A feasibility study on fast reactor with low-enriched uranium fuel at Kyoto University Critical Assembly

2017 ◽  
Vol 100 ◽  
pp. 60-70 ◽  
Author(s):  
Song Hyun Kim ◽  
Cheol Ho Pyeon ◽  
Akito Ohizumi ◽  
Masahiro Fukushima ◽  
Kazufumi Tsujomoto ◽  
...  
1985 ◽  
Vol 22 (7) ◽  
pp. 507-520 ◽  
Author(s):  
Seiji SHIROYA ◽  
Masatoshi HAYASHI ◽  
Keiji KANDA ◽  
Toshikazu SHIBATA

2021 ◽  
Vol 6 (1) ◽  
pp. 14-31
Author(s):  
Kien Cuong Nguyenn ◽  
Hai Dang Vo Doan

Critical assembly is a very important facility to serve for fundamental reactor physics research, application of neutron source, training and education. In nuclear engineering, critical assembly is a facility for carrying out measurement of reactor physics parameters, creating benchmark problem, validation of neutron physics calculation tool in computer codes and nuclear data. Basing on concept using commercial Nuclear Power Plant (NPP) fuels such as PWR (AP-1000) and VVER-1000 fuel rods with limited 2 meter in length and fully controlled by water level, the conceptual design of the critical assembly has been carried out in neutronic, thermal hydraulics and safety analysis. Ten benchmark critical core configurations of critical assembly are established and investigated to show safety during normal opeartion and accident conditions. Design calculation results show that NPP fuels are fully adequate for critical assembly operating under nominal power 100W and having average neutron flux about 3×109 neutron/cm2.s.


Author(s):  
J. Fradera ◽  
P. Alberto ◽  
G. Moya ◽  
A. Bernad ◽  
A. Fernández

2014 ◽  
Vol 1070-1072 ◽  
pp. 357-360
Author(s):  
Dao Xiang Shen ◽  
Yao Li Zhang ◽  
Qi Xun Guo

A travelling wave reactor (TWR) is an advanced nuclear reactor which is capable of running for decades given only depleted uranium fuel, it is considered one of the most promising solutions for nonproliferation. A preliminary core design was proposed in this paper. The calculation was performed by Monte Carlo method. The burning mechanism of the reactor core design was studied. Optimization on the ignition zone was performed to reduce the amount of enriched uranium initially deployed. The results showed that the preliminary core design was feasible. The optimization analysis showed that the amount of enriched uranium could be reduced under rational design.


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