Please use this identifier to cite or link to this item: http://113.161.190.196:8080/thuvienso/handle/123456789/2097
Title: Tiểu ban A: NEUTRONICS CALCULATIONS USING MCNP6 BASED ON A CAD MODEL
Authors: Tran Thuy Duong, Nguyễn Khánh Hưng, Nguyễn Bá Vũ Chính, Nguyễn Quốc Hùng
Keywords: Reactor physic; MCNP code; SuperMC
Issue Date: 2017
Publisher: Viện Năng Lượng Nguyên Tử Việt Nam
Abstract: A new CAD model of the Training Reactor of Budapest University of Technology and Economics (BME) was developed by using SuperMC/MCAM and converted into MCNP6 input. It is very useful for our neutronics calculations by using MCNP code. We calculate some physical parameters of BME reactor as the effective multiplication factor with different control rod positions, with various water levels and temperatures of water; the effective delayed neutron fraction and neutron flux distribution. Comparison of the calculated results with experimental data were also done.
URI: http://113.161.190.196:8080/thuvienso/handle/123456789/2097
Appears in Collections:Hội nghị KHCNHN toàn quốc lần thứ 12

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