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基于252Cf中子源,构建了反应堆结构屏蔽材料屏蔽性能测试装置设计模型。采用MCNP程序建立了测试模型,并逐次模拟计算屏蔽性能测试装置慢化层、中子防护层、γ光子防护层厚度。对于关键的慢化层,采用Geant4程序进一步验证MCNP程序的计算结果。通过分析模拟计算获得了最优屏蔽材料及厚度分别为:慢化层材料为石蜡,厚度为8 cm;中子防护层材料为聚乙烯,厚度为38 cm;γ防护层材料为铁,厚度为11 cm。模拟实验结果表明,所设计屏蔽性能测试装置能够满足中子慢化以及中子、光子防护的需要。
Based on the 252Cf neutron source, a design model of the shield performance test device for the reactor structure was constructed. The MCNP program was used to establish a test model, and the thickness of the moderator layer, the neutron shielding layer and the γ photon shielding layer of the shielding performance testing device were simulated one after another. For critical moderators, the Geant4 program is used to further verify the MCNP program’s calculations. The optimal shielding materials and thicknesses were obtained through analysis and simulation. The material of the moderator layer was paraffin wax with a thickness of 8 cm. The material of the neutron protection layer was polyethylene with a thickness of 38 cm. The γ-protective layer was made of iron with a thickness of 11 cm. Simulation results show that the designed shielding performance test device can meet the needs of neutron moderation and neutron and photon protection.