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Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

[+] Author Affiliations
Xiong Wen-bin, Yan Xiu-ping, Wang Bo, Wang Zhan-yong, Bie Ye-wang, Zhang Bo-ping, Yang Ming, Chen Ci, Cai Ning

Nuclear and Radiation Safety Center, MEP, Beijing, China

Paper No. ICONE25-67727, pp. V003T02A063; 6 pages
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5781-6
  • Copyright © 2017 by ASME


This study investigates the reactor core physical properties of the AP1000, which applies the MCNP4a program to model the AP1000 reactor core with the parameters and data from the DCD (19th Edition) of the AP1000 Nuclear Power Plant, which has been submitted to the NRC. The model is applied to calculate and verify the physical parameters of AP1000 core design. The results match well with the design values in the DCD of the AP1000 nuclear power plant. The design values have been calculated by the KENO-Va program, which proves the correctness of the MCNP model. The model will be improved and applied for safety review and verification analysis of AP1000 nuclear power plant in the future.

Copyright © 2017 by ASME
Topics: Design



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