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- Title
Neutron Flux and Th-U Conversion Ratio for Graphite-Molten Salt Reactor.
- Authors
Tang Xiaobin; Xie Qin; Yao Zeen; Chen Da
- Abstract
The molten salt reactor (MSR) is the only one liquid-fuel reactor in six candidates of Generation IV advanced nuclear reactor, which is characterized by remarkable advantages in safety, economics and sustainable development of the fissile resource and proliferation resistance of nuclear energy. A detailed computational model using the Monte Carlo code MCNP5 is set up, in order to study about radical/axis neutron flux and the influences of the reflect thickness or blanket thickness on the conversion ratio (CR) of the Th-U fuel cycle. Main results obtained in this calculation show that; (1) The neutron flux distribution of the graphite-molten zero power reactor core is relatively smooth. (2) CR will increase with the increasing of the thickness of reflector and/or the thickness of breeding region in a certain range and when it exceeds this range CR cannot get increased significantly.
- Subjects
MOLTEN salt reactors; GRAPHITE; NEUTRON flux; NUCLEAR energy; SUSTAINABLE development; MONTE Carlo method
- Publication
Journal of Nanjing University of Aeronautics & Astronautics / Nanjing Hangkong Hangtian Daxue Xuebao, 2012, Vol 44, Issue 6, p775
- ISSN
1005-2615
- Publication type
Article