Pneumatic device for the absolute measurement of the thermal neutron flux in the active part of the reactors, atomic

• 1. 锗材料在检测反应堆热中子平均通量密度中的应用、反应堆热中子平均通量密度的检测方法 [P] . 中国专利： CN113838588A . 2021-12-24
• 2. 一种用于BNCT仿真水模内部的热中子通量三维分布测量系统 [P] . 中国专利： CN113640856A . 2021-11-12
• 3. METHOD grading measurement channel neutron flux density in a nuclear reactor in absolute power units [P] . 俄罗斯专利： RU2005137252A . 2007-06-10

  机译： 用绝对功率单位对核反应堆中测量通道中子通量密度进行分级的方法

• 4. Atomic reactor with zones of more rapid and thermal neutron flux. [P] . 德国专利： DE1868396U . 1963-03-07

  机译： 具有更快中子通量和热中子通量的原子反应堆。

• 5. Device for measurement of the thermal neutron flux of a nuclear reactor [P] . 德国专利： DE1139587B . 1962-11-15

  机译： 核反应堆热中子通量测量装置

• 1. Flux measurements for a DD neutron generator using neutron activation analysis [J] . Walid A.Metwally, Samar EI-Sayed, Ahmad Ababneh, 核技术（英文版） . 2018,第004期
• 2. MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons [J] . BAI Yunfei, WANG Dezhong, MAUERHOFER Eric, 核技术：英文版 . 2010,第001期
• 3. Simultaneous Measurements of Nuclear Heating and Thermal Neutron Flux Obtained with the CALMOS-2 Measurement Device inside the OSIRIS Reactor [C] . Hubert Carcreff, Laurent Salmon, Valerie Lepeltier, Reactor Dosimetry(STP 1608) . 2018
• 4. Accurate determination of thermal neutron flux: A critical step in the measurement of the neutron lifetime. [D] . Richardson, Jonathan Mayhew. 1993
• 5. An Absolute Calibration of the National Bureau of Standards Thermal Neutron Flux [O] . E. J. Axton 1963
• 6. Last Improvements of the CALMOS Calorimeter Dedicated to Thermal Neutron Flux and Nuclear Heating Measurements inside the OSIRIS Reactor [O] . H. Carcreff, L. Salmon, V. Lepeltier, 2018
• 7. Fast-Neutron Spectrum and Absolute Fast Flux Measurements in TR-1 Reactor Core and Its Reflector [R] . Isyar, A., Ertek, C. 1979

• 1. 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
• 2. 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
• 3. Thermally induced gelation of alumina shaping-neutron scattering and rheological measurements [J] . Papiya Biswas ,Kotikalapudi Rajeswari ,Somasani Chaitanya . 无机化学期刊（英文） . 2013,第2期
• 4. 二氧化铀辐照重结构试验模拟装置热中子通量测量和计算 [C] . 张坚 . 中国核学会计算物理学会第十届反应堆数值计算和粒子输运学术会议暨2004年反应堆物理会议 . 2004
• 5. 反应堆热中子成像装置准直系统模拟设计 [A] . 李欣 . 2017