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DING Qian-xue, YANG Yong-wei. Application of Multigroup Monte-Carlo Method for Reactor Shielding Design[J]. Atomic Energy Science and Technology, 2010, 44(2): 197-200. DOI: 10.7538/yzk.2010.44.02.0197
Citation: DING Qian-xue, YANG Yong-wei. Application of Multigroup Monte-Carlo Method for Reactor Shielding Design[J]. Atomic Energy Science and Technology, 2010, 44(2): 197-200. DOI: 10.7538/yzk.2010.44.02.0197
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Application of Multigroup Monte-Carlo Method for Reactor Shielding Design

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  • Multigroup MCNP code calculation was made for the 10 MW High-Temperature Gas-Cooled Reactor in Tsinghua University. Multigroup crosssections were got from the DCL-75/BUGLE-80 cross-section library, using discrete angular representation and equally probable step function representation to approach real angular distribution. The results show that the multigroup MCNP and SN procedure DOT meet well.
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