Research on Calculation of PWR Coolant <sup>16</sup>N and <sup>17</sup>N Activity Source Terms Based on Transport Calculation Method

HU Jian-jun; TANG Bin; YANG Bin

Mar. 2025

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HU Jian-jun, TANG Bin, YANG Bin. Research on Calculation of PWR Coolant 16N and 17N Activity Source Terms Based on Transport Calculation Method[J]. Nuclear Power Engineering, 2013, 34(5): 16-19.

Citation:

HU Jian-jun, TANG Bin, YANG Bin. Research on Calculation of PWR Coolant ¹⁶N and ¹⁷N Activity Source Terms Based on Transport Calculation Method[J]. Nuclear Power Engineering, 2013, 34(5): 16-19.

HU Jian-jun, TANG Bin, YANG Bin. Research on Calculation of PWR Coolant 16N and 17N Activity Source Terms Based on Transport Calculation Method[J]. Nuclear Power Engineering, 2013, 34(5): 16-19.

Citation:

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Research on Calculation of PWR Coolant ¹⁶N and ¹⁷N Activity Source Terms Based on Transport Calculation Method

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

Received Date: 2012-07-12
Rev Recd Date: 2013-01-30

Available Online: 2025-03-08

Abstract

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