temperature Test Reactor (FHTR) is necessary for the development of the FHR technology. In this paper, the thermal-hydraulics of FHTR (also called TMSR-SF) designed by Shanghai Instituted of Applied Physics (SINAP) is studied in different power modes. The temperature distributions of the coolant and the fuel pebble are obtained using a steady-state thermal-hydraulic analysis code for FHR. The comprehensive local flow and heat transfer are investigated by computational fluid dynamics (CFD) for the locations where may have the maximum pebble temperature based on the results from single channel analysis. The profiles of temperature, velocity, pressure and Nu of the coolant on the surface of the pebble as well as the temperature distribution of a fuel pebble are obtained and analyzed. Numerical results showed that the results of 3-D simulation are in reasonable agreement with that of single channel model and also illustrated safety operation of the preliminary designed TMSR-SF in different power mode.


1992 ◽  
Vol 99 (2) ◽  
pp. 158-168 ◽  
Author(s):  
Tatsuo Iyoku ◽  
Yoshiyuki Inagaki ◽  
Shusaku Shiozawa ◽  
Isoharu Nishiguchi

1967 ◽  
Author(s):  
L.D. Coffin ◽  
S.J. Simmons ◽  
J.R. Kosorok ◽  
C.E. Haines ◽  
W.C. Roberts

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