tailieunhanh - A study on the core loading pattern of the VVER-1200/V491

The VVER-1200/V491 was a selected candidate for the Ninh Thuan I Nuclear Power Plant. However, in the Feasibility Study Safety Analysis Report (FS-SAR) of the VVER-1200/V491, the core loading pattern of this reactor was not provided. To assess the safety features of the VVER1200/V491, finding the core loading patterns and verifying their safety characteristics are necessary. | Nuclear Science and Technology No. 1 2017 pp. 21-27 A study on the core loading pattern of the VVER-1200 V491 Tran Vinh Thanh1 Tran Viet Phu Nguyen Thi Dung Institute for Nuclear Science and Technology 179 Hoang Quoc Viet Ha Noi Email tranvinhthanh. vn@ Received 02 December 2016 accepted 15 April 2017 Abstract The VVER-1200 V491 was a selected candidate for the Ninh Thuan I Nuclear Power Plant. However in the Feasibility Study Safety Analysis Report FS-SAR of the VVER-1200 V491 the core loading pattern of this reactor was not provided. To assess the safety features of the VVER-1200 V491 finding the core loading patterns and verifying their safety characteristics are necessary. In this study two core loading patterns of the VVER-1200 V491 were suggested. The first loading pattern was applied from the VVER-1000 V446 and the second was searched by core loading optimization program LPO-V. The calculations for power distribution the effective multiplication factor k-eff and fuel burn-up were then calculated by SRAC code. To verify several safety parameters of loading patterns of the VVER-1200 V491 the neutron delayed fraction DNF fuel and moderator temperature feedbacks FTC and MTC were investigated and compared with the safety standards in the VVER-1200 V491 FS-SAR or the VVER-1000 V392 ISAR. Keywords VVER-1200 V491 VVER-1000 V446 loading pattern I. INTRODUCTION The VVER-1200 V491 was a candidate for the Ninh Thuan I Nuclear Power Plant NPP . Therefore studying neutronic characteristics of the VVER-1200 V491 is required for the safety assessment of this reactor. Although the arrangements of fuel rods in fuel assemblies FAs the average enrichments and numbers of FAs in the 1st fuel cycle of the VVER-1200 V491 were shown in the Feasibility Study Safety Analysis Report FS-SAR there is still lacking of the details on the active core height and the loading pattern for the 1st cycle of the VVER-1200 V491 1 . To do the core calculations of the VVER-1200 V491 .

• Năng lượng
• Loading pattern
• Nuclear Power Plant
• Neutron delayed fraction
• Moderator temperature feedbacks
• Pressurized water reactor
• Nuclear energy
• Boiling water reactor
• Loading pattern optimisation
• Simulated annealing
• Nuclear reactors
• Fuel performance
• BMC Musculoskeletal Disorders
• First metatarsal shortening
• Plantar pressure
• Finite element method
• Hallux valgus
• Transfer metatarsalgia