测量了角响应、径向微分响应、能量响应及球腔内中子计数率分布，并估算了有效中心。

The angular response, the radial differential response, the energy response and the distribution of neutron counting rate inside sphere cavity are measured, and the effective centre is estimated.

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在软件模型的基础上分别计算了不同能量的中子进行治疗时的肿瘤及正常组织剂量分布，并对计算结果进行了分析。

The neutron absorbed dose rate distributions for tumour and natural histiocyte are calculated respectively based on this software and the results are analyzed.

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作者在MCNP的基础上，开发了中子测井，中子通量随能量、时间分布蒙特卡罗(MC)模拟软件包。

Based on MCNP, authors developed the software package of the Monte Carlo method to simulate the neutron flux distributions with the space, energy and time for neutron logging.

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