Method of analysis of the neutron flux in the core of a pressurized-water nuclear reactor.

• 1. 一种针对压水堆堆芯的三维中子通量数值模拟方法 [P] . 中国专利： CN110717275B . 2021.03.16
• 2. 一种基于轴向展开的模拟压水堆堆芯三维中子通量的方法 [P] . 中国专利： CN111523234B . 2021.10.19
• 3. Method of analysis of the neutron flux in the core of a pressurized-water nuclear reactor. [P] . 法国专利： FR1259687A . 1961-04-28

  机译： 分析压水核反应堆堆芯中子通量的方法。

• 4. Method and device in order to flatten the neutron flux axially of a pressurized-water nuclear reactor. [P] . 法国专利： FR1361744A . 1964-05-22

  机译： 为了使压水核反应堆的中子通量轴向变平的方法和装置。

• 5. Method and device in order to flatten the neutron flux axially of a pressurized-water nuclear reactor. [P] . LU44075A1 . 1963-09-17

  机译： 为了使压水核反应堆的中子通量轴向变平的方法和装置。

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• 7. Large Core Code Evaluation Working Group Benchmark Problem Four: Neutronics and Burnup Analysis of a Large Heterogeneous Fast Reactor. Part 1. Analysis of Benchmark Results [R] . Cowan, C. L., Protsik, R., Lewellen, J. W. 1984

• 1. Delayed Neutrons Energy Spectrum Flux Profile of Nuclear Materials in Ghana’s Miniature Neutron Source Reactor Core [J] . R.B.M. Sogbadji ,R.G. Abrefah ,E. Ampomah-Amoako . 核科学与技术国际期刊（英文） . 2011,第2期
• 2. Measurement of the Energy Spectrum of the Neutrons inside the Neutron Flux Trap Assembled in the Center of the Reactor Core IPEN/MB-01 [J] . Ulysses d＇Utra Bitelli ,Luiz Ernesto Credidio Mura ,Diogo Feliciano dos Santos . 能源与动力工程 . 2014,第011期
• 3. Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana’S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty [J] . R.B.M. Sogbadji ,B.J.B. Nyarko ,E.H.K. Akaho . 核科学与技术国际期刊（英文） . 2011,第2期
• 4. 压水堆堆芯功率分布在线监测计算中的探测器失效诊断与处理方法 [C] . Li Zhuo ,李茁 ,Wu Hongchun . CORPHY-2016第十六届反应堆数值计算和粒子输运学术会议暨2016年反应堆物理会议 . 2016
• 5. 压水核反应堆堆芯燃料棒热工数值计算与研究 [A] . 张功伟 . 2017