• Title/Summary/Keyword: radiation shielding fiber

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Development of a muon detector based on a plastic scintillator and WLS fibers to be used for muon tomography system

  • Chanwoo Park;Kyu Bom Kim;Min Kyu Baek;In-soo Kang;Seongyeon Lee;Yoon Soo Chung;Heejun Chung;Yong Hyun Chung
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.1009-1014
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    • 2023
  • Muon tomography is a useful method for monitoring special nuclear materials (SNMs) such as spent nuclear fuel inside dry cask storage. Multiple Coulomb scattering of muons can be used to provide information about the 3-dimensional structure and atomic number(Z) of the inner materials. Tomography using muons is less affected by the shielding material and less harmful to health than other measurement methods. We developed a muon detector for muon tomography, which consists of a plastic scintillator, 64 long wavelength-shifting (WLS) fibers attached to the top of the plastic scintillator, and silicon photomultipliers (SiPMs) connected to both ends of each WLS fiber. The muon detector can acquire X and Y positions simultaneously using a position determination algorithm. The design parameters of the muon detector were optimized using DETECT2000 and Geant4 simulations, and a muon detector prototype was built based on the results. Spatial resolution measurement was performed using simulations and experiments to evaluate the feasibility of the muon detector. The experimental results were in good agreement with the simulation results. The muon detector has been confirmed for use in a muon tomography system.

The Evaluation of the Characteristics of Electromagnetic Waves on CFRTP for Multimedia Instrument Applications (Multimedia 기기에의 적용을 위한 CFRTP에 대한 전자파 특성의 평가)

  • ;Ri-ichi Murakami
    • The Journal of Korean Institute of Electromagnetic Engineering and Science
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    • v.8 no.3
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    • pp.254-263
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    • 1997
  • As the communication and electronic industry develops, it is important to study the electromagnetic shielding effectiveness (SE) of carbon fiber (CF) reinforced thermal plastics (CFRTP) against the electromagnetic (EM) radiation. In this paper the shielding effectiveness of CFRTP was measured experimentally in an electromagnetic shielding room. The resin ma- terials used were PC, PP, PEI, PMMA and PA. Experiments were carried out by using a copper box and a monopole antenna with a spectrum analyzer. From the experimental results it was found that CF was a good candidate as an electromagnetic shielding material. The sheilding effectiveness was found to be increased in the composite as the number of laminated layers of CF was increased. As the minor damage increased, the SE increased due to increasing of the plane density, transmitting thickness and reflected angle of the CF. Other characteristics of the SE depended on the material used for the resin matrix, distance of the antennas and the noise frequency band.

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A Study on Radiation Shielding for Grid-stiffened Multi-Functional Composite Structures (격자-강화된 다기능 복합재 구조체의 방사차폐에 관한 연구)

  • Jang, Tae Seong;Rhee, Juhun;Seo, Hyun-Suk;Hyun, Bum-Seok;Kim, Taig Young;Seo, Jung Ki
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.42 no.8
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    • pp.629-639
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    • 2014
  • This paper deals with an alternative multi-functional structures by using grid-stiffened composite structure with excellent bending stiffness and lightweight characteristics which is capable of easy embedding of electrical/electronic circuitry into structure. The enhancement of thermal conduction capability is made by the application of pitch-based carbon fiber. The lightweight radiation spot shielding technique is also proposed for multi-functional structures without conventional housing and the effectiveness of selective radiation shielding is validated through the proton irradiation test.

Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's Water-Water Energetic Reactor (VVER) 1000 nuclear-power-plant spent fuels

  • Rezaeian, Mahdi;Kamali, Jamshid;Ahmadi, Seyed Javad;Kiani, Mohammad Amin
    • Nuclear Engineering and Technology
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    • v.49 no.7
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    • pp.1563-1570
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    • 2017
  • In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of $epoxy/clay/B_4C$ and $epoxy/clay/B_4C/carbon$ fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of $epoxy/clay/B_4C$ instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.