![](/images/graphics-bg.png)
Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
Joint Authors
Tran, Hoai-Nam
Phan, Giang
Nguyen, Kien-Cuong
Tran, Viet-Phu
Hoang, Van-Khanh
Ha, Pham Nhu Viet
Kiet, Hoang Anh Tuan
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2017, Issue 2017 (31 Dec. 2017), pp.1-10, 10 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2017-12-27
Country of Publication
Egypt
No. of Pages
10
Abstract EN
Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system.
The effective multiplication factors, keff, were analyzed for the core at criticality conditions and in two cases corresponding to the complete withdrawal and the full insertion of control rods.
MCNP5 calculations were also conducted and compared to that obtained with the SRAC code.
The results show that the difference of the keff values between the codes is within 55 pcm.
Compared to the criticality conditions established in the experiments, the maximum differences of the keff values obtained from the SRAC and MCNP5 calculations are 119 pcm and 64 pcm, respectively.
The radial and axial power peaking factors are 1.334 and 1.710, respectively, in the case of no control rod insertion.
At the criticality condition these values become 1.445 and 1.832 when the control rods are partially inserted.
Compared to MCNP5 calculations, the deviation of the relative power densities is less than 4% at the fuel bundles in the middle of the core, while the maximum deviation is about 7% appearing at some peripheral bundles.
This agreement indicates the verification of the analysis models.
American Psychological Association (APA)
Phan, Giang& Tran, Hoai-Nam& Nguyen, Kien-Cuong& Tran, Viet-Phu& Hoang, Van-Khanh& Ha, Pham Nhu Viet…[et al.]. 2017. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations،Vol. 2017, no. 2017, pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
Modern Language Association (MLA)
Phan, Giang…[et al.]. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations No. 2017 (2017), pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
American Medical Association (AMA)
Phan, Giang& Tran, Hoai-Nam& Nguyen, Kien-Cuong& Tran, Viet-Phu& Hoang, Van-Khanh& Ha, Pham Nhu Viet…[et al.]. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations. 2017. Vol. 2017, no. 2017, pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1203614