Lattice optimization for graphite moderated molten salt reactors using low-enriched uranium fuel

2017 ◽  
Vol 110 ◽  
pp. 1-10 ◽  
Author(s):  
Dallas Moser ◽  
Alexander Wheeler ◽  
Ondřej Chvála
Keyword(s):  
Molten Salt ◽  
Uranium Fuel ◽  
Enriched Uranium

Preliminary Core Design and Optimization Analysis of Travelling Wave Reactor

2014 ◽  
Vol 1070-1072 ◽  
pp. 357-360
Author(s):  
Dao Xiang Shen ◽  
Yao Li Zhang ◽  
Qi Xun Guo
Keyword(s):  
Monte Carlo ◽  
Rational Design ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Travelling Wave ◽  
Optimization Analysis ◽  
Design And Optimization ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
Ignition Zone

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.

Three-Region Core Design for 200-MW(electric) Molten-Salt Reactor with Thorium-Uranium Fuel

2007 ◽  
Vol 158 (3) ◽  
pp. 348-357 ◽  
Author(s):  
Koshi Mitachi ◽  
Takahisa Yamamoto ◽  
Ritsuo Yoshioka
Keyword(s):  
Molten Salt ◽  
Molten Salt Reactor ◽  
Uranium Fuel

Delays hit conversion to low enriched uranium fuel

Physics World ◽  
2016 ◽  
Vol 29 (3) ◽  
pp. 14-14
Author(s):  
Michael Allen
Keyword(s):  
Uranium Fuel ◽  
Enriched Uranium

Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium

2018 ◽  
Vol 104 ◽  
pp. 75-84 ◽  
Author(s):  
D.Y. Cui ◽  
X.X. Li ◽  
S.P. Xia ◽  
X.C. Zhao ◽  
C.G. Yu ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Molten Salt Reactor ◽  
Enriched Uranium

Neutron-physical and heat-engineering aspects of uranium-graphite reactors loaded with enriched-uranium fuel elements

Atomic Energy ◽  
2006 ◽  
Vol 101 (2) ◽  
pp. 606-610
Author(s):  
Yu. A. Artel’nyi ◽  
P. M. Gavrilov ◽  
A. A. Tsyganov
Keyword(s):  
Heat Engineering ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
Fuel Elements
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