Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
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 wi...
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| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/2615409 |
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| author | Giang Phan Hoai-Nam Tran Kien-Cuong Nguyen Viet-Phu Tran Van-Khanh Hoang Pham Nhu Viet Ha Hoang Anh Tuan Kiet |
| author_facet | Giang Phan Hoai-Nam Tran Kien-Cuong Nguyen Viet-Phu Tran Van-Khanh Hoang Pham Nhu Viet Ha Hoang Anh Tuan Kiet |
| author_sort | Giang Phan |
| collection | DOAJ |
| description | 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. |
| format | Article |
| id | doaj-art-1a986050c1b44025a1b29fa2c620d69e |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-1a986050c1b44025a1b29fa2c620d69e2025-02-03T01:26:06ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/26154092615409Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5Giang Phan0Hoai-Nam Tran1Kien-Cuong Nguyen2Viet-Phu Tran3Van-Khanh Hoang4Pham Nhu Viet Ha5Hoang Anh Tuan Kiet6Faculty of Applied Sciences, Ton Duc Thang University, Ho Chi Minh City 700000, VietnamInstitute of Fundamental and Applied Sciences, Duy Tan University, 3 Quang Trung, Da Nang 550000, VietnamNuclear Research Institute, VINATOM, 01 Nguyen Tu Luc, Dalat, Lamdong 670000, VietnamInstitute for Nuclear Science and Technology, VINATOM, 179 Hoang Quoc Viet, Hanoi 100000, VietnamInstitute for Nuclear Science and Technology, VINATOM, 179 Hoang Quoc Viet, Hanoi 100000, VietnamInstitute for Nuclear Science and Technology, VINATOM, 179 Hoang Quoc Viet, Hanoi 100000, VietnamInstitute of Fundamental and Applied Sciences, Duy Tan University, 3 Quang Trung, Da Nang 550000, VietnamNeutronics 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.http://dx.doi.org/10.1155/2017/2615409 |
| spellingShingle | Giang Phan Hoai-Nam Tran Kien-Cuong Nguyen Viet-Phu Tran Van-Khanh Hoang Pham Nhu Viet Ha Hoang Anh Tuan Kiet Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 Science and Technology of Nuclear Installations |
| title | Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 |
| title_full | Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 |
| title_fullStr | Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 |
| title_full_unstemmed | Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 |
| title_short | Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5 |
| title_sort | comparative analysis of the dalat nuclear research reactor with heu fuel using srac and mcnp5 |
| url | http://dx.doi.org/10.1155/2017/2615409 |
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