Shielding container for the transport and / or storage elements of burn burned with a shield against neutrons in the outer surface of the container.

• 1. 容器、中子屏蔽体用组合物和中子屏蔽体制造法 [P] . 中国专利： CN1321423C . 2007.06.13
• 2. 容器、中子屏蔽体用组合物和中子屏蔽体制造法 [P] . 中国专利： CN1692453A . 2005-11-02
• 3. SCREEN CONTAINER WITH NEUTRON SHIELDING FOR THE TRANSPORT AND / OR STORAGE OF BURNED BURNING ELEMENTS. [P] . 瑞士专利： CH643082A5 . 1984-05-15

  机译： 带中子屏蔽的屏幕容器，用于燃烧的燃烧元素的运输和/或存储。

• 4. DEVICE FOR RECEIVING, TRANSPORTING AND RADIATING SHIELDING OF CONTAINERS LOADED WITH BURNED REACTOR FUEL ELEMENTS [P] . 德国专利： DE8012618U1 . 1981-11-05

  机译： 用于接收，运输和辐射烧成的反应堆燃料元件的容器的屏蔽装置

• 5. SHIELDED CONTAINER FOR TRANSPORTING AND / OR STORING BURNED NUCLEAR FUEL ELEMENTS [P] . 法国专利： FR2454157A1 . 1980-11-07

  机译： 带屏蔽的容器，用于运输和/或存储燃烧的核燃料元素

• 1. 5-1 Introduction to Code System COUPLE3.0 for Neutron Transport and Nuclides Burn-up Analyses [J] . Yang, Yongwei, Zhang, 中国科学院近代物理研究所和兰州重离子研究装置年报：英文版 . 2015,第001期
• 2. Calculation of photon shielding properties for some neutron shielding materials [J] . A.M.El-Khayatt 核技术（英文版） . 2017,第005期
• 3. A neutronic experiment to support the design of an Indian TBM shield module for ITER [J] . H L SWAMI, V CHAUDHARI, P CHAUDHURI, 等离子体科学和技术（英文版） . 2019,第006期
• 4. Shielding effectiveness of boron-containing ores in Liaoning province of China against gamma rays and thermal neutrons [J] . Meng-Ge Dong, Xiang-Xin Xue, V.P.Singh, 核技术（英文版） . 2018,第004期
• 5. 3-5 Study on Shielding Design and Neutronics for ADS Spallation Target [J] . Jin, Jin, Luo, 中国科学院近代物理研究所和兰州重离子研究装置年报：英文版 . 2015,第001期
• 6. DEVELOPMENT OF NEUTRON SHIELDING MATERIALS FOR HIGH BURN UP NUCLEAR FUEL STORAGE FACILITIES [C] . Herve Issard International conference on structural mechanics in reactor technology;SMiRT 20 . 2011
• 7. New production development of bulk fluid (water) storage container. [D] . Kirschner, Clayton. 2007
• 8. Design and fabrication of a Nano-based neutron shield for fast neutrons from medical linear accelerators in radiation therapy [O] . Younes Afkham, Asghar Mesbahi, Abdolali Alemi, 2020
• 9. Calculations of shielding for burned-out reactor fuel elements / [O] . Stern, H. E., U.S. Atomic Energy Commission., Oak Ridge National Laboratory. 1953
• 10. Shielded Container for the Transport and Storage of Spent Fuel Elements [R] . Christ, R. 1984

• 1. MCNP应用于计算平板及乏燃料运输容器屏蔽问题的精确性验证 [C] . 徐超 ,杨健 ,郑津洋 . 中国核学会2011年年会 . 2011
• 2. 用于原子气室中实施光存储的高磁屏蔽腔的研制 [A] . 邱淑伟 . 2012