Chinese Physics C > 2013, Vol. 37 > Issue(12): 124001 DOI: 10.1088/1674-1137/37/12/124001

Measurement and analysis of fission rates in a spherical mockup of uranium and polyethylene

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Abstract：
Measurements of the reaction rate distribution were carried out using two kinds of Plate Micro Fission Chamber (PMFC). The first is a depleted uranium chamber and the second an enriched uranium chamber. The material in the depleted uranium chamber is strictly the same as the material in the uranium assembly. With the equation solution to conduct the isotope contribution correction, the fission rate of ²³⁸U and ²³⁵U were obtained from the fission rate of depleted uranium and enriched uranium. Then, the fission count of ²³⁸U and ²³⁵U in an individual uranium shell was obtained. In this work, MCNP5 and continuous energy cross sections ENDF/BV.0 were used for the analysis of fission rate distribution and fission count. The calculated results were compared with the experimental ones. The calculation of fission rate of DU and EU were found to agree with the measured ones within 10% except at the positions in polyethylene region and the two positions near the outer surface. Because the fission chamber was not considered in the calculation of the fission counts of ²³⁸U and ²³⁵U, the calculated results did not agree well with the experimental ones.

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ZHU Tong-Hua, YANG Chao-Wen, LU Xin-Xin, LIU Rong, HAN Zi-Jie, JIANG Li and WANG Mei. Measurement and analysis of fission rates in a spherical mockup of uranium and polyethylene[J]. Chinese Physics C, 2013, 37(12): 124001. doi: 10.1088/1674-1137/37/12/124001

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Received: 2013-02-27
Revised: 1900-01-01

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通讯作者:陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

Measurement and analysis of fission rates in a spherical mockup of uranium and polyethylene

Corresponding author:ZHU Tong-Hua,

Corresponding author:HAN Zi-Jie,

Received Date:2013-02-27

Accepted Date:1900-01-01

Available Online:2013-12-05

Abstract:Measurements of the reaction rate distribution were carried out using two kinds of Plate Micro Fission Chamber (PMFC). The first is a depleted uranium chamber and the second an enriched uranium chamber. The material in the depleted uranium chamber is strictly the same as the material in the uranium assembly. With the equation solution to conduct the isotope contribution correction, the fission rate of²³⁸U and²³⁵U were obtained from the fission rate of depleted uranium and enriched uranium. Then, the fission count of²³⁸U and²³⁵U in an individual uranium shell was obtained. In this work, MCNP5 and continuous energy cross sections ENDF/BV.0 were used for the analysis of fission rate distribution and fission count. The calculated results were compared with the experimental ones. The calculation of fission rate of DU and EU were found to agree with the measured ones within 10% except at the positions in polyethylene region and the two positions near the outer surface. Because the fission chamber was not considered in the calculation of the fission counts of²³⁸U and²³⁵U, the calculated results did not agree well with the experimental ones.

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Measurement and analysis of fission rates in a spherical mockup of uranium and polyethylene

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