| 300#研究堆首炉中央孔道中子通量密度计算 |
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| 引用本文： | 杨万奎,曾和荣,冷军,刘耀光.300#研究堆首炉中央孔道中子通量密度计算[J].强激光与粒子束,2012,24(12):3001-3005. |
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| 作者姓名： | 杨万奎 曾和荣 冷军 刘耀光 |
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| 作者单位： | 1.中国工程物理研究院 核物理与化学研究所, 四川 绵阳 621 900 |
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| 摘 要： | 基于MCNP程序对300#研究堆首炉堆芯进行精细建模，通过并行计算方式得到了实验临界棒位下堆芯的有效增殖因数为1.002 29，与临界值之间的相对误差为0.229%，验证了物理模型的正确性。探讨并解决了并行计算的中断与接续问题，提出了体通量计数与点探测器计数应用中的合理化建议，即对大体积空间计数时尽量使用体通量计数。计算值与实验值对比结果表明:两者在3 MW功率水平下热中子通量密度相差4.6％，符合得较好。
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| 关 键 词： | 中子反应堆 临界计算 MCNP程序 并行计算 接续运行 |
| 收稿时间： | 2012/6/26 |
Neutron flux calculation for central channel in first cycle of SPRR-300 |
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| Affiliation: | 1.Institute of Nuclear Physics and Chemistry,CAEP,P.O.Box 919-211,Mianyang 621900,China |
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| Abstract: | The physical model of the 300# swimming pool research reactor(SPRR-300) based on the Monte Carlo code MCNP has been verified. Sophisticated modeling is conducted. An effective multiplication factor value of 1.002 29 is obtained, existing a relative error of 0.229% compared with the critical value. Meanwhile, a problem comes out that the interrupt and continue-run with parallel version of MCNP doesn’t work. The problem is solved through trail and error process. A reasonable application of flux tally average over a cell and flux tally at a point is suggested, namely the former is prior to the latter to tally in big volume. Comparison between calculation results and experimental data shows that the thermal neutron flux has a deviation of 4.6% at a power level of 3 MW. That is to say, the calculated value and the experimental value agree well with each other, and the neutron flux result is dependable. |
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| Keywords: | neutron reactor criticality calculation MCNP code parallel calculation continue-run |
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