Fissile material and fuel elements for neutronic reactors

• 1. 用于保持具有高温载热气体的GFR(气体快中子反应堆)型核反应堆的裂变组件的核燃料板的保持装置 [P] . 中国专利： CN101849265B . 2013.06.26
• 2. 用于保持具有高温载热气体的GFR(气体快中子反应堆)型核反应堆的裂变组件的核燃料板的保持装置 [P] . 中国专利： CN101849265A . 2010-09-29
• 3. Method of measuring the amount of material fissile by thermal neutrons and present in any arbitrary substance, particularly for controlling the state of exhaustion of fuel elements in nuclear reactors [P] . 英国专利： GB917776A . 1963-02-06

  机译： 测量由热中子裂变并存在于任意物质中的材料数量的方法，特别是用于控制核反应堆中燃料元件的耗尽状态的方法

• 4. fissile material and neutron reactor fuel elements. [P] . BE581062A . 1960-01-25

  机译： 易裂变材料和中子反应堆燃料元件。

• 5. fissile material and neutron reactor fuel elements. [P] . BE581062A1 . 1960-01-25

  机译： 易裂变材料和中子反应堆燃料元件。

• 1. Experimental Studies on the Self-Shielding Effect in Fissile Fuel Breeding Measurement in Thorium Oxide Pellets Irradiated with 14 MeV Neutrons [J] . Mitul ABHANGI, Nupur JAIN, Rajnikant MAKWANA, 等离子体科学和技术（英文版） . 2013,第002期
• 2. Fusion Reactor and Fusion Reactor Materials— Target Fuel Depletion Fraction and Energy Gain of Inertial Confinement Fusion with D-3He Advanced Fuel [J] . DENG, Baiquan, FENG, 核工业西南物理研究院年报：英文版 . 2004,第001期
• 3. Neutronic analysis of silicon carbide cladding accident-tolerant fuel assemblies in pressurized water reactors [J] . Zhi-Xiong Tan, Jie-Jin Cai 核技术（英文版） . 2019,第003期
• 4. Active Neutron Monitoring of Nuclear Fuel Cycle Fissile Materials [C] . V.F. Batyaev, M.D. Karetnikov, S.V. Sklyarov Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (conference) . 2019
• 5. AN EXPERIMENTAL STUDY OF THE NEUTRON SPECTRUM AND THE RADIAL POWER DISTRIBUTION IN A FUEL ELEMENT IN THE ILLINOIS ADVANCED TRIGA REACTOR [D] . WEAVER, WALTER LESLIE, III. 1975
• 6. Determination of element composition and extraterrestrial material occurrence in moss and lichen samples from King George Island (Antarctica) using reactor neutron activation analysis and SEM microscopy [O] . Tomasz Mróz, Katarzyna Szufa, Marina V. Frontasyeva, -1
• 7. Active Neutron Monitoring of Nuclear Fuel Cycle Fissile Materials [O] . V.F. Batyaev, M.D. Karetnikov, S.V. Sklyarov 2020
• 8. Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Joint U.S./Russian Progress Report for Fiscal Year 1997. Volume 4, Part 5 - ESADA Plutonium Program Critical Experiments: Multiregion Core Configurations. Fissile Materials Disposition Program [R] . Akkurt, H., Abdurrahman, N. M. 2001

• 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. Neutronics physics analysis of a large fluoride-salt-cooled solidfuel fast reactor with Th-based fuel [J] . Yu Peng ,Gui-Feng Zhu ,Yang Zou . 核技术：英文版 . 2017,第11期
• 3. 水泥基碳化硼材料对裂变中子屏蔽性能的模拟 [C] . ZUO Ying-hong ,左应红 ,XIE Hong-gang . 中国核学会2015年学术年会 . 2015
• 4. 核反应堆和Cf自发裂变中子源中子-γ混合辐射场剂量学的研究 [A] . 纪刚 . 2001