Measurement and Analysis of Fission Rate in Alternate Depleted Uranium/Polyethylene Shells

YAN Xiao-song; YANG Yi-wei; ZHU Tong-hua; LIU Rong; LU Xin-xin; JIANG Li

doi:10.7538/yzk.2013.47.03.0462

Atomic Energy Science and Technology > 2013 > 47(3): 462-467. > DOI: 10.7538/yzk.2013.47.03.0462

YAN Xiao-song, YANG Yi-wei, ZHU Tong-hua, LIU Rong, LU Xin-xin, JIANG Li. Measurement and Analysis of Fission Rate in Alternate Depleted Uranium/Polyethylene Shells[J]. Atomic Energy Science and Technology, 2013, 47(3): 462-467. DOI: 10.7538/yzk.2013.47.03.0462

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Measurement and Analysis of Fission Rate in Alternate Depleted Uranium/Polyethylene Shells

1.
Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, China
2.
Department of Engineering Physics, Tsinghua University, Beijing 100084, China

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Abstract

In order to check the conceptual design of the subcritical blanket in fusion-fission hybrid reactor, an integral experiment was carried out in alternate depleted uranium/polyethylene shells with 14 MeV neutron using activation technique. The ²³⁸U(n,f) and ²³⁵U(n,f) reaction rates at 90° direction to the incident D beam were determined by measuring the 293.3 keV γ ray emitted from ¹⁴³Ce which is generated by ²³⁸U(n,f) and ²³⁵U(n,f) reactions. The experiment was simulated using MCNP5 code with ENDF/B-Ⅵ library, and the calculated ²³⁸U(n,f) and ²³⁵U(n,f) reaction rates are generally 5% higher than experimental results.
- 14 MeV neutron,
- ²³⁵U fission,
- ²³⁸U fission,
- Monte Carlo simulation

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