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Technical Brief

Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

[+] Author and Article Information
Xiong Wenbin

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

Xie Qin

School of Nuclear Science and Technology,
University of South China,
28 Western Changshen Road,
Hengyang City 421001, Hunan Province, China
e-mail: zoid0@hotmail.com

Li Huwei

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

Yang Sengai

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

Mao Huan

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

Cao Jian

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

1Corresponding author.

Manuscript received September 3, 2017; final manuscript received December 21, 2017; published online March 5, 2018. Assoc. Editor: Juan-Luis Francois.

ASME J of Nuclear Rad Sci 4(2), 024501 (Mar 05, 2018) (4 pages) Paper No: NERS-17-1105; doi: 10.1115/1.4038999 History: Received September 03, 2017; Revised December 21, 2017

The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.

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References

IAEA, 2006, “Fast Reactor Database 2006 Update,” International Atomic Energy Agency, Vienna, Austria, Standard No. IAEA-TECDOC-1531. http://www-pub.iaea.org/MTCD/Publications/PDF/te_1531_web.pdf
Briesmeister, J. F. , 1993, “CNP-A General Monte Carlo N-Particle Transport Code, Version4A,” Los Alamos National Laboratory, Los Alamos, NM, Technical Report No. LA-12625.
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Fink, J. K. , and Leibowitz, L. , 1995, “Thermodynamic and Transport Properties of Sodium Liquid and Vapor,” Argonne National Laboratory, Argonne, IL, Technical Report No. ANL/RE-95/2. http://www.ne.anl.gov/eda/ANL-RE-95-2.pdf
Xu, M. , and Li, Z. H. , 2011, Physical Basis for Fast Reactor, The China Atomic Energy Publishing Media, Beijing, China.
The Engineering Department of CEFR, 2008, “Internal Calculation Report of CEFR With HND 3D (Non-Public),” China Institute of Atomic Energy, Beijing, China.
Chen, Y. Y. , Yang, Y. , Gang, Z. , XU, L. , Yang, X. Y. , Zhou, K. Y. , and Hu, D. S. , 2013, “ Measurement and Analysis of CEFR Safety and Shim Rod Worth,” Atomic Energy Sci. Technol., 47(Suppl.), pp. 92–94.

Figures

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Fig. 4

The curve of density varies with temperature of liquid sodium coolant

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Fig. 3

Three-dimensional view of whole-core of CEFR (3/4 volume view)

Grahic Jump Location
Fig. 2

The control rod assemblies and fuel assembly structures of CEFR

Grahic Jump Location
Fig. 1

The section view of whole-core model of CEFR

Grahic Jump Location
Fig. 5

The control rods' worth versus withdrawal position of control rods: SH: shim rods RE: regulating rods SA: safety rods

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