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

[+] Author and Article Information
Xiong Wenbin

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: xiongwenbin@chinansc.cn

Cao Jian

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: caojian@chinansc.cn

Huang Chaoyun

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: Huangchaoyun@chinansc.cn

Bie Yewang

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: bieyewang@chinansc.cn

Wang Yanqi

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: wangyanqi@chinansc.cn

Li Jufeng

Nuclear and Radiation Safety Center,
MEP of China,
No. 54 of Hong Lian Nan Cun,
Haidian 10082, Beijing, China
e-mail: lijufeng@chinansc.cn

1Corresponding author.

2AP1000® is Westinghouse owned trademark.

Manuscript received September 27, 2017; final manuscript received February 27, 2018; published online May 16, 2018. Assoc. Editor: Milorad Dzodzo.

ASME J of Nuclear Rad Sci 4(3), 031018 (May 16, 2018) (5 pages) Paper No: NERS-17-1132; doi: 10.1115/1.4039596 History: Received September 27, 2017; Revised February 27, 2018

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 design control document (DCD, Rev. 19) of the AP1000 Nuclear Power Plant, which has been submitted to the nuclear regulatory commission (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 model will be modified according to the actual reactor core arrangement, such as AP1000 reactors at China's Sanmen and Haiyang sites, and then compared with the commissioning test results in the future.

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References

NRC, 2011, “ Westinghouse AP1000 Design Control Document Rev. 19,” U.S. Nuclear Regulatory Commission, Washington, DC, accessed June 21, 2011, http://www.nrc.gov/docs/ML1117/ML11171A500.html
Briesmeister, J. F. , 1993, “ MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A,” Los Alamos National Laboratory, Los Alamos, NM, Technical Report No. LA-12625.
Godfrey, A. T. , 2014, “ VERA Core Physics Benchmark Progression Problem Specifications,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No. CASL-U-2012-0131-004. https://www.casl.gov/sites/default/files/docs/CASL-U-2012-0131-004.pdf
Franceschini, F. , Godfrey, A. , Kulesza, J. , and Oelrich, R. , 2014, “ Zero Power Physics Test Simulations for the AP1000® PWR,” Westinghouse, Pittsburgh, PA, Report No. CASL-U-2014-0012-001.
Freudenreich, W. E. , Gruppelaar, H. , Hogenbirk, A. , and Koning, A. J. , 1998, “ Accelerator Driven Systems TH-ADS Benchmark Calculations,” ECN-Nuclear Research Section, Nuclear & Reactor Physics, Petten, The Netherlands, Report No. ECN-R-97-012. https://www.researchgate.net/publication/299347947_Accelerator-driven-systems_TH-ADS_benchmark_calculations_Results_of_stage_1
Mohapatra, D. K. , Sunny, C. S. , Mohanakrishnan, P. , and Subbaiah, K. V. , 2004, “ Monte Carlo Modeling of KAMINI,” Ann. Nucl. Energy, 31(18), pp. 2185–2194. [CrossRef]
Roger, B. , 2009, “ Criticality Calculations With MCNP5: A Primer,” Los Alamos National Laboratory, Los Alamos, NM, Report No. LA-UR-09-00380.
Branislav, V. , Jakub, L. , Gabriel, F. , Jan, H. , Róbert, H. , Martin, P. , Vladimír, S. , and Juraj, Š. , 2014, “ Temperature Coefficients Calculation for the First Fuel Loading of NPP Mochovce 3–4,” Ann. Nucl. Energy, 63, pp. 646–652. [CrossRef]

Figures

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Fig. 6

Boron concentrations versus keff in initial reactor core of AP1000

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Fig. 5

The position of control rods in AP1000 core

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Fig. 4

Burnable absorber assembly arrangement in the reactor core

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Fig. 3

Integral fuel burnable absorbers rod arrangement within the fuel assembly

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Fig. 2

Positions of Pyrex rods in fuel assemblies

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Fig. 1

Whole-core modeling process by MCNP

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