基于输运计算方法的压水堆冷却剂<sup>16</sup>N和<sup>17</sup>N活化源项计算研究

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基于输运计算方法的压水堆冷却剂¹⁶N和¹⁷N活化源项计算研究

Science and Technology on Reactor Svstem Design Technology Laboratory, Nuclear Power institute of China, Chengdu, 610041. China

摘要: 采用二维离散纵标输运程序DORT及ENDF/BVI库计算压水堆压力容器内中子注量率分布,用自行研制的活化源项计算程序计算冷却剂¹⁶N和¹⁷N源项,并验证堆芯径向与轴向功率分布对计算结果的影响。对核电厂例题的敏感性计算对比分析结果表明,采用低泄漏或高泄漏堆芯装载方式的压水堆冷却剂¹⁶N和¹⁷N活化源项结果偏差很小。
- 输运方法 /
- 压水堆 /
- 冷却剂 /
- ¹⁶N和¹⁷N /
- 活化源项
Abstract: The two-dimensional Sn transport calculation code DORT and ENDF/BVI library are used to calculate the neutron flux distribution in PWR reactor pressure vessel,and the special activity source terms calculation code is developed and used to calculate the reactor coolant ¹⁶N and ¹⁷N activity source terms.It is used for the validation of the effect of core radial and axial power distributions.Results of sensitivity analysis indicate that it has little effect on the ¹⁶N and ¹⁷N activity source terms calculation results for low or high leakage core load mode of PWR NPP.
- Transport calculation method /
- PWR /
- Coolant /
- ¹⁶N and ¹⁷N /
- Activity source terms