Procedure for the comparison of the neutron flux of a liquid moderator nuclear reactor and a nuclear reactor for the operation of the procedure

• 1. 用于模拟核反应堆中容器内流体流动的方法以及用于计算核反应堆堆芯组件的机械形变的方法，以及相关的计算机程序产品 [P] . 中国专利： CN105247622A . 2016-01-13
• 2. 用于模拟核反应堆中容器内流体流动的方法以及用于计算核反应堆堆芯组件的机械形变的方法，以及相关的计算机程序产品 [P] . 中国专利： CN105247623A . 2016-01-13
• 3. procedures for the operation of a nuclear reactor and nuclear reactor moderator and for implementation of this procedure [P] . 德国专利： DE000001236677A . 1967-03-16

  机译： 核反应堆和核反应堆主持人的运行程序以及该程序的实施

• 4. PROCEDURE FOR THE DETERMINATION OF POWER DISTRIBUTION IN THE NUCLEUS OF A NUCLEAR REACTOR AND CALIBRATION PROCEDURE OF NEUTRONIC DETECTORS AROUND THE NUCLEAR REACTOR. [P] . ES2064682T3 . 1995-02-01

  机译： 确定核反应堆核中功率分布的程序以及核反应堆周围的中子探测器的校准程序。

• 5. Procedure and device for automatic, reciprocal adjustment of the pressure of a liquid moderator in the moderator tank of a gas-cooled nuclear reactor and a cooling gas flowing through the reactor [P] . 瑞士专利： CH466446A . 1968-12-15

  机译： 自动，双向调节气冷核反应堆减速箱中液体减速器压力和流经该反应堆的冷却气体的程序和装置

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• 2. A novel digital neutron flux monitor for international thermonuclear experimental reactor [J] . Xiang ZHOU, Zihao LIU, Chao CHEN, 等离子体科学和技术（英文版） . 2018,第006期
• 3. Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor [J] . Viet-Phu Tran, Kien-Cuong Nguyen, Donny Hartanto, 核技术（英文版） . 2021,第002期
• 4. Design of Moderator Neutron for Boron Neutron Capture Therapy in Kartini Nuclear Reactor Using Monte Carlo N Particle 5 Simulation [C] . D Wahyuningsih, A Jufriadi, H D Ayu Annual Applied Science and Engineering Conference . 2018
• 5. Modeling and design of a new core-moderator assembly and neutron beam ports for the Penn State Breazeale Nuclear Reactor (PSBR) [D] . Ucar, Dundar 2013
• 6. Automation system for neutron activation analysis at the reactor IBR-2 Frank Laboratory of Neutron Physics Joint Institute for Nuclear Research Dubna Russia [O] . Sergey S. Pavlov, Andrey Yu. Dmitriev, Marina V. Frontasyeva -1
• 7. Delayed Neutrons Energy Spectrum Flux Profile of Nuclear Materials in Ghana’s Miniature Neutron Source Reactor Core [O] . R.B.M. Sogbadji, R.G. Abrefah, E. Ampomah-Amoako, 2011
• 8. POST-NEUTRON MEASUREMENTS AND CALIBRATION PROCEDURES FOR THE AIR FORCE NUCLEAR ENGINEERING TEST REACTOR [R] . Albert Nelson Tardiff 1959

• 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. Comparison of Small Modular Reactor and Large Nuclear Reactor Fuel Cost [J] . Christopher P. Pannier ,Radek Skoda . 能源与动力工程（英文） . 2014,第5期
• 3. 核反应堆中子通量测量指套管磨损涡流检测 [C] . Zhu Zhibin ,朱志斌 ,Li Qingshun . 2017远东无损检测新技术论坛 . 2017
• 4. 海洋条件下核反应堆热工水力分析程序开发 [A] . 王冰 . 2017