Calculation on the Distribution of Ex-Core Neutron Flux during Reactor Start-Up

Chun Yu Liu; Benbicha Mohamed Elghazali

doi:10.4028/www.scientific.net/AMM.672-674.375

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HomeApplied Mechanics and MaterialsApplied Mechanics and Materials Vols. 672-674Calculation on the Distribution of Ex-Core Neutron...

Calculation on the Distribution of Ex-Core Neutron Flux during Reactor Start-Up

Abstract:

The distribution of neutron flux is simulated by MCNP code from reactor start-up to criticality when the control rods are drawn different length from reactor core on ex-core detector area of the WWER reactor of TianWan. Because physical model built is very large, in order to save calculation time, the moving process of control rod is simplified. The results of calculation show that The neutron mainly distributed in the range of 0-400cm outside the pressure vessel. The value of the relative neutron flux ex-core is maximum in the range of 110cm to 180cm, so detection effect is better when the detector is set in this region.

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Periodical:

Applied Mechanics and Materials (Volumes 672-674)

Pages:

375-378

DOI:

https://doi.org/10.4028/www.scientific.net/AMM.672-674.375

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Online since:

October 2014

Authors:

Chun Yu Liu*, Benbicha Mohamed Elghazali

Keywords:

Control Rod, MCNP, Neutron Flux

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* - Corresponding Author

References

[1] Zhang Dafa. Marine nuclear reactor operation management. Harbin, Harbin engineering university press, 2010 (in Chinese).

Google Scholar

[2] Judith F. Briesmeist. MCNPTM-A General Monte Carlo N-Particle Transport Code Verson4C. Los Alamos National Lab, NM, (2000).

Google Scholar

[3] Jiang guoyuan, Gu Yingbin. Equipment and system of WWER-1000 nuclear power plant. Beijing: Energy Press, 2009, 12: 14-22 (in Chinese).

Google Scholar

[4] Zhang Xiaomin, Zang Wenzhong, Luo Yisheng. Application of MCNP in the modeling for reactor core. Nuclear Electronics and Detection Technology, 2006, 26(2): 219-221 (in Chinese).

Google Scholar

[5] Yang Jiayin. Research on Neutron Distribution in Reactor and Design of Radiation Shielding. Harbin: Harbin Engineering University，2010 (in Chinese).

Google Scholar